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Sample records for daiichi nendo seika

  1. Report on results 1998. Research and development on fusion area. Part 1 (next generation optical substrate technology); 1998 nendo seika hokokusho. Yugo ryoiki kenkyu kaihatsu daiichi bunsatsu (jisedai hikari kiban gijutsu)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Emphasis was placed on the research on a planar apertured near-field head and a super-RENS (super-resolution near-field structure) method, as a near-field application element for replacing protruding probes, which has a number of difficult points in developing near-field recording into a practical system, and as a recording and reproducing method. The super-RENS method, as a result of the examination, has become capable of recording/detecting a mark of the minimum 60nm diameter, by the near-field, under conditions such as the most advanced optical disk size and the number of revolution of the disk. This means that a high density recording is possible which is at least 40 times as dense as a DVD (digital versatile disk). It was confirmed by an experiment that the high density was possible in the track pitch direction by the super-RENS method. As a result of the examination on the behavior of the near-field in the super-RENS disk, it revealed that signal detection by the transmitted light which had not been tried before was effective for the improvement of the performance. The smallest detectable mark size was 80nm, in which case CNR (carrier to noise ratio) was 6.4dB. These values are approximately the same level as in the signal detection by reflected light, and are insufficient to verify the superiority. (NEDO)

  2. Fukushima Daiichi Radionuclide Inventories

    Energy Technology Data Exchange (ETDEWEB)

    Cardoni, Jeffrey N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jankovsky, Zachary Kyle [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-09-01

    Radionuclide inventories are generated to permit detailed analyses of the Fukushima Daiichi meltdowns. This is necessary information for severe accident calculations, dose calculations, and source term and consequence analyses. Inventories are calculated using SCALE6 and compared to values predicted by international researchers supporting the OECD/NEA's Benchmark Study on the Accident at Fukushima Daiichi Nuclear Power Station (BSAF). Both sets of inventory information are acceptable for best-estimate analyses of the Fukushima reactors. Consistent nuclear information for severe accident codes, including radionuclide class masses and core decay powers, are also derived from the SCALE6 analyses. Key nuclide activity ratios are calculated as functions of burnup and nuclear data in order to explore the utility for nuclear forensics and support future decommissioning efforts.

  3. Fukushima Daiichi Status Report

    International Nuclear Information System (INIS)

    2012-01-01

    The IAEA issues regular status reports to the public on the current status of the Fukushima Daiichi Nuclear Power Plant, including information on environmental radiation monitoring, the status of workers, and current conditions on-site at the plant. The information cited in this report is compiled from official Japanese sources, including the Ministry of Economy, Trade and Industry (METI), the Nuclear and Industrial Safety Agency (NISA), the Ministry of Education, Culture, Sports, Science and Technology (MEXT), the Ministry of Land, Infrastructure, Transport and Tourism (MLIT), the Ministry of Health, Labour and Welfare (MHLW) and the Ministry of Foreign Affairs (MOFA) through the Japanese Permanent Mission in Vienna and the Cabinet's Office of the Prime Minister. Information is also provided by the Tokyo Electric Power Company (TEPCO), the operator of the Fukushima Daiichi Nuclear Power Plant.

  4. Achievement report for fiscal 1998 on joint research business (2/2). Photovoltaic power generation field test for public facilities; 1998 nendo kokyo shisetsu nadoyo taiyoko hatsuden field test jigyo (2/2). Kyodo kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    Photovoltaic power generation systems are experimentally installed at public facilities at various locations, and subjected to field tests in which they experience long-term operation under real loads. Mie Prefectural Iidaka Senior/Junior High School has a 10kW solar cell system installed on the south-side roof of the school house. The system is linked to an in-house transformation station and the power generated by the system is supplied to the lighting and air-conditioning facilities in the building, and surplus if any is transmitted to the Chubu Electric Power Co., Inc., system. A field test is being conducted to determine if there are usability and safety in the 10kW system. A number of like systems are undergoing field tests, installed at a comprehensive technological training center of Kyushu Electric Power Safety Association, Kongo Gakuen Senior High School, Sakata Nursery School, Taiyo Daiichi Nursery School, Minami Kindergarten, Neyagawa Ishizu Old People's Home, Co-Op Living Konan, Factory Hishimeki, Tochigi Fuji Industries, Gamo-cho Hirabayashi Public Hall, Fukuoka Prefectural Culture Complex, Yatsusugi Forest Schooling Center, Osaka Prefectural Murano Water Purification Plant, Yamanashi Institute of Environmental Sciences, Utatsu-cho Town Office, Ginga Gakuen Junior High School, etc. (NEDO)

  5. Achievement report for fiscal 1998 on joint research business (2/2). Photovoltaic power generation field test for public facilities; 1998 nendo kokyo shisetsu nadoyo taiyoko hatsuden field test jigyo (2/2). Kyodo kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    Photovoltaic power generation systems are experimentally installed at public facilities at various locations, and subjected to field tests in which they experience long-term operation under real loads. Mie Prefectural Iidaka Senior/Junior High School has a 10kW solar cell system installed on the south-side roof of the school house. The system is linked to an in-house transformation station and the power generated by the system is supplied to the lighting and air-conditioning facilities in the building, and surplus if any is transmitted to the Chubu Electric Power Co., Inc., system. A field test is being conducted to determine if there are usability and safety in the 10kW system. A number of like systems are undergoing field tests, installed at a comprehensive technological training center of Kyushu Electric Power Safety Association, Kongo Gakuen Senior High School, Sakata Nursery School, Taiyo Daiichi Nursery School, Minami Kindergarten, Neyagawa Ishizu Old People's Home, Co-Op Living Konan, Factory Hishimeki, Tochigi Fuji Industries, Gamo-cho Hirabayashi Public Hall, Fukuoka Prefectural Culture Complex, Yatsusugi Forest Schooling Center, Osaka Prefectural Murano Water Purification Plant, Yamanashi Institute of Environmental Sciences, Utatsu-cho Town Office, Ginga Gakuen Junior High School, etc. (NEDO)

  6. Fiscal 2000 regional consortium research and development project - regional new technology creation research and development. Development of micro-array for next generation gene analysis (1st fiscal year); 2000 nendo chiiki consortium kenkyu kaihatsu jigyo - chiiki shingijutsu soshutsu kenkyu kaihatsu seika hokokusho. Jisedai idenshi kaiseki micro array no kaihatsu (daiichi nendo)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Efforts are under way to construct a novel DNA (deoxyribonucleic acid) micro-array for gene diagnosis on the basis of technologies of laser scan type manipulation, nanometric position detection, and micro-machining. Using these technologies, structural changes to accompany reactions induced in the probe DNA deposited on an array are detected for the identification of the DNA. Activities are conducted in the four fields of (1) the study of probe DNA fixation technology, (2) development of an optical detection system, (3) detailed check of DNA micro-array performance evaluation technologies, and (4) a comprehensive survey. In field (1), gold colloid modified DNA molecules are designed and evaluated, and the fixation of DNA to substrates and technologies for integration are studied. In field (2), the gold colloid modified DNA is fixed on a thin gold film, and then a surface plasmon resonance (SPR) is observed in the wake of hybridization. Furthermore, a Brownian motion is observed of the metal particles fixed on a glass substrate via DNA. (NEDO)

  7. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium energy field / research and development of a reverse engineering system for local industrial articles (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium bun`ya / chiiki kogeihin muke reverse engineering system no kenkyu kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The paper described the fiscal 1997 result of the research on the application of local industrial article use reverse engineering (RE, it had been regarded as imitation and reproduction technology, but has recently been as a part of the production information integration). With the actual local industrial article as standard, which has features in design and was added with local traditionality, such as glass having 3D free-form surface, 3D shape information modeling technology RE is developed, and a system for direct automatic metal mold processing is established, aiming at shortening of delivery date, cost reduction and higher grade. The target of the research is Okinawa prefecture. In fiscal 1997, study was made of the speeding-up of the non-contact 3D shape information inputting (multi-point simultaneous inputting by CCD of the laser reflected light of the actual model) and the data storage technology. Cast iron was selected as molding materials, judging from reactivity/machinability with heat resistant glass. Also studied was the blend of glass materials suitable for press forming. Further, studies were proceeded with of development of intellectual cutting tools into which sensor function is integrated and of virtual reality for facilitating/accelerating the design up to metal mold manufacturing. 39 refs., 88 figs., 21 tabs.

  8. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium energy field / Development of the plasma use surface treatment process by in-situ control (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium energy bun`ya / in-situ seigyo ni yoru plasma riyo hyohi shori process no kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The paper described the fiscal 1997 result of the development. To know of in-plasma phenomena such as carburization and nitriding, a basic plasma experimental device was fabricated for quantitative measurement of reaction activity species. For the study of reaction control between plasma and substrate, a rotary analyzer type ellipsometer was fabricated as a method to detect composition and thickness of the deposit on the substrate surface. For He gas cooling after carburization and hardening, basic specifications for He gas refining/circulating system were confirmed. For perfect non-hazardous processing of exhaust gas from plasma carburization furnace, conducted was the thermodynamic computation of the process. Priority in order of the functions to be possessed as specifications for basic design of mini plant is plasma carburization, He gas cooling, and in-situ measurement. To make the most of the plasma use surface treatment as substitutes for expensive alloy elements, sliding parts/die-cast mold raw materials were carburized to measure the hardness. The Cr carbide coating technology by plasma CVD is also under study as an application example except carburization. 47 refs., 59 figs., 31 tabs.

  9. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium energy field / R and D of a task adaptation type group architecture transfer robot system, TRIPTERS (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium energy bun`ya / task tekigogata gun kosei hanso robot system TRIPTERS no kaihatsu kenkyu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The paper stated the fiscal 1997 result of the development of a task adaptation type group architecture transfer robot system (TRIPTERS) which can cope with changes in carrying task rapidly and flexibly. R and D were conducted mainly of various functional modules, the operation management technology which enables group architecture, and the basic design of a standardized transfer robot. As to the positioning, studied were the construction of the basic hardware of laser position measuring device, and the application method. Concerning the cooperative carrying, conducted were securing of positioning accuracy of matters to be carried, high speed heavy transfer control, and design of dead reckoning system. Relating to the operation management, passable areas were divided into more than one zones, and the effective path reservation method was constructed so that one and the same zone is not occupied. As to the environmental recognition/obstacle avoidance, developed were actual hour/distance acquisition equipment, and autonomous cars running according to the directions of the color sign recognition system by stereo CCD camera. Also conducted were the development of methods to recognize the distance to obstacles and to discriminate areas, the development of mobile sensor, and the basic experiment on running of the demonstration machine. 44 refs., 153 figs., 15 tabs.

  10. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium energy field/R and D high performance flat panel display technology (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium energy bun`ya / koseino flat panel display gijutsu no sogo kaihatsu kenkyu (daiichi nendo ) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    One of the subjects in technology supporting the highly information-oriented society which will develop and diversify toward the 21st century is the construction of high grade man/machine interface. For it, high precision/high luminance/energy saving/thin plane displays are strongly requested. This R and D is to indicate models of systematical development in the region of element technology individually existing in the Shikoku area by forming a regional consortium in the industry/universities/government. Creation of new industries by gathering display related enterprises is a first step in a plan to realize `Display Island Shikoku.` As a concrete target, with the use of high-tech diamond semiconducting technology, a development is conducted of the high performance flat panel display using the negative electron affinity (NEA) electron emitter which drastically solves the problems such as luminance, visibility angle and response speed, the subjects on the commercialized liquid crystal flat panel display. 16 refs., 45 figs., 8 tabs.

  11. Fiscal 2000 regional consortium research and development project - regional new technology creation research and development. Practicalization of polymer back light (1st fiscal year); 2000 nendo chiiki consortium kenkyu kaihatsu jigyo - chiiki shingijutsu soshutsu kenkyu kaihatsu bun'ya seika hokokusho. Polymer back light no jitsuyoka ni kansuru kenkyu (daiichi nendo)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Efforts are being exerted to develop technologies for fabricating polyvinyl carbazole thin film, 100 nm or less in average thickness and 400 mm square in area, for the construction of an exothermal sheet utilizing polymer semiconductor light emission diodes. Activities are conducted in the three fields of (1) the development of large area light emission sheets for use in polymer LEDs (light emission diodes), (2) the study of manufacturing technologies, and (3) the study of technologies for testing, analyzing, and evaluating the material. In field (1), a polyvinyl carbazole thin film is fabricated by the use of a low viscosity resin liquid application method, and a film fabrication technique is established for fabricating a thin film on a 400 mm square substrate within {+-}3 nm of film thickness error. In field (2), studies are conducted of an integrated large area thin film application/transportation system, application device mechanisms, and control sequences for application devices. Through studies of technical literature, exhibitions, and research institute meetings in Japan and overseas, it is concluded that the polymer back light is commercially feasible. (NEDO)

  12. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium field / R and D on downsizing technology of machine tools (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium energy bun`ya / kosaku kikai no downsizing gijutsu ni kansuru kenkyu kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The R and D were conducted aiming at downsizing machine tools by combining microfactory technology owned by Mechanical Engineering Laboratory, Agency of Industrial Science and Technology of MITI with fundamental element technology owned by industrial groups of machine tools. In fiscal 1997, as to the study of spindle drum indexing mechanism in making main spindle multiaxial, the following have been finished: the basic study through openness of controller and networks, confirmation of function of the equipment acquired, and initialization of the driver software. Relating to the study on machining conditions of dry machining processing, delivery and installation of cold air machining instrument have been finished. Concerning the optical measurement of spindle radial run-out vectors, a system to make optical no contact measurement of radial direction components of rotation error was constructed with high accuracy pin gauge attached to the work spindle clamp mechanism as a medium. About the study on sensor-based state recognition technology, specifications for various kinds of sensor were decided on. 5 refs., 67 figs., 3 tabs.

  13. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium field / Development of medical equipment use super devices using micro-3D processing technology (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium bun`ya / micro sanjigen kako gijutsu ni yoru iryo kikiyo super device no kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The R and D are conducted of medical equipment use super devices using technical seeds of Mechanical Engineering Laboratory and micro-3D processing technology which was developed from precision processing technology, etc. which is integrated in the Suwa area, Nagano prefecture. For it, the following R and D are carried out: 1) development of micromechanism: DC3V driven micromotor, chemical use microtube with diameter of 0.1mm, micro-delivery mechanism of chemicals, misting mechanism of chemicals, microjoint, microconnector and cable, and microfilter. 2) development of microsensor: small size/non-contact, microflow of chemicals, and sensor to detect emission of bubble. 3) development of control system. In fiscal 1997, in 1), each element was trially made to clarify subjects. In 2), it was made clear that as flow sensor, ultrasonic type, electromagnetic type and thermal mass flow type are viable, and as bubble sensor, optical sensor is viable. In 3), the following were conducted: information collection of contactless charging circuit, and trial fabrication of liquid crystal polymer ultra thin casing. 9 refs., 84 figs., 30 tabs.

  14. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium field / Development of 3D high speed bio-micromanipulation system (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium bun`ya / sanjigen kosoku bio-micromanipulation system no kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    This is aimed at developing a 3D high speed bio-micromanipulation system for small objects such as cells, bacteria and DNA. In fiscal 1997, a common platform for putting together and integrating individual technology owned by each member is trially fabricated, and the R and D of element technology to be integrated to it is divided up among members. As to selection/transportation technology, a basic experiment on screening by laser beams and electric field is conducted, and microfluid chips isolating bacteria are fabricated. Concerning positioning/fixation technology, cells and others which are comparatively larger than bacteria are freely positioned, and microdevices for fixation are trially fabricated. Relating to power measuring/controlling technology, developed is a multi-freedom degree contact type micromanipulator and a multi-axial minute sensor which enables the 3D mechanical manipulation of cells of the above-mentioned size, etc. The minute processing technology is developed to trially fabricate various microdevices which are integrated into the common flatform. 42 refs., 89 figs., 9 tabs.

  15. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium energy field / development of nano-structured materials for ceramic bearing application (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium energy bun`ya / ceramic bearing yo nano seigyo zairyo no kenkyu kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    For the purpose of developing high efficient ceramic bearing using nano-structured materials, technical development was proceeded with of raw material powder treatment, forming sintering, processing, structural analysis, property evaluation, etc. As to the study of manufacturing of ceramic balls, the following were conducted by the method developed at Osaka Prefectural Institute of Industrial Technology: coprecipitation laminate processing of ZrO2-Al2O3 system to alumina powder at Okumura Crucible Mfg. Co. Ltd., spherial press processing and sintering at Kyocera Co. Ltd., and precise machining at Nippon Pillow Block Mfg., Co. Ltd. The performance as bearing was measured of the ceramic balls obtained such as surface coarseness, sphericity, crush strength and fatigue life. Surface coarseness and sphericity were the same as those of bearing use silicon nitride, but crush strength was considerably low. In the experiment on rolling fatigue strength as bearing, separation occurred within 100 hours even at a load of 100kgf. It is thought that this is because of the pores remaining on the surface, and the measures to be taken for long life were studied. 12 refs., 64 figs., 27 tabs.

  16. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium field / R and D on process adaptive type flexible robot technology (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium bun`ya / kotei tekiogata flexible robot gijutsu ni kansuru kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    For the purpose of establishing robot technology required for the construction of a highly functional automation line with flexibility, the R and D were conducted. At Kumamoto University, a model following type power control system was studied into which polynominal trajectory formation algorithm was integrated. Also studied was damping control of robot arms in a disturbance environment. The following were further carried out: experimental verification (HIRATA Corporation) of the application of power control and intelligent control to transportation equipment production line, experimental verification (SAKURAI SEIGI Co. Ltd.) of the application of power control and intelligent control to semiconductor testing equipment, R and D (OMRON Corporation) of high accuracy force sensing and positioning system, research (Kumamoto Technopolis Foundation) on flexible arms/hands suitable for cooperative control, sensor-based skill (Electrotechnical Laboratory), research (Kyushu National Industrial Research Institute) on tactual system and tactual sensing, etc. 20 refs., 86 figs., 14 tabs.

  17. Imaging Fukushima Daiichi reactors with muons

    Directory of Open Access Journals (Sweden)

    Haruo Miyadera

    2013-05-01

    Full Text Available A study of imaging the Fukushima Daiichi reactors with cosmic-ray muons to assess the damage to the reactors is presented. Muon scattering imaging has high sensitivity for detecting uranium fuel and debris even through thick concrete walls and a reactor pressure vessel. Technical demonstrations using a reactor mockup, detector radiation test at Fukushima Daiichi, and simulation studies have been carried out. These studies establish feasibility for the reactor imaging. A few months of measurement will reveal the spatial distribution of the reactor fuel. The muon scattering technique would be the best and probably the only way for Fukushima Daiichi to make this determination in the near future.

  18. Fukushima Daiichi Status Report. 28 June 2012

    International Nuclear Information System (INIS)

    2012-01-01

    The IAEA issues regular status reports to the public on the current status of the Fukushima Daiichi Nuclear Power Plant, including information on environmental radiation monitoring, the status of workers, and current conditions on-site at the plant.

  19. Construction of Daiichi Tamagawa bridge; Daiichi Tamagawa kyoryo no seko

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, O.; Tsuyoshi, T. [East Japan Railway Company, Tokyo (Japan); Ota, T.; Sato, S. [Tekken Corp., Tokyo (Japan)

    1997-05-30

    This paper describes the construction of Daiichi Tamagawa Bridge for JR Tazawako Line, which was reconstructed with the Akita Shinkansen Project apart from the existing line. This bridge is a three-span continuous PC cable stayed bridge. To avoid operation accidents due to snow and ice, independent two-column type with a height of 11 m without beam was employed for the main tower. For the construction of upper part, overhang election construction method was adopted, which can be applied all the year round. The main girder has a single box cross section, and a width of 5.5 m and a beam height of 2.3 m. This was also constructed by the overhang construction method. To reduce the construction period, the main tower was constructed by the precast block construction method. The whole bridge was divided into six blocks by considering the hoist performance of cranes. Reinforcement against bearing pressure and cleavage due to the cable tensile force was conducted by adopting saddle structure for the main tower. Oblique members were jointed with the main girder using lateral beams projected from lateral side of girder. Totally seven PC cables were used for each oblique member. Measurements and management during the overhang construction were also described. The construction was over without problems in August, 1996. This bridge is under test operation using test run vehicles. 2 refs., 20 figs., 7 tabs.

  20. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium energy field / Study on a new production process of functional thin films suitable for recycling and its application to colored glasses (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium energy bun`ya / recycle ni tekishita kinosei usumaku no shinki seizoho to chakushoku glass eno oyo ni kansuru kenkyu kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The paper described the fiscal 1997 result. Using organic pigment and dye, the basic composition of sol-gel colored coating liquid for glass bottles and sheets was selected to clarify characteristics of gel films. Moreover, chemical modification and optical sensitivity of metallic alkoxide were studied to obtain a trially produced colored glass bottle use coating liquid. As to sheet glass, strength of the gel film is low, which requires further improvement. In relation to optical sensitive gel films, the reaction of various metallic alkoxides and {beta}-diketones was discussed to clarify chemical reactivity with utltaviolet rays. Trial design was also conducted of the coating equipment. The paper examined by literature the present status of recycling systems of colored glass bottles and the technical development in European countries. The problem is a method to wash colored bottles for sterilization. To make colored films durable, it is necessary to form films by organic-inorganic hybrid thin films. Also discussed was a possibility of changing the washing method by administrative guidance. 27 refs., 62 figs., 42 tabs.

  1. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium field / Development of technology to treat aquatic environment by using microorganisms fixed on carbon fabrics (abbreviation: carbon/aquatic environment project) (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium bun`ya / tanso sen`i nansoshiki eno biseibutsu kochaku gensho wo riyoshita mizukankyo seibi gijutsu no kaihatsu (ryakusho: tanso mizu kankyo project) daiichi nendo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    Out of the development of technology to arrange the aquatic environment using phenomena of microorganism fixation on carbon fiber soft textures, the paper stated the fiscal 1997 result. On carbon fibers in a state of swaying in water, microorganisms in water fix in an amazingly large quantity. A catalog was compiled of 58 kinds of carbon fabrics trially woven and knitted. When carbon fiber is used as activated sludge carrier, activity of microorganism lasts more than one year. Only a little amount of surplus sludge is generated. The fixed microorganisms are more active in case of carbon fiber than in case of nylon and polyester fibers. Fiber texture models of carbon fiber fixing activated sludge groups were proposed. By pump operation, the water flow inside/outside microorganism groups is being accelerated. Several new strains of bacillus carboniphilus were isolated/identified from soil and marsh. To grasp relationships of characteristics among three elements such as the state of aquatic environment, fiber, and microorganism group, the experiment was prepared. Preliminary work is conducted to derive a simple equation for facility design, and experimental directions to obtain design conditions were proposed. 6 refs., 166 figs., 47 tabs.

  2. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium energy field/R and D of new technology using low temperature energy for storage of agricultural products (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium energy bun`ya / teion energy wo riyoshita nosanbutsu no shinki chozo gijutsu no kenkyu kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The development was conducted of a new technology using low temperature energy in Hokkaido for storage of agricultural products. In this fiscal year, the R and D were conducted of 1) elucidation of behavior of water droplets in the air at below-freezing temperatures and technology to preserve agricultural products, 2) low temperature region high efficiency energy conversion application technology, and 3) latent heat cold storage technology. In 1), it was clarified that the electrostatic capacity system is appropriate as non-contact simple measuring device of moisture distribution in cold air. Freezing temperatures were measured of potatoes, onions and carrots produced in Hokkaido. Equipment to generate moist air at below-freezing temperatures was trially manufactured which is composed of humidifier and freezer. A relation was studied between the humidifying method and the size of particulate water droplet. In 2), an experimental device was trially fabricated of BiTe thermoelectric conversion device. An experimental device for Stirling engine power generation was assembled which was incorporated into the waste incinerator. A basic experimental device of pulse pipe refrigerator was trially fabricated. Single crystals of BiSb semiconductors were made. In 3), it was clarified that gas hydrates of CO2 and C3H8 are promising as refrigerant. 60 refs., 120 figs., 19 tabs.

  3. Report of the results of the fiscal 1997 regional consortium R and D project. Regional consortium energy field / Development of an environmentally friendly industrial cleaning system using near-critical and supercritical carbon dioxide (first fiscal year); 1997 nendo chiiki consortium kenkyu kaihatsu jigyo. Chiiki consortium energy bun`ya / chorinkai ryutai wo mochiita kankyo chowagata kogyo senjo sochi no kaihatsu (daiichi nendo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    In the manufacturing process of semiconductors and in the high tech industry, cleaning is indispensable. At present, when regulation of the use of CFC which used to be much used has been decided on, the conversion to the use of substitutes for CFC cleaning is urgently needed. Transfer to cleaning by water/alcohol/hydrocarbon has been proceeded with, but there are a lot of problems. Out of the development of the cleaning method using supercritical fluid, the paper described the fiscal 1997 result. As to enhancement of efficiency and decrease in size of equipment, a cleaning experiment by high pressure CO2 around the critical point was conducted by integrating nozzle, ultrasonic generator and cavitation generator and adding solvent circulating system. Multi-purpose and energy saving of the equipment were also studied. To establish an analysis method for the cleaning degree, the contaminated component film of trace organic matter with a specified thickness was formed on the silicon wafer, and using the Fourier transform ultrared spectroscopy, a method to determine the film thickness was studied. For the function evaluation for precision machine parts and determination of optimum cleaning conditions, the cleaning/degreasing process of valves were compared with the conventional method. For the product manufacturing, the paper investigated and prepared the data in Japan and from abroad. 55 refs., 79 figs., 18 tabs.

  4. Analysis of Fukushima Daiichi Accident Using HFACS

    International Nuclear Information System (INIS)

    Mohamed, Saeed Almheiri

    2013-01-01

    The shadow of Fukushima Daiichi nuclear power plant (NPP) accident is still too big and will last long. On the other hand, it could still teach us lots of lessons to better design and operate nuclear power plants. In this paper, we will be focusing on the Fukushima Daiichi accident, especially on human organizational factors. We will analyze the accident using Human Factors Analysis and Classification System (HFACS) in order to better understand the organizational climate of TEPCO 1 and NISA 2 that led to Fukushima Daiichi Accident. HFACS was developed for the U. S. aviation industry and has been used at many industries like the rail and mining industries. We found that the HFACS to be greatly beneficial in investigating the latent and organizational causes for the accident. The application results show that the causes of Fukushima Daiichi accident were spread out from sharp end (i.e. Unsafe Act) to blunt end (i. e. Organizational Influences). This means that the corresponding countermeasures should cover from front line staff to management. Thus, we managed to develop a better understanding on how to prevent similar errors or violations. The incident and near-miss have a lot of helpful information because it may show the actual and latent deficiencies of complex systems. We applied the HFACS into Fukushima Daiichi accident to better locate the causes related to both sharp and blunt ends of operation of NPP. In order to derive useful lessons from the accident analysis, the analyst should try to find the similarities not differences from the incident. It is imperative that whatever accident/incident analysis systems we use, we should fully utilize the disastrous Fukushima accident

  5. Analysis of Fukushima Daiichi Accident Using HFACS

    Energy Technology Data Exchange (ETDEWEB)

    Mohamed, Saeed Almheiri [Korea Advanced Institue of Science and Technology, Daejeon (Korea, Republic of)

    2013-10-15

    The shadow of Fukushima Daiichi nuclear power plant (NPP) accident is still too big and will last long. On the other hand, it could still teach us lots of lessons to better design and operate nuclear power plants. In this paper, we will be focusing on the Fukushima Daiichi accident, especially on human organizational factors. We will analyze the accident using Human Factors Analysis and Classification System (HFACS) in order to better understand the organizational climate of TEPCO{sup 1} and NISA{sup 2} that led to Fukushima Daiichi Accident. HFACS was developed for the U. S. aviation industry and has been used at many industries like the rail and mining industries. We found that the HFACS to be greatly beneficial in investigating the latent and organizational causes for the accident. The application results show that the causes of Fukushima Daiichi accident were spread out from sharp end (i.e. Unsafe Act) to blunt end (i. e. Organizational Influences). This means that the corresponding countermeasures should cover from front line staff to management. Thus, we managed to develop a better understanding on how to prevent similar errors or violations. The incident and near-miss have a lot of helpful information because it may show the actual and latent deficiencies of complex systems. We applied the HFACS into Fukushima Daiichi accident to better locate the causes related to both sharp and blunt ends of operation of NPP. In order to derive useful lessons from the accident analysis, the analyst should try to find the similarities not differences from the incident. It is imperative that whatever accident/incident analysis systems we use, we should fully utilize the disastrous Fukushima accident.

  6. The Fukushima Dai-ichi catastrophe

    International Nuclear Information System (INIS)

    Fluke, R.

    2011-01-01

    This article explains the accident at Fukushima Dai-ichi in terms of the fundamental safety principles and how these principles are achieved by design. Design differences between the reactors at Fukushima and a typical CANDU reactor are explained to illustrate how the safety principles can be achieved by different reactor designs. How these principles fared at Fukushima is explained. A detailed chronology of events is given in a separate table. (author)

  7. Feature article. Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    Ekarinai, Masashi; Ake, Yutaka; Narabayashi, Tadashi

    2011-01-01

    This special feature article consisted of five reports and the minutes of emergency discussion meeting on Fukushima Daiichi Nuclear Power Plant (NPP) accident. Effects of the accident on future electricity supply of electric utilities and also on business development of nuclear industries were discussed. Activities of senior network team of atomic energy society of Japan (AESJ) to conduct severe accident analysis and early restoration from the accident were introduced. Circulating injection reactor cooling system and zeolite decontamination system of accumulated contaminated water was proposed. Effects of the accident on overseas reaction on nuclear development were also reported as well as personal experience of the professor in the US west coast on communications. (T. Tanaka)

  8. Report on Fukushima Daiichi NPP precursor events

    International Nuclear Information System (INIS)

    2014-01-01

    The main questions to be answered by this report were: The Fukushima Daiichi NPP accident, could it have been prevented? If there is a next severe accident, may it be prevented? To answer the first question, the report addressed several aspects. First, the report investigated whether precursors to the Fukushima Daiichi NPP accident existed in the operating experience; second, the reasons why these precursors did not evolve into a severe accident. Third, whether lessons learned from these precursor events were adequately considered by member countries; and finally, if the operating experience feedback system needs to be improved, based on the previous analysis. To address the second question which is much more challenging, the report considered precursor events identified through a search and analysis of the IRS database and also precursors events based on risk significance. Both methods can point out areas where further work may be needed, even if it depends heavily on design and site-specific factors. From the operating experience side, more efforts are needed to ensure timely and full implementation of lessons learnt from precursor events. Concerning risk considerations, a combined use of risk precursors and operating experience may drive to effective changes to plants to reduce risk. The report also contains a short description and evaluation of selected precursors that are related to the course of the Fukushima Daiichi NPP accident. The report addresses the question whether operating experience feedback can be effectively used to identify plant vulnerabilities and minimize potential for severe core damage accidents. Based on several of the precursor events national or international in-depth evaluations were started. The vulnerability of NPPs due to external and internal flooding has clearly been addressed. In addition to the IRS based investigation, the WGRISK was asked to identify important precursor events based on risk significance. These precursors have

  9. Assistance to the Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    Sakuma, Minoru

    2012-01-01

    Immediately after the reactor accident of Fukushima Daiichi Nuclear Power Plant occurring on March 11, 2011, JAEA started and continues to work with its every possible effort for remediation and has established the head quarter for countermeasure in Fukushima prefecture. The present paper includes main activities of assisting Fukushima area such as environmental monitoring and decontamination, technical advises to Japanese and local government, and others. Some are in cooperation with universities and others with Tokyo Electric Power Company. Towards closing the reactor accident, JAEA is joining the integrated activities for cooling the damaged reactor core and management of storing and disposal of radioactive wastes produced and large amount of remaining contaminated water to find out an adequate method for decontamination and preparing the manual for it. (S. Ohno)

  10. Safety insights from forensics evaluations at Daiichi

    Directory of Open Access Journals (Sweden)

    J. Rempe

    2017-01-01

    Information obtained from Daiichi is required to inform Decontamination and Decommissioning activities, improving the ability of the Tokyo Electric Power Company (TEPCO to characterize potential hazards and to ensure the safety of workers involved with cleanup activities. This paper reports initial results from the US Forensics Effort to utilize examination information obtained by TEPCO to enhance the safety of existing and future nuclear power plant designs. In this paper, three examples are presented in which examination information, such as visual images, dose surveys, sample evaluations, and muon tomography examinations, along with data from plant instrumentation, are used to obtain significant safety insights in the areas of component performance, fission product release and transport, debris end-state location, and combustible gas generation and transport. In addition to reducing uncertainties related to severe accident modeling progression, these insights confirm actions, such as the importance of water addition and containment venting, that are emphasized in updated guidance for severe accident prevention, mitigation, and emergency planning.

  11. Insight from Fukushima Daiichi Unit 3 Investigations using MELCOR

    International Nuclear Information System (INIS)

    Robb, Kevin R.; Francis, Matthew W.; Ott, Larry J.

    2014-01-01

    During the emergency response period of the accidents that took place at Fukushima Daiichi in March of 2011, researchers at Oak Ridge National Laboratory (ORNL) conducted a number of studies using the MELCOR code to help understand what was occurring and what had occurred. During the post-accident period, the Department of Energy (DOE) and the US Nuclear Regulatory Commission (NRC) jointly sponsored a study of the Fukushima Daiichi accident with collaboration among Oak Ridge, Sandia, and Idaho national laboratories. The purpose of the study was to compile relevant data, reconstruct the accident progression using computer codes, assess the codes predictive capabilities, and identify future data needs. The current paper summarizes some of the early MELCOR simulations and analyses conducted at ORNL of the Fukushima Daiichi Unit 3 accident. Extended analysis and discussion of the Unit 3 accident is also presented taking into account new knowledge and modeling refinements made since the joint DOE/NRC study

  12. Public opinion on Fukushima Daiichi nuclear disaster

    International Nuclear Information System (INIS)

    Hirose, Hirotada

    2013-01-01

    This article showed trend of public opinion on nuclear power after Fukushima Daiichi nuclear disaster, for which the survey had been done five times under the same method and inquiries. Most unreliable source of information at disaster was government ministries and offices, whose unreliability sharply increased from 20% to about 50% after 3 months later and one year later after March 11 and reliability after 2 year and 5 months later (August 2013) was not high and almost comparable with unreliability of 27%. Nuclear disaster was most serious cause of Great East Japan earthquake disaster (60%) and not entirely ended due to such increase of contaminated water. Public opinion survey in August 2013 showed nuclear power stoppage totaled about 80% with immediate of about 30% and phaseout of about 50%, and possibility of occurrence of another nuclear accident comparable with Fukushima disaster was almost 80% with a belief not only earthquakes, tsunamis, terrorism but also human errors might initiate nuclear disaster if nuclear power restarted. Future most serious disaster would be earthquake (50%) and nuclear disaster (35%). Nuclear accident preparedness of government and local government was not enough (58% and 24%) and nothing (33% and 24%). Residents within UPZ (Urgent Protection action Planning Zone) of 30 km radius could not evacuate safely (57%) and entirely (22%). If government and local government encouraged damaged residents to come home with declaration of safety for evacuation area of nuclear accident, damaged residents might not return almost (46%) and entirely (9%). Notwithstanding people's strong feeling against nuclear power, LDP (Liberal Democratic Party) promoting nuclear power won an overwhelming victory at the election of House of Councilors in July 2013. Public opinion survey in August 2013 showed most important issue of voters was party's image (25%), economic measures (20%) and candidate's personality (13%), and nuclear power policy was only 5%. (T

  13. Achievement report for fiscal 1998. Optical tomographic system; 1998 nendo seika hokokusho. Hikari danso imaging system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    Evaluations were given on spatial resolution and measurement time of an optical tomographic system by using the developed 64-channel time-resolved spectroscopy and an image reconstruction algorithm. With respect to the spatial resolution, the target value of 1 cm was verified from tomographic images of a phantom with a diameter of 10cm, simulating a neonate. The measurement time achieved 20 minutes, being one third of the target value. In installing the equipment at Hokkaido University, speeds of the optical switches and attenuators were increased to have reduced the measurement time to one minute. For installation at Kanagawa Rehabilitation Center, development has been made on a nano-second light pulser, whose average beam quantity has been increased to 40 times, and improvement has been given on the optical switches, the attenuators, and the indication software, by which the measurement time was decreased further by 30 seconds than that at Hokkaido University. In performing the clinical evaluation, the evaluation protocol resolved by the Experiment Evaluation Special Committee was submitted for deliberation at the Medical Welfare Device Clinical Evaluation Committee. Upon having been authorized by the Committee, the clinical evaluations were performed at Hokkaido University and the Kanagawa Rehabilitation Center. (NEDO)

  14. A comparison of responses to the Fukushima Daiichi Nuclear Plant

    International Nuclear Information System (INIS)

    Oshima, Teruo

    2011-01-01

    Many Institutions abroad have expressed their views on the Fukushima Daiichi Nuclear Power Plant accident. When more emphasis on risk and precaution, they differ markedly from that in Japan. One of the main causes of the accident lies in disregard for prior warnings about possible tsunami risks. This paper will discuss lessons we can learn from the accident and future problems. (author)

  15. Technological Lessons from the Fukushima Dai-Ichi Accident

    Science.gov (United States)

    2016-06-01

    a devastating earth - quake and tsunami. One of the many secondary effects of these disas- ters was a loss of control of the Fukushima Dai-Ichi nuclear...plant needed to be continually cooled, vast quantities of contaminated water was (and is) created, particularly at the plant. Certain radioisotopes ...terminated, although it could be revived at some future date . The political difficulties of developing a similar storage site in densely populated

  16. Fukushima-Daiichi after the severe accident (estimation)

    International Nuclear Information System (INIS)

    Otcenasek, Petr

    2011-01-01

    All facts about the Fukushima-Daiichi NPP and about the accident known at the time of publication are summarized and expected remedial actions and consequences of the accidents are deduced. The paper is structured as follows: (1) Accident initiation is known; (2) Logically inferred results; (3) Framework identification; (4) Survey; and (5) Economic and strategic impacts of the accident. Worldwide solidarity is mentioned in conclusion. (P.A.)

  17. Fukushima - calculation of the reactor core inventory and storage pools Dai-ichi 1 to Dai-ichi 4, an estimation of a source term

    International Nuclear Information System (INIS)

    Krpelanova, M.; Carny, P.

    2011-01-01

    Inventory of the reactor core and spent fuel storage pool of the reactors at Dai-ichi 1 to Dai-ichi 4 was determined to need a realistic estimate of the source (released into the atmosphere environment) and modelling of radiological impact of the events in Fukushima NPP. Calculations of inventories were carried out by the methodology that is used in systems to support emergency response and crisis management anymore. Calculations were made based on a model that respects knowledge of real fuels and fuel cycles for individual reactors Dai-ichi. Necessary input data for training the model and calculate inventories are obtained from the IAEA PRIS database.

  18. Precept from the management for the accident of Fukushima daiichi

    International Nuclear Information System (INIS)

    Miyaushiro, Norihiro

    2013-01-01

    At 17 hours after the accident of Fukushima Daiichi Nuclear Power Plant due to the Great East Japan Earthquake, National Institute of Radiological Sciences sent the first REMAT (Radiation Emergency Medical Assistance Team) in the 20 km range from the Plant. The team members were confronted by two issues: (1) Medical activities under the infrastructures destructed by a multiple disaster caused by earthquake, tsunami and nuclear accident, which was not presumed. (2) Radiation protection management for dispatched staff. Measures for this situation worked out by activities on the site are presented. (K.Y.)

  19. Influence on UK Nuclear Regulation from the Fukushima Daiichi Accident

    International Nuclear Information System (INIS)

    Savage, R.

    2016-01-01

    This paper provides an overview of the UKs response to the Fukushima Daiichi Accident and highlights the influence that this has had on UK nuclear regulation since March 2011. ONR’s Incident Suite was staffed from the first day of the accident and remained active on a 24 hours basis for over two weeks. The purpose was to provide advice to the UK government specifically prompt assurance of why this accident couldn’t take place in the UK and practical advice in relation to the 17,000 UK nationals in Japan at that time. In the early phase of the accident ONR took part in international cooperation with the US, Canadian and French regulators in order to determine the actual technical status of the Fukushima Daiichi power plant units. The UK Secretary of State requested that the ONR Chief Inspector identify any lessons to be learnt by the UK nuclear industry and in doing so cooperate and coordinate with international colleagues. The Interim report was produced (May 2011) this focused on civil NPP’s, provided background to radiation, technology and regulations. This report compared the Japan situation with the UK and identified 11 conclusions and 26 recommendations.

  20. Study on disaster waste around Fukushima Daiichi NPS

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    Extreme difficulties exists in Fukushima Prefecture in disposing of waste generated from the tsunami disaster (hereinafter referred to as disaster waste) and contaminated with radioactive material released from the crippled Fukushima Daiichi Nuclear Power Station. Although the waste should be treated according to the level of radioactivity, there were only air dose rates and radionuclide analyses of soil due to monitoring around the Fukushima Daiichi Nuclear Power Station and there had been no information on the radioactivity concentration of the disaster waste. The radioactivity concentration of the disaster waste was investigated by sampling measurement and in-situ Ge measurement at 20 temporary disaster waste storages in Fukushima Prefecture excluding the evacuation zone and 'deliberate evacuation zone.' JNES carried out tins investigation upon a request from die Nuclear and Industrial Safety Agency. The investigation revealed that the measured radioactivity concentrations of the disaster waste lumps were enveloped within the soil monitoring readings in Fukushima Prefecture and also within a correlated curve between the air dose rates obtained from air dose rate readings around the disaster waste and the radioactivity concentrations of it. Based on the results of this study, JNES compiled a manual on measurement technique for contaminated disaster waste. (author)

  1. Impacts of the Fukushima Daiichi Accident on Nuclear Development Policies

    International Nuclear Information System (INIS)

    Vance, Robert; Henderson, David; ); Moore, Laurie

    2017-01-01

    The Fukushima Daiichi nuclear power plant accident has had an impact on the development of nuclear power around the world. While the accident was followed by thorough technical assessments of the safety of all operating nuclear power plants, and a general increase in safety requirements has been observed worldwide, national policy responses have been more varied. These responses have ranged from countries phasing out or accelerating decisions to phase out nuclear energy to countries reducing their reliance on nuclear power or on the contrary continuing to pursue or expand their nuclear power programs. This study examines changes to policies, and plans and attempts to distinguish the impact of the Fukushima Daiichi accident from other factors that have affected policy-making in relation to nuclear energy, in particular electricity market economics, financing challenges and competition from other sources (gas, coal and renewables). It also examines changes over time to long-term, quantitative country projections, which reveal interesting trends on the possible role of nuclear energy in future energy systems. (authors)

  2. Lessons of the Fukushima Dai-ichi accident for PSA

    International Nuclear Information System (INIS)

    Kumar, M.; Klug, J.; Alzbutas, R.; Burgazzi, L.; Farcasiu, M.; Nitoi, M.; Ivanov, I.; Bogdanov, D.; Hashimoto, K.; Hirata, K.; La Rovere, S.; Sevbo, O.; Vitazkova, J.; Hustak, S.; Wielenberg, A.; Raimond, E.

    2016-01-01

    The objective of this document is to identify some lessons learned from the Fukushima Dai-ichi accident for PSA. Based on the public information on the causes that have led to major radioactive release during the Fukushima Dai-ichi accident (initiating events, material and human response), the authors, ASAMPSA-E WP30 members have performed a review to examine the gaps/insufficiencies/incompleteness in the existing Level 1 and Level 2 PSAs. This is the aim of this report which is one of WP30 deliverables i.e. D30.2. The consideration of external initiating events for the different levels of defense-in-depth is one of the focal points in this review. Recommendations in the way of developing the different elements of PSAs have been proposed by the authors and were completed later during the ASAMPSA-E project. Moreover, first recommendations on the use of PSA information in decision making have been included as well. (authors)

  3. NEA support to Fukushima Daiichi decommissioning strategy planning

    International Nuclear Information System (INIS)

    Weber, Inge; Otsuka, Ichiro; ); Sandberg, Nils; ); Funaki, Kentaro

    2017-01-01

    Six years after the Fukushima Daiichi nuclear power plant accident, the Japanese government and Tokyo Electric Power Holdings, Inc. (TEPCO) are shifting their focus to strategy planning for long-term challenges related to the decommissioning of the damaged reactors. The international community has been helping to address the unprecedented challenges of managing the accident facilities. The NEA is playing a key supporting and coordinating role in the international community, in particular in the area of radioactive waste management and the evaluation of the conditions and location of fuel debris. In the first half of 2017, a series of visual investigations using remotely controlled equipment and robots were performed to identify the condition of vessels inside, as well as the distribution of fuel debris in all three units. In the summer of 2017, as stated in the government road-map, policies for fuel debris retrieval from each unit would be presented, and would result in a discussion on which unit should be the first to undergo fuel debris retrieval in 2018. In addition, the basic policy for the processing and disposal of radioactive material arising from the accident would be conceptualised in the year 2017. This article highlights ongoing international joint activities within the NEA framework, corresponding to the challenges that have been identified in the Fukushima Daiichi decommissioning strategy planning

  4. Study on disaster waste around Fukushima Daiichi NPS

    International Nuclear Information System (INIS)

    2012-01-01

    Extreme difficulties exists in Fukushima Prefecture in disposing of waste generated from the tsunami disaster (hereinafter referred to as disaster waste) and contaminated with radioactive material released from the crippled Fukushima Daiichi Nuclear Power Station. Although the waste should be treated according to the level of radioactivity, there were only air dose rates and radionuclide analyses of soil due to monitoring around the Fukushima Daiichi Nuclear Power Station and there had been no information on the radioactivity concentration of the disaster waste. The radioactivity concentration of the disaster waste was investigated by sampling measurement and in-situ Ge measurement at 20 temporary disaster waste storages in Fukushima Prefecture excluding the evacuation zone and 'deliberate evacuation zone.' JNES carried out tins investigation upon a request from die Nuclear and Industrial Safety Agency. The investigation revealed that the measured radioactivity concentrations of the disaster waste lumps were enveloped within the soil monitoring readings in Fukushima Prefecture and also within a correlated curve between the air dose rates obtained from air dose rate readings around the disaster waste and the radioactivity concentrations of it. Based on the results of this study, JNES compiled a manual on measurement technique for contaminated disaster waste. (author)

  5. Accident management insights after the Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    Degueldre, Didier; Viktorov, Alexandre; Tuomainen, Minna; Ducamp, Francois; Chevalier, Sophie; Guigueno, Yves; Tasset, Daniel; Heinrich, Marcus; Schneider, Matthias; Funahashi, Toshihiro; Hotta, Akitoshi; Kajimoto, Mitsuhiro; Chung, Dae-Wook; Kuriene, Laima; Kozlova, Nadezhda; Zivko, Tomi; Aleza, Santiago; Jones, John; McHale, Jack; Nieh, Ho; Pascal, Ghislain; ); Nakoski, John; Neretin, Victor; Nezuka, Takayoshi; )

    2014-01-01

    The Fukushima Daiichi nuclear power plant (NPP) accident, that took place on 11 March 2011, initiated a significant number of activities at the national and international levels to reassess the safety of existing NPPs, evaluate the sufficiency of technical means and administrative measures available for emergency response, and develop recommendations for increasing the robustness of NPPs to withstand extreme external events and beyond design basis accidents. The OECD Nuclear Energy Agency (NEA) is working closely with its member and partner countries to examine the causes of the accident and to identify lessons learnt with a view to the appropriate follow-up actions to be taken by the nuclear safety community. Accident management is a priority area of work for the NEA to address lessons being learnt from the accident at the Fukushima Daiichi NPP following the recommendations of Committee on Nuclear Regulatory Activities (CNRA), Committee on the Safety of Nuclear Installations (CSNI), and Committee on Radiation Protection and Public Health (CRPPH). Considering the importance of these issues, the CNRA authorised the formation of a task group on accident management (TGAM) in June 2012 to review the regulatory framework for accident management following the Fukushima Daiichi NPP accident. The task group was requested to assess the NEA member countries needs and challenges in light of the accident from a regulatory point of view. The general objectives of the TGAM review were to consider: - enhancements of on-site accident management procedures and guidelines based on lessons learnt from the Fukushima Daiichi NPP accident; - decision-making and guiding principles in emergency situations; - guidance for instrumentation, equipment and supplies for addressing long-term aspects of accident management; - guidance and implementation when taking extreme measures for accident management. The report is built on the existing bases for capabilities to respond to design basis

  6. Development of source term PIRT of Fukushima Daiichi NPPs accident

    International Nuclear Information System (INIS)

    Suehiro, S.; Okamoto, K.

    2017-01-01

    The severe accident evaluation committee of AESJ (Atomic Energy Society of Japan) developed the thermal hydraulic PIRT (Phenomena Identification and Ranking Table) and the source term PIRT based on findings during the Fukushima Daiichi NPPs accident. These PIRTs aimed to explore the debris distribution and the current condition in the NPPs with high accuracy and to extract higher priority from the aspect of the sophistication of the analytical technology to predict the severe accident phenomena by the code. The source term PIRT was divided into 3 phases for the time domain and 9 categories for the spatial domain. The 68 phenomena were extracted and the importance from viewpoint of the source term was ranked through brainstorming and discussion. This paper describes the developed source term PIRT list and summarized the high ranked phenomena in each phase. (author)

  7. Atmospheric dispersion modeling: Challenges of the Fukushima Daiichi response

    Energy Technology Data Exchange (ETDEWEB)

    Sugiyama, Gayle [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Nasstrom, John [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pobanz, Brenda [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Foster, Kevin [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Simpson, Matthew [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Vogt, Phil [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Aluzzi, Fernando [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Homann, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2012-05-01

    In this research, the U.S. Department of Energy’s (DOE) National Atmospheric Release Advisory Center (NARAC) provided a wide range of predictions and analyses as part of the response to the Fukushima Daiichi Nuclear Power Plant accident including: daily Japanese weather forecasts and atmospheric transport predictions to inform planning for field monitoring operations and to provide U.S. government agencies with ongoing situational awareness of meteorological conditions; estimates of possible dose in Japan based on hypothetical U.S. Nuclear Regulatory Commission scenarios of potential radionuclide releases to support protective action planning for U.S. citizens; predictions of possible plume arrival times and dose levels at U.S. locations; and source estimation and plume model refinement based on atmospheric dispersion modeling and available monitoring data.

  8. Decommissioning and environmental remediation scenario development for Fukushima Daiichi

    Energy Technology Data Exchange (ETDEWEB)

    Kawamura, Hideki [mcm japan, Tokyo (Japan); Yashio, Shoko [Obayashi Corporation, Tokyo (Japan); McKinley, Ian G. [McKinley Consulting, Frick (Switzerland)

    2017-07-15

    Although the general approach to reactor decommissioning is well established, there is no direct precedent for managing the 6 units of the Fukushima Daiichi nuclear power plant. Apart from damaged reactors, challenges include extensive contamination of the entire reactor site and a huge tank farm currently storing contaminated cooling water. In order to move forward with planning decommissioning, it is important to decide on the desired end state of the site and understand the impact on such a decision on the costs, hazards and environmental impact of the project. A decommissioning roadmap and reference dismantling concept provide a basis for short-term planning, but the potential for technological optimisation should be carefully considered.

  9. Accident analysis of Fukushima Daiichi Nuclear Power Station unit 1

    International Nuclear Information System (INIS)

    Kobayashi, Masahide; Narabayashi, Tadashi; Tsuji, Masashi; Chiba, Go; Nagata, Yasunori; Shimoe, Tomohiro

    2015-01-01

    As a result of the Great East Japan Earthquake that occurred on 11 March 2011, all AC and DC power at the Fukushima Daiichi NPP units 1 to 3 were lost soon after the tsunami. The core cooling function was lost, and the cores of units 1 to 3 were damaged. The purpose of this work is to clarify the progress of the accident in unit 1, which was damaged the earliest among the 3 units. Therefore, an original severe accident analysis code was developed, and the progress of the accident was evaluated from the analysis results and the actual data. As a result, the leakage path from a pressure vessel was clarified, and some lessons and knowledge were gained. (author)

  10. The Fukushima Daiichi nuclear disaster: a brief report

    International Nuclear Information System (INIS)

    Yadav, Roopaksh; Joshi, Pankaj Kumar

    2012-01-01

    Fukushima Daiichi is a series of equipment failures, nuclear meltdown and release of radioactive materials at the Fukushima -1 nuclear power plant, following the Tohoku earthquake and tsunami. The plant comprises six separate boiling water reactors originally designed by general electric and maintained by the Tokyo Electric Power Company (TEPCO). The Fukushima disaster is the building may be causing isolated, uncontrolled nuclear chain reaction. TEPCO confirmed its concern about the accuracy of high iodine and chlorine report by formally retracting the report which eliminated both the exceptionally high iodine-134 and chlorine-38 levels as proof of criticality. Reports of 13 observation of neutron beams 1.5 km. 'southwest of the plant's no. 1 and 2 reactors' from 13 to 16 March raised the possibility the nuclear fission could have occurred after the initial scraming of the reactors at Fukushima Daiichi. 16 March reports that fuel rods in the spent fuel pool at unit 4 could have been exposed to air appeared to indicate the fission may have occurred in that fuel pool. Later reports of exceptionally high iodine-134 levels appeared to confirm this theory because very high levels of iodine-134 would be indicative of fission reactions. The same report also showed high measurements of chlorine-38, which some nuclear experts used to calculate that fission must be occurring in unit 1. Despite TEPCO suggesting the iodine-134 report was inaccurate, the IAEA appeared to accept the chlorine-based analysis as a valid theory suggesting fission when it stated at a press conference that Melted fuel in the no. 1 reactor as of September 2011, there were no deaths or serious injuries due to direct radiation. Cancer deaths due to accumulated radiation exposure cannot be ruled out and according to one expert, might be in the order of 100 cases. (author)

  11. Surveillance of Strontium-90 in Foods after the Fukushima Daiichi Nuclear Power Plant Accident.

    Science.gov (United States)

    Nabeshi, Hiromi; Tsutsumi, Tomoaki; Uekusa, Yoshinori; Hachisuka, Akiko; Matsuda, Rieko; Teshima, Reiko

    2015-01-01

    As a result of the Fukushima Daiichi nuclear power plant (NPP) accident, various radionuclides were released into the environment. In this study, we surveyed strontium-90 ((90)Sr) concentrations in several foodstuffs. Strontium-90 is thought to be the third most important residual radionuclide in food collected after the Fukushima Daiichi, NPP accident after following cesium-137 ((137)Cs) and cesium-134 ((134)Cs). Results of (90)Sr analyses indicated that (90)Sr was detect in 25 of the 40 radioactive cesium (r-Cs) positive samples collected in areas around the Fukushima Daiichi NPP, ranging in distance from 50 to 250 km. R-Cs positive samples were defined as containing both (134)Cs and (137)Cs which are considered to be indicators of the after-effects of the Fukushima Daiichi NPP accident. We also detected (90)Sr in 8 of 13 r-Cs negative samples, in which (134)Cs was not detected. Strontium-90 concentrations in the r-Cs positive samples did not significantly exceed the (90)Sr concentrations in r-Cs negative samples or the (90)Sr concentration ranges in comparable food groups found in previous surveys before the Fukushima Daiichi NPP accident. Thus, (90)Sr concentrations in r-Cs positive samples were indistinguishable from the background (90)Sr concentrations arising from global fallout prior to the Fukushima accident, suggesting that no marked increase of (90)Sr concentrations has occurred in r-Cs positive samples as a result of the Fukushima Daiichi NPP accident.

  12. Achievement report for fiscal 1998. Home rehabilitation system for aphasia patients; 1998 nendo seika hokokusho. Shitsugosho zaitaku rehabilitation shien system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    Development has been made on the element technologies for a home rehabilitation system for aphasia patients. First, studies were performed on an authoring procedure for aphasia patient training, and partial trial production and development were carried out on an authoring system for the training program formula. Then, studies were executed on a training simulation and analysis filter, and partial trial production and development were implemented on a home rehabilitation supporting and self-teaching system. Next, an input and output mechanism for voice signal processing was studied, and aphasia patient and caregiver human interface was partially fabricated on a trial basis. In addition, a remote rehabilitation communicating method was researched, and partial trial production was carried out on a remote rehabilitation evaluation and diagnosis support means. Finally, communication assisting means were researched, and a communication assisting system was partially produced on a trial basis. Good evaluation results were given on a demonstration system. Although partial indications were given on minute parts, practical agreement was obtained as a whole. Great expectation was given particularly on the remote rehabilitation system and the authoring system. (NEDO)

  13. Summary of achievement reports on the Sunshine Project in fiscal 1978 (Hydrogen energy); 1978 nendo seika hokokusho gaiyoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-04-01

    This paper summarizes achievement reports on the Sunshine Project in fiscal 1978 (hydrogen energy). In hydrogen manufacturing methods, studies are described on materials of membranes and electrodes used in high temperature and pressure electrolysis. In thermo-chemical method, studies are continuing on cycles of the iron system, iodine system, and mixed system (composed by thermal, photo and electro-chemistries). For the iodine system, summary design was performed on an experimental device. For the mixed system, trial fabrication and experiments were carried out on a beam radiation type electrolytic tank that electrolyses quickly HI and Fe{sup 3+} produced in the photo-chemical reaction, and separates the products. Discussions were also given on HI decomposition (hydrogen acquisition) by means of heat diffusion. With respect to storage and transportation, development is being made on optimal metal hydrides. In combustion technologies, discussions are given on combustors and catalysts to break through the dilemma of high NOx emission and frequent occurrence of reverse ignition. For fuel cells, the paper describes developments of the materials thereof, high-temperature solid electrolyte type fuel cells and alkaline aqueous solution electrolyte type fuel cells. Regarding the non-steady hydrogen engines, the paper describes fundamental studies on non-steady jet flow behavior using shock tubes, and single cylinder engine tests. It also describes hydrogen safety assuring measures, and studies on energy systems. (NEDO)

  14. Fiscal 2000 achievement report. Welfare technosystem research and development (Ube); 2000 nendo walfare technosystem kenkyu kaihatsu (Ube) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Efforts continue to develop welfare nursing equipment for helping persons in need of nursing care or handicapped persons who live an independent life. Efforts are exerted in three fields for developing (1) a motor driven wheelchair in which the occupant feels as if driving a car, (2) an online cardiac function monitoring system using a cardiac sound sensor, (3) an automatic pressure belt for patients of postural low blood pressure, (4) and a seated position aiding and stabilizing device for workers with legs not fully useful. In field (1), the steering wheel, brake, and driving system are contrived so that the occupant may easily drive the wheelchair as if in an automobile driver's seat. In field (2), a device is developed to monitor and examine the heart rate and respiration rate, for which a cardiac sensor has to be installed on the water bed or an air mattress. In field (3), a computer controlled automatic pressure belt is developed for patients of myelopathy or cerebrovascular disease. In field (4), a work assisting device is developed to help seated workers with leg troubles. (NEDO)

  15. Development of environmentally friendly universal controller. Data and materials; 1998 nendo kankyo taio universal controller no kaihatsu seika hokokusho. Shiryohen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    Research and development was carried out for an 'environmentally friendly universal controller (UC)' which would be 'user-friendly and energy-saving' when used with electrical home appliances, and data and materials on them were compiled into this volume. It covers the specifications (Versions 0.6 and 0.51) of a newly developed two-way controller protocol, the specification (Version 0.1) of two-way remote control IrDA-C communication unit hardware, an infrared communication protocol IrDa Control, and the like. It also accommodates information collected through surveys of technological trends as reflected in technical literature, Internet home pages, catalogs, and the like, concerning the user-friendliness of electrical home appliances, remote control, domestic consumption of electric power, and the like. Also covered is the result of surveys of patents involving environmentally friendly UC related technologies, namely, Japanese patents (from applications made in 1979 through disclosures made in 1998) and U.S. patents (registrations made in 1982 and thereafter). Furthermore, it contains the result of surveys of actualities of domestic use conducted for the purpose of clarifying the effect of environmentally friendly UC introduction, how such UCs are being accepted by the public, and the conditions that should be satisfied for their popularization. (NEDO)

  16. FY 1998 R and D project on industrial science technology; 1998 nendo ryoshi kino soshi no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The R and D on quantum functional devices (QFDs) were conducted, and the FY 1998 results were summed up. In the comprehensive survey on QFDs, the following were carried out for the efficient R and D promotion: R and D progress state survey/problem extraction/analytical study, technical trend survey, overseas survey ordered from overseas supplier, common basement technology study, etc. In the R and D on technology for QFDs, integration of multivalued logical devices using tunneling control functional devices, integration of logical memory devices using quantum levels, integration of quantum band combination-type multi-functional devices, silicon insulating film tunnel memory devices, assembly quantum dot functional memory, quantum wave switching functional devices, integration of single electron logical devices, integration of CMOS combination-type single electron devices, etc. Moreover, in the development of the basement technology of single electron devices, technology to construct element devices using quantum functions, basement technology of single electron device integration devices, architecture of single electron device information processing circuit system, etc. (NEDO)

  17. Fiscal 2000 achievement report. Welfare technosystem research and development (Niihama); 2000 nendo walfare technosystem kenkyu kaihatsu (Niihama) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Efforts are made to develop welfare equipment systems for helping people needing care lead an independent life. In collecting data on the transfer of patients and carrying out research and development in this connection, activities are conducted to develop (1) a transfer wheelchair and a transfer aiding wheelchair, (2) a simplified transfer type toilet, and (3) a tilt mechanism installable on a standard wheelchair. Under item (1), a wheelchair and an auxiliary wheelchair enabling the transfer of a person who cannot move without help between a wheelchair and an automobile are experimentally built. Under item (2), a simplified transfer type toilet to which a single attendant can easily guide the patient from the bed is developed. Under item (3), a tilt mechanism is developed, installable on a wheelchair to recline the same for the aged person to assume a comfortable attitude. In the development of a portable character reading device, a finger tip reader was experimentally manufactured for reading Japanese characters. (NEDO)

  18. Outline of fiscal 1970 achievements in research on MHD power generation; 1970 nendo MHD hatsuden kenkyu seika gaiyo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1970-07-01

    Compiled are the results of studies conducted in fiscal 1970 on MHD (magnetohydrodynamic) power generation. In the operation test and modification of the 1000kW-class MHD power generator, modification is carried out involving the combustion system, seed collecting method, and power generation channel, and reviews through experiments are conducted about the analysis and control of the boundary layer structure. In the operation test of the MHD power generator designed for prolonged operation, a test operation for resistance to heat and seeds continues more than 100 hours using a cold wall type power generation channel constituted of water cooled ceramics, and the ceramics are analyzed for failure and loss. Studies are also conducted involving MHD power generator heat exchangers, seed collecting methods, electrode materials for MHD power generators, heat-resistant materials for MHD power generators, thermal performance rating for MHD power plants, etc. In the research and development of superconductive electromagnets, superconductive electromagnets are developed and tested for 1000kW-class MHD power generators, and studies are conducted on turbine type helium liquefiers, superinsulated superconductive electromagnetic field generators, etc. (NEDO)

  19. Fiscal 2000 achievement report. Welfare technosystem research and development (Sapporo); 2000 nendo Welfare technosystem kenkyu kaihatsu (Sapporo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Activities are conducted on system technologies for ensuring comfortable living circumstances and thereby helping aged or handicapped people live independently in snowy cold regions. The research and development efforts center about the three fields of (1) in-house systems to help aged or handicapped people live an independent life, (2) in-home care equipment systems suitable for advanced welfare oriented residences, and (3) user interface controllers to improve on operating sensation in a motor driven wheelchair. In field (1), studies involve the development of low floor residences for snowy cold regions, improvement on entrances for independent residences helping the inhabitants lead an independent life, and functionally excellent designs for handrails for steps, stairs, or bathrooms. In field (2), surveys are conducted concerning design improvements and their acceptability relative to a universal welfare equipment controller, optimum sound that welfare equipment alarms should produce, and transfer devices. In field (3), studies are made about motor driven wheelchair controllers. (NEDO)

  20. Achievement report on developing inverse manufacturing system in fiscal 1998; 1998 nendo inverse manufacturing system no kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    Research and development has been performed on a circulating type production system, or an inverse manufacturing system, to minimize the environmental load in the entire life cycle of industrial products from design to manufacturing, maintenance, recovery, and re-utilization. In developing the recycling information system, discussion and extraction were executed on the data to be exchanged between manufacturers and users in the inverse society. A new individual parts history control system was developed. In developing the recycling processing system, a prototype system was evaluated by using hypothetical data, wherein the possibility of improving the recycling processing efficiency and reducing the cost was verified. In addition, trial design was made on a recycling processing plant in consideration of the cost effect to get the future plant image. In fabricating the inverse manufacturing products, a prototype concept model was made for information terminal devices. Development was performed on such elementary technologies as the easy-to-disintegrate structure technology, self-integration connecting structure and environmental hysteresis detection system. (NEDO)

  1. FY 1999 report on the results on analysis of protein functions; 1999 nendo tanpakushitsu kino kaiseki seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    This project is aimed at construction of the intellectual infrastructures for biotechnologies, in order to accelerate development of the Japanese technologies and activate their application to industries. Described herein are the FY 1999 results. These infrastructures are for functional analysis of protein which will be one of the key issues in genome analysis, and collection and analysis of biological information. This project includes a total of 9 research and development themes for four research categories: frequency analysis of gene expression (development of the gene expression profile database system for functional analysis of human genome, and analysis of the gene expression and protein functions by the ECA chip technology), function analysis by the biological model (high-performance analysis by the bio-project, database system for drug metabolizing enzymes, analysis of gene functions using mutant mice, and simple genome function analysis of murine individuals using the RNAi effect), protein expression (function validation of unknown human genes based on the useful biological model, and protein function analysis using multi-purpose destination vectors), and protein function prediction by the information science method. (NEDO)

  2. Achievement report for fiscal 1982 on Sunshine Program. Coal energy; 1982 nendo sunshine keikaku seika hokokusho. Sekitan energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-07-01

    This research program consists of (1) the solid catalyst-aided reforming of various petroleum based oils and heavy coal oils into Solvolysis solvents and the secondary hydrogenolysis, (2) a search for pre-treatment for improvement on the sub-bituminous coal liquefaction yield, and (3) a search for measures for improvement on the brown coal liquefaction yield. Studied in this fiscal year are (1) the high-temperature short-contact time liquefaction of brown coal, (2) the role of catalyst support for selective upgrading of SRC (solvent refined coal), and (3) reforming of thermal melting feature of low rank coal by preliminary deashing at room temperature. In relation with Item (1), it is found that the dehydrogenation or reaction to carbonization of molecules involved in hydrogen donation is structure-sensitive but that thermolysis of coal is accelerated under high-temperature conditions to allow transfer hydrogen to contribute uniformly. It is deemed also that matching is excellent between hydrogen transfer and thermolysis, that the solvent dissolution level is elevated, and that the reaction short in duration inhibits consecutive polymerization reaction. These are supposed to be effective in improving on the liquefaction yield and in rendering heavy constituents lighter. In relation with Item (2), it is found that the experimentally manufactured catalysts are effective in reducing the weight of heavy constituents. In relation with Item (3), a carbonization reforming method is experimentally implemented in which the ash that affects carbonization is further removed by a pre-treatment at room temperature. (NEDO)

  3. Outline of fiscal 1967 achievements in research on MHD power generation; 1967 nendo MHD hatsuden kenkyu seika gaiyo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1968-09-01

    Compiled are the results of studies conducted in fiscal 1967 on MHD (magnetohydrodynamic) power generation. In the test operation and modification of a 1,000kW-class MHD power generator at the Electrical Research Laboratory, a test is conducted using Faraday-type electrodes. It is then found that this configuration results in a maximum output of approximately 700kW, which is less than expected. In the experimental construction at the Hitachi, Ltd., of a machine capable of a long-term operation, an MHD power generator is built for a continuous operation of 100 hours with an maximum output of 2kW, and a 110-hour power generation is successfully achieved with a maximum output of 1.9kW. In the research and development of heat exchangers, tests are conducted for a bulkhead type heat exchanger, heat accumulator type heat exchanger, molten slag type heat exchanger, and a gas/liquid 2-phase flow type heat exchanger. In the study of heat-resisting insulators, materials based on zirconate, magnesia, thoria, zirconia, etc., are tested. In addition, studies are conducted on electrode materials, superconductive electromagnets (small superconductive electromagnets for MHD power generators, turbine type helium liquefiers, superconductive wires for 70-kilogauss electromagnets, etc.), and thermal performance rating. (NEDO)

  4. 1998 Annual Study Report. Standardization of color reproduction management; 1998 nendo seika hokokusho. Iro saigen kanri (color management) no hyojunka

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Standardization of color reproduction management is aimed at realization of the most urgently needed areas of the color reproduction management for international standardization. This R and D program is aimed at drafting the standards for color information devices and their characteristics, and proposing the drafts. Factors which deteriorate color reproduction stability of input and output devices are classified and analyzed, devices for evaluation are selected, and extents of the deterioration are measured and evaluated, in order to extract the problems involved in the color reproduction models for the current input and output devices. Standardization of color management on the multi-spectrum color images is attempted for business printing, where effectiveness of a fluorescent ink containing a fluorescent material is noted for expansion of the color reproduction range for printing color images with the conventional YMCK inks. Basic aspects of the fluorescent colors are measured, to verify the methods for measuring fluorescent body colors. As a result, new knowledge is obtained. The standard images for flesh color evaluation are produced, and the methods for analyzing the data obtained by the tests, including the subjective tests, are established. These lead to establishment of the standards for preferred flesh color of the yellow races. (NEDO)

  5. Fiscal 2000 achievement report. Welfare technosystem research and development (Mizusawa); 2000 nendo walfare technosystem kenkyu kaihatsu (Mizusawa) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    For assisting aged people, healthy and living alone, in living without help, activities were conducted for (1) an electrical transmission experiment connecting residences (two, inhabited for the experiment) and a remote location (Techno-House) and (2) the development of a home server equipped with an electrocardiograph. Under item (1), data collected by sensors (occupancy sensor, open/close sensor, flame sensor, waterflow sensor) installed at the residences occupied by aged persons living alone were forwarded to Techno-House via CATV (cable television) and analyzed for the study of elderly people's behavior and daily life pattern. It was found that using this system the behavior of elderly people living alone might be detected even in the absence of their intention to report or communicate. Under item (2), an Ni-based electrode sheet was fabricated and installed in a bed and, via the sheet and a CATV channel, cardiographic waveforms were transmitted to Techno-House where the data were put into an analyzer for the examination of the elderly person's physical conditions. (NEDO)

  6. Fiscal 1997 achievement report. Research and development of synergy ceramics; 1997 nendo synergy ceramics no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    Research and development is conducted on two subjects, that is, 1) hyper organized structure control technology and 2) structural element control technology. In addition, joint research and development is conducted on the creation of new materials by hyper organized structure controlling, hyper organized structure controlling for ceramics by a structurization reaction process, designing of precursors to ceramics, and the hyper organized structure control for ceramics by nanostructure process control. The joint research and development endeavors further deal with re-entrusted projects which involve researches on sintered structure control by powdery particulate structure control; dynamic process of synergy ceramics; oxynitride liquids, glasses, and glass-ceramics; and multifunctional ceramic laminates for engineering applications. Under subject 1), researches are made on the development of precursors into ceramics by utilizing chemical reactions of organic metal compounds, and analyses are conducted into the effects, exerted by the molecular structures of precursors and the conditions of a reaction for their development into ceramics, on the microstructures and various properties of the ceramics to be composed. Under subject 2), high strength, great hardness, and high resistance to wear are realized by allowing the precipitation of nano-particulates in crystals of a fine and very compact sintered body of alumina. (NEDO)

  7. Summarized achievement report on the Sunshine Project in fiscal 1980 (Hydrogen energy); 1980 nendo seika hokokusho gaiyoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-04-01

    This paper summarizes the achievement report on the Sunshine Project in fiscal 1980 for hydrogen energy research. In hydrogen manufacturing using the electrolytic process, improvements were made on membranes and electrodes. Solid electrolyte electrolysis is also under research. Researches are continued on reaction, separating operation, and device materials for the iodine system cycle in the thermo-chemical method. In the iron system cycle, a reaction experimenting equipment was fabricated on the trial basis, and tests and evaluation were performed on the material and heat balances. In the mixed system cycle, researches on the light irradiation electrolytic process were continued, whereas the light collecting rate was raised by using a lens to increase light intensity, having enhanced successfully the reaction rate to 60 to 80%. A heat diffusion column for HI decomposition and separation (hydrogen acquisition) was discussed in terms of chemical engineering. Development works are continued on metal hydrides for hydrogen transportation, and durability tests are also being performed. Same applies to hydrogen storage. A model burner was fabricated on the trial basis, and catalytic combustion was studied as development of a combustion technology that matches the requirements for safe hydrogen combustion and suppression of NOx emission. Searches were continued on catalysts and solid electrolyte materials for fuel cells. Thin film sold electrolyte fuel cells constructed by using the evaporation process are also being studied. The paper also describes measures for hydrogen safety assurance and researches on energy systems. (NEDO)

  8. FY 1981 Report on the results of Sunshine Project. Coal energy; 1981 nendo sunshine keikaku seika hokokusho. Sekitan energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-07-01

    This report presents the results of (researches on solvolysis liquefaction mechanisms and reaction promotion with oil- and coal-based solvents), conducted as part of the research and development project for coal liquefaction techniques. The FY 1981 program includes researches on (1) the effects of liquefaction reaction conditions on liquefaction yield and production of light products for coal species of low degree of carbonization, including brown coal, (2) the effects of pretreatment of coal on its liquefaction reactivity, and (3) up-grading of the solvolysis coal liquid (SCL). For the item (1), HA240 (hydrogenated Ashland's A240) is used to investigate its liquefaction capacity for various coal species of low degree of carbonization, including brown coal. For the item (2), the effects of pretreatment in a hot water bath with reflux was investigated for sub-bituminous coal in the FY 1980. In the FY 1981, various pretreatment methods are attempted for enhancing liquefaction reactivity of brown coal. As a result, it is found that ash content of brown coal is decreased to one-third of the initial level, when it is treated in a diluted hydrochloric acid bath with reflux. For the item (3), SCL hydrogenated by Birch reduction (B-SCL, 1) is compared with H-SCL with respect to properties, structures and thermal crackability, to discuss the items required for the catalyst to be used in the second stage by clarifying effectiveness of the catalyst. (NEDO)

  9. Fiscal 2000 achievement report. Welfare technosystem research and development (Chofu); 2000 nendo welfare technosystem kenkyu kaihatsu (Chofu) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Research and development efforts are exerted to realize (1) a variable function residential circumstance system for the aged people and (2) a medical welfare and life assisting information system for helping the aged or handicapped people lead an independent life. Under item (1), a variable function residential circumstance system under which functions of the residence may be changed dependent upon inhabitants' degree of debility will be developed, and an information system will be developed under which medical welfare assistance and life assistance are integrated. Under item (2), residences, welfare appliances, and nurse/attendant assisting systems will be assessed and examined. In fiscal 2000, under item (1), a variable function residential unit was fabricated and was inhabited experimentally by people approximately 1 to 4 in the degree of need for nursing care, and problems were isolated to be discussed toward putting the system to practical use. Under item (2), physical power required for nursing and attending was measured using medical assistance appliances for in-home nursing care installed at Welfare Technohouse Chofu, and ergonomic studies were conducted with a view to relieving the load to be imposed upon those engaged in the nursing and attending work. (NEDO)

  10. Fiscal 1998 achievement report on welfare technosystem research and development. Kyoto; 1998 nendo walfare technosystem kenkyu kaihatsu (Kyoto) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    To be ready for the computing-everywhere age to come, it is necessary to create environments in which the barrier-free utilization is ensured of various apparatuses of the daily routine, such as various bodily function substituting apparatuses capable of compensating for the degraded functions of disabled or aged individuals. Under the circumstances, a system for building man-machine interfaces in the home or the like is required, and fundamental technologies of architecture and information infrastructure have to be established on which the development of technologies for the field involved will proceed. Concerning the technologies already in existence in this field of research, a survey is conducted of the status of research and development of information interface techniques primarily at Stanford University, and a report is made thereon. Also reported is the information obtained at Technology and Persons with Disabilities Conference 1999. The result of a survey of the trend of research and development of the smart house under the TIDE (Technology Initiative for Disabled and Elderly People) project and the result of a survey of an information standardization project for equipment control in Europe are reported, and the result of a survey of the approach of Kyoto's welfare apparatus distributors to the development of equipment is made known. (NEDO)

  11. Achievement report for fiscal 1998. Multimedia system for the disabled; 1998 nendo seika hokokusho. Shogaisha taio multimedia system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    Development has been made on the element technologies for a multimedia system for the disabled. In developing the non-visual graphical user interface (GUI) access system, a non-visual access system to enable the visually disabled to access a GUI system by utilizing sound and tactile devices was developed. In developing the three-dimensional sound utilizing information providing system, a system was developed, in which information on screen arrangement of the GUI in a personal computer is presented as spatial sound positions by using the three-dimensional sound control technology. The system can be operated non-visually using a mouse by controlling movements of a cursor. The current fiscal year has improved three-dimensional sound producing devices, three-dimensional sound interface, and how to handle their applications. User evaluations were also performed. Functions were expanded and improved in a system and an optical media reader that enable the visually disabled person to read printed papers by himself. Development was made also on a function to link the system with a total system. (NEDO)

  12. Fiscal 1999 achievement report. Research and development of synergy ceramics; 1999 nendo synergy ceramics no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    Studies are conducted on three subjects, which are the development of 1) high-temperature energy materials technology, 2) ultrasophisticated materials technology, and 3) high-performance active materials technology. Under subject 1), high-strength porous materials are to be developed, which are resistant to heat and corrosion, tolerant of damage and deformation, and light in weight. In addition, relative to fluid transmission, materials are to be developed, which are highly resistant to heat, corrosion, and thermal impact, and capable of separating and removing particulates of powder dust. Under subject 2), efforts are under way to develop two technologies, related to materials creation and their application. The former technology involves the development of a process of simultaneously equipping materials with high wear resistance, desired friction factors, and desired mechanical and thermal characteristics; a process of equipping them with a trace damage detecting function; and a process of simultaneously equipping them with functions of restoration from accidents and of self-lubrication. Relative to the latter technology, efforts are conducted, in coordination with the endeavors for the above-said materials creation technology, to develop materials and their application with attention paid to some specified functions. Under subject 3), self-complete type ceramic materials not requiring an external driving power source are to be developed, in which a selective cleaning function and environmental energy conversion function are amalgamated. (NEDO)

  13. Achievement report for fiscal 1998. Esophageal vocalization aid system; 1998 nendo seika hokokusho. Shokudo hassei hojo sochi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    Development has been made on element technologies for an esophageal vocalization aid system. With regard to the speaker, selection and trial production were performed on a speaker used for a phono-coupler to be used in coupling with a telephone transmitter. Performance not differing from that in the currently used telephone set was obtained in the overall characteristics evaluation using a dummy telephone circuitry. For the microphone, two kinds of hands-free microphones were fabricated on a trial basis. In order to develop pitch extraction and amplitude pitch conversion systems, pitch extraction performances were compared and discussed on the following five methods: the auto-correlation method, the Cepstram method, the average magnitude difference function (AMDF) method, the simplified inverse filter tracking (SIFT) method, and the time-domain excitation extractor using minimum perturbation operator (TEMPO) method. The hauling phenomenon, having come up as a problem in an auxiliary digital device, was analyzed to discuss methods for prevention thereof. In developing a voice/unvoiced distinction judgment method, a method using low domain power and high domain power was discussed. Development has been made on exclusive ICs, a voice analyzer, and the using feeling enhancing technology. In developing a total system, a digital unit incorporated esophageal vocalization aid system was developed and improved. (NEDO)

  14. Summary of reports on 1979 result of Sunshine Project. Solar energy; 1979 nendo sunshine keikaku seika hokokusho gaiyoshu. Taiyo energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-04-01

    This report is a compilation of all outlines of the results concerning 'solar energy' for which R and D was carried out as a part of Sunshine Project in fiscal 1979. The research subjects (items of the studies) are written below. 1. Solar energy system (measurement of spectral irradiance, utilization system, and meteorological investigation); 2. Solar thermal power generation system; 3. Photovoltaic power generation system (basic research on solar cells, silicon vertical ribbon crystal, silicon horizontal ribbon crystal, particle non-acceleration growth type thin film silicon crystal, particle acceleration growth type thin film silicon crystal, new type solar cells, secondary to quaternary compound semiconductor solar cells, and photovoltaic power generation system); 4. Solar cooling, heating and hot water supply system (evaluation system, newly-built private residential system, existing private residential system, multiple dwelling system, large building system, synthetic resin materials, glass based materials, and metallic materials); 5. Solar energy new utilization method (new power generation system and materials); 6. R and D on solar thermal power generation plant (R and D on pilot plant, experimental research for developing plant on curved surface converging method, and experimental research for developing plant on tower converging method). (NEDO)

  15. Summary of the FY 1988 Sunshine Project results. Hydrogen energy; 1988 nendo sunshine keikaku seika hokokusho gaiyoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-04-01

    Outlined herein are the results of researches on hydrogen energy as part of the FY 1988 Sunshine Project results. Researches on the techniques for producing hydrogen by electrolysis of water using a polymer electrolyte include development of power-supplying materials for electrolysis at high current density, and basic studies on the electrolysis using an OH ion conducting type polymer electrolyte. Researches on the techniques for producing hydrogen by electrolysis with hot steam include development of the materials, techniques for processing these materials, and electrolysis performance tests. Researches on the techniques for transporting hydrogen by metal hydrides include development of hydrogen-occluding alloys of high bulk density, and techniques for evaluating characteristics of metal hydrides. Researches on the techniques for storing hydrogen include those on alloy molding/processing techniques, hydrogen-storing metallic materials, and new hydrogen-storing materials. Researches on the techniques for utilizing hydrogen include those on energy conversion techniques using hydrogen-occluding alloys, and hydrogen-fueled motors. Researches on the techniques for safety-related measures include those on prevention of embrittlement of the system materials by hydrogen. (NEDO)

  16. Summary of the FY 1989 Sunshine Project results. Hydrogen energy; 1989 nendo sunshine keikaku seika hokokusho gaiyoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-04-01

    Outlined herein are the results of researches on hydrogen energy as part of the FY 1989 Sunshine Project results. Researches on the techniques for producing hydrogen by electrolysis of water using a polymer electrolyte include those on the SPE electrolysis at high temperature and current density, and basic studies on the electrolysis using an OH ion conducting type polymer electrolyte. Researches on the techniques for producing hydrogen by electrolysis with hot steam include development of the materials, techniques for processing these materials, and electrolysis performance tests. Researches on the techniques for transporting hydrogen by metal hydrides include development of hydrogen-occluding alloys of high bulk density, and techniques for evaluating characteristics of metal hydrides. Researches on the techniques for storing hydrogen include those on hydrogen-storing metallic materials, alloy molding/processing techniques, and new hydrogen-storing materials. Researches on the techniques for utilizing hydrogen include those on energy conversion techniques using hydrogen-occluding alloys, and hydrogen-fueled motors. Researches on the techniques for safety-related measures include those on prevention of embrittlement of the system materials by hydrogen. (NEDO)

  17. Outline of fiscal 1969 achievements in research on MHD power generation; 1969 nendo MHD hatsuden kenkyu seika gaiyo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-07-01

    Compiled are the results of studies conducted in fiscal 1969 on MHD (magnetohydrodynamic) power generation. In the operation test and modification of the 1,000kW-class MHD power generator, the operation test continues from the preceding fiscal year using high-temperature air as oxidant, and the growth of boundary layer in the channel is determined. In the operation test of the MHD power generator designed for prolonged operation, insulation walls, electrode materials, and structures capable of prolonged operation are developed and tested. In the research of MHD power generator heat exchangers, studies are made about the bulkhead type and heat accumulator types (stationary type, rotary type, and falling-grain type). In addition, studies are conducted about seed collecting methods, MHD power generator electrode materials, heat-resisting insulators, and thermal performance rating. In the research and development of superconductive electromagnets, studies are conducted about superconductive electromagnets for 1kW MHD power generators, ferromagnetic superconductive electromagnets for 1,000kW-class MHD power generators, 45-kilogauss col type superconductive electromagnets, turbine type helium liquefier, high current density col type superconductive electromagnets, superinsulated magnetic field generators, etc. (NEDO)

  18. Fiscal 1998 achievement report on welfare technosystem research and development. Tokushima; 1998 nendo walfare technosystem kenkyu kaihatsu (Tokushima) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The project aims to construct a real-time system capable of searching a wider living area through establishing a management system centralized by remote control by improving on radio transmitters in a communication network and on a central station communication control system centering about a health and welfare office, for alleviating the burden of the nursing of old persons who wander, for preventing them from accidents attributable to wandering, and for finding and protecting them in time. For the construction of such a system, surveys and studies are conducted for the preparation of fundamental designs for personal data files on individuals carrying radio transmitters, monitor screen manipulation, program for acquiring information from a transmitter about its current position and for receiving information from the terminal station, and a frequency selecting program or the like to give instructions to the terminal station to probe the frequency on which the missing person's transmitter operates. In this fiscal year, specifications are studied of software programs based on data obtained from an experiment conducted for the practical application of a search network system utilizing the currently available radio direction finding technique, which effort is exerted mainly at the infirmary of Hanoura-cho, Tokushima Prefecture. (NEDO)

  19. Development of environmentally friendly universal controller. Data and materials; 1998 nendo kankyo taio universal controller no kaihatsu seika hokokusho. Shiryohen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    Research and development was carried out for an 'environmentally friendly universal controller (UC)' which would be 'user-friendly and energy-saving' when used with electrical home appliances, and data and materials on them were compiled into this volume. It covers the specifications (Versions 0.6 and 0.51) of a newly developed two-way controller protocol, the specification (Version 0.1) of two-way remote control IrDA-C communication unit hardware, an infrared communication protocol IrDa Control, and the like. It also accommodates information collected through surveys of technological trends as reflected in technical literature, Internet home pages, catalogs, and the like, concerning the user-friendliness of electrical home appliances, remote control, domestic consumption of electric power, and the like. Also covered is the result of surveys of patents involving environmentally friendly UC related technologies, namely, Japanese patents (from applications made in 1979 through disclosures made in 1998) and U.S. patents (registrations made in 1982 and thereafter). Furthermore, it contains the result of surveys of actualities of domestic use conducted for the purpose of clarifying the effect of environmentally friendly UC introduction, how such UCs are being accepted by the public, and the conditions that should be satisfied for their popularization. (NEDO)

  20. Fiscal 2000 achievement report. Welfare technosystem research and development (Kamogawa); 2000 nendo welfare technosystem kenkyu kaihatsu (Kamogawa) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    For the purpose of assisting in-home medical care, a system to enable in-home acquisition, compression, accumulation, distribution, and regeneration of auscultatory sounds (cardiac sound, respiratory sound) is added to telemedicine assisting system technologies for remotely located doctors' decisions and instructions for in-home medical care. In fiscal 2000, for improvement on the already-developed system, operationality was improved, uptake was realized of still images (digital camera pictures) mainly for diseases in dematology where such is strongly demanded, and a transmitter function was augmented. The system enables the PHS (personal handyphone system) aided exchange of medical data between portable terminals on patrol and (doctors') personal computers through the personal computer server in the hospital. Doctors are able to administer remote telemedicine now that biomimetic information on remotely located patients such as still medical images and auscultatory sounds necessary for diagnosing is available in the hospital. (NEDO)

  1. Fiscal 1999 research achievement report on the development of SNPs related technologies; 1999 nendo SNPs kanren gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Efforts are made to develop specimen processing technologies for modifying and enabling various kinds of specimens to automatically undergo SNP (single nucleotide polymorphism) analysis for medicine development and clinical diagnostic activities and to develop technologies and apparatuses to enable rapid, inexpensive, and simple search and analysis of SNPs using DNA (deoxyribonucleic acid) chips and mass spectrometry. Activities are conducted in the four fields involving (1) the development of a practical clinical system for rapid detection and analysis of SNPs, (2) research and development of an SNP scoring system using bar-coded oligonucleotides and magnetic beads, (3) research and development of a high-speed SNP analysis system using a mass spectrometer, and (4) the development of a high throughput SNP analysis line. Efforts exerted in field (1) involve a protein fixation method using plasma polymerization and its application to DNA arrays, development of an SNP detection method using human genomes, construction of a rapid DNA detection device using an electric field, development of an SNP analysis system using the solid phase HPA (hybridization protection assay) method, and SNP analysis using solid phase ligation. (NEDO)

  2. Fukushima Daiichi Unit 1 power plant containment analysis using GOTHIC

    International Nuclear Information System (INIS)

    Ozdemir, Ozkan Emre; George, Thomas L.; Marshall, Mervin D.

    2015-01-01

    Highlights: • The inclusion of vent heat transfer had a significant impact on the overall containment response. • The vent heat transfer and condensation results in lower containment pressure. • The reduced gas transfer to the wetwell via the vents results in higher hydrogen concentration in the drywell. - Abstract: This paper is a part of Fukushima Technical Evaluation Project (EPRI, 2013a, 2014a, 2015) which investigates various aspects of the Fukushima Daiichi event using the GOTHIC code. The analysis takes advantage of the capability of GOTHIC to model certain aspects of the system geometry and behavior in more detail than typically considered in containment performance analysis. GOTHIC is a general purpose thermal hydraulics code that is used extensively in the nuclear industry for system design support, licensing support and safety analysis. It has the capability to model 3-dimensional flow behavior including the effects of turbulence, diffusion and buoyancy (EPRI, 2014b). This allows GOTHIC to be used in cases where mixing effects and stratification are important. The analysis presented here considers the events at Fukushima Daiichi Unit 1 (1F1) following the tsunami and leading up to the time of the hydrogen detonation in the 1F1 Reactor Building. The 1F1 MAAP5 Baseline Scenario (EPRI, 2013b) is used to define the steam, hydrogen and carbon-monoxide source terms from the primary system and the core concrete interaction. The model incorporates three dimensional modeling of the drywell, wetwell and connecting vent system that can predict the 3-dimensional flow patterns and the temperature and gas distributions. The model also includes leakage to the surrounding reactor building and the wetwell vent to the stack. The 3D containment model includes models for the heat transfer from the steam and gas in the drywell vent system to the torus room, wetwell gas space and pool. Inclusion of vent heat transfer had a significant impact on the overall containment

  3. Emergency feature. Great east Japan earthquake disaster Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Kawata, Tomio; Tsujikura, Yonezo; Kitamura, Toshiro

    2011-01-01

    The Tohoku Pacific Ocean earthquake occurred in March 11, 2011. The disastrous tsunami attacked Fukushima Daiichi nuclear power plants after automatically shutdown by the earthquake and all motor operated pumps became inoperable due to station black out. Despite the strenuous efforts of operators, if caused serious accident such as loss of cooling function, hydrogen explosion and release of large amount of radioactive materials into the environment, leading to nuclear power emergency that ordered resident to evacuate or remain indoors. This emergency feature consisted of four articles. The first was the interview with the president of JAIF (Japan Atomic Industrial Forum) on how to identify the cause of the accident completely, intensify safety assurance measures and promote discussions on a role of nuclear power in the nation's entire energy policy toward the reconstruction. Others were reactor states and events sequence after the accident with trend data of radiation in the reactor site, statement of president of AESJ (Atomic Energy Society of Japan) on nuclear crisis following Tohoku Pacific Ocean earthquake our response and my experience in evacuation life. (T. Tanaka)

  4. Research investigation report on Fukushima Daiichi nuclear accident

    International Nuclear Information System (INIS)

    2012-03-01

    This report was issued in February 2012 by Rebuild Japan Initiative Foundation's Independent Investigation Commission on the Fukushima Daiichi Nuclear Accident, which consisted of six members from the private sector in independent positions and with no direct interest in the business of promoting nuclear power. Commission aimed to determine the truth behind the accident by clarifying the various problems and reveal systematic problems behind these issues so as to create a new starting point by identifying clear lessons learned. Report composed of four chapters; (1) progression of Fukushima accident and resulting damage (accident management after Fukushima accident, and effects and countermeasure of radioactive materials discharged into the environment), (2) response against Fukushima accident (emergency response of cabinet office against nuclear disaster, risk communication and on-site response against nuclear disaster), (3) analysis of historical and structural factors (technical philosophy of nuclear safety, problems of nuclear safety regulation of Fukushima accident, safety regulatory governance and social background of 'Safety Myth'), (4) Global Context (implication in nuclear security, Japan in nuclear safety regime, U.S.-Japan relations for response against Fukushima accident, lessons learned from Fukushima accident - aiming at creation of resilience). Report could identify causes of Fukushima accident and factors related to resulting damages, show the realities behind failure to prevent the spread of damage, and analyze the overall structural and historical background behind the accidents. (T. Tanaka)

  5. Industrial Safety and Utopia: Insights from the Fukushima Daiichi Accident.

    Science.gov (United States)

    Travadel, Sébastien; Guarnieri, Franck; Portelli, Aurélien

    2018-01-01

    Feedback from industrial accidents is provided by various state or even international, institutions, and lessons learned can be controversial. However, there has been little research into organizational learning at the international level. This article helps to fill the gap through an in-depth review of official reports of the Fukushima Daiichi accident published shortly after the event. We present a new method to analyze the arguments contained in these voluminous documents. Taking an intertextual perspective, the method focuses on the accident narratives, their rationale, and links between "facts," "causes," and "recommendations." The aim is to evaluate how the findings of the various reports are consistent with (or contradict) "institutionalized knowledge," and identify the social representations that underpin them. We find that although the scientific controversy surrounding the results of the various inquiries reflects different ethical perspectives, they are integrated into the same utopian ideal. The involvement of multiple actors in this controversy raises questions about the public construction of epistemic authority, and we highlight the special status given to the International Atomic Energy Agency in this regard. © 2017 The Authors Risk Analysis published by Wiley Periodicals, Inc. on behalf of Society for Risk Analysis.

  6. Update on the SDTP Sponsored Fukushima Daiichi Related Assesment Activities

    International Nuclear Information System (INIS)

    Allison, Chris

    2014-01-01

    Following the accident at Fukushima Daiichi, Innovative Systems Software and several other members of an international software development and training group (SDTP) started an assessment of the possible core/vessel damage states of Units 1-3. This assessment, using a reference RELAP/SCDAPSIM Laguna Verde BWR model developed by CNSNS, the Mexican nuclear regulatory body, was presented initially to the IAEA emergency response team for Fukushima in March of 2011. Our assessment for the IAEA indicated that significant fuel melting, fuel slumping, and lower head failure was likely for Units 1 and 3. The results for Unit 2 were inconclusive because of the complex thermal hydraulic conditions at the time of likely fuel melting. Since that time the SDTP related assessment activities have continued on three main fronts: (a) continued analysis using our representative Laguna Verde model to determine the likely failure modes leading to an un-intentional depressurization of the vessel during a SBO in a BWR, (b) development of improved RELAP/SCDAPSIM models to treat the likely mode of lower core support structure melting and failure, and (c) design studies for proposed fuel melting and relocation experiments in Japan to support model development and cleanup related activities, The presentation gives a brief summary and discussion of these activities.

  7. Effects of the Fukushima Daiichi nuclear accident on goshawk reproduction

    Science.gov (United States)

    Murase, Kaori; Murase, Joe; Horie, Reiko; Endo, Koichi

    2015-01-01

    Although the influence of nuclear accidents on the reproduction of top predators has not been investigated, it is important that we identify the effects of such accidents because humans are also top predators. We conducted field observation for 22 years and analysed the reproductive performance of the goshawk (Accipiter gentilis fujiyamae), a top avian predator in the North Kanto area of Japan, before and after the accidents at the Fukushima Daiichi nuclear power plant that occurred in 2011. The reproductive performance declined markedly compared with the pre-accident years and progressively decreased for the three post-accident study years. Moreover, it was suggested that these declines were primarily caused by an increase in the air dose rate of radio-active contaminants measured under the nests caused by the nuclear accidents, rather than by other factors. We consider the trends in the changes of the reproductive success rates and suggest that internal exposure may play an important role in the reproductive performance of the goshawk, as well as external exposure. PMID:25802117

  8. Applicability of health physics lessons learned from the Three Mile Island Unit 2 accident to the Fukushima Daiichi accident.

    Science.gov (United States)

    Bevelacqua, J J

    2012-02-01

    The TMI-2 and Fukushima Daiichi accidents appear to be dissimilar because they involve different reactor types. However, the health physics related lessons learned from TMI-2 are applicable, and can enhance the Fukushima Daiichi recovery effort. Copyright © 2011 Elsevier Ltd. All rights reserved.

  9. The Fukushima Daiichi nuclear accident final report of the AESJ investigation committee

    CERN Document Server

    Atomic Energy Society of Japan

    2015-01-01

    The Magnitude 9 Great East Japan Earthquake on March 11, 2011, followed by a massive tsunami struck  TEPCO’s Fukushima Daiichi Nuclear Power Station and triggered an unprecedented core melt/severe accident in Units 1 – 3. The radioactivity release led to the evacuation of local residents, many of whom still have not been able to return to their homes. As a group of nuclear experts, the Atomic Energy Society of Japan established the Investigation Committee on the Nuclear Accident at the Fukushima Daiichi Nuclear Power Station, to investigate and analyze the accident from scientific and technical perspectives for clarifying the underlying and fundamental causes, and to make recommendations. The results of the investigation by the AESJ Investigation Committee has been compiled herewith as the Final Report. Direct contributing factors of the catastrophic nuclear incident at Fukushima Daiichi NPP initiated by an unprecedented massive earthquake/ tsunami – inadequacies in tsunami measures, severe accident ma...

  10. Unsolved issues related to thermal-hydraulics in the suppression chamber during Fukushima Daiichi accident progressions

    International Nuclear Information System (INIS)

    Mizokami, Shinya; Yamada, Daichi; Honda, Takeshi; Yamauchi, Daisuke; Yamanaka, Yasunori

    2016-01-01

    On 11 March 2011, the Great East Japan Earthquake and Tsunami hit the Fukushima Daiichi Nuclear Power Station. The Fukushima Daiichi Units 1-3 lost all DC and AC power supplies, which set in motion a chain of events that led to releases of radioactivity to the environment. Since then, TEPCO has made many efforts to investigate the accident progressions and the status of the reactors and containment vessels. However, there still exist several tens of unsolved issues to be investigated for the fully understanding of the accident. In this paper, we introduce the unsolved issues related to thermal-hydraulics in the suppression chamber during the Fukushima Daiichi accident progressions. Especially, in Units 2 and 3, there are possibilities that thermal stratification inside their suppression chambers played an important role. It is important that these phenomena are addressed following both theoretical and experimental approaches as support to severe accident simulations. (author)

  11. The Human Aspect of the Fukushima Daiichi Accident

    International Nuclear Information System (INIS)

    Anegawa, T.; Kawano, A.

    2016-01-01

    Recognizing itself as the main party involved in the nuclear accident triggered by the Tohoku-Chihou-Taiheiyo-Oki Earthquake on March 11, 2011, Tokyo Electric Power Company (TEPCO) has performed accident investigation from various aspects. Results of the investigation are reported mainly in two reports; (1) Fukushima Nuclear Accident Analysis Report (June 20, 2012), which identified the timeline and the proximate causes of the accident, and (2) Summary of Fukushima Nuclear Accident and Nuclear Safety Reform Plan (March 29, 2013) to set forth the results of the investigation and provide an analysis of the background factors surrounding the accident and countermeasures taken. This presentation will first provide overview of the accident response at Fukushima Daiichi and Daini Nuclear Power Stations. Voices from the first responders at the sites will be introduced in order to share thoughts of individuals involved in the emergency response. Summary of retrospective study of the accident by one of the shift supervisors at the time of the accident will be presented in order to share the facts that happened at main control rooms. The shift supervisor and his crew had to manage the situation for extended period of time that exceeded the scenarios that they had been trained, in a situation with no lightning and high radiation condition. During the accident response, shift supervisors had to decide to dispatch some of his crew members to the field to open valves, check the status of equipment etc., in the situation where the high radiation exposure is foreseen. The presentation will include conflict of shift supervisors and crew focusing on the human aspects. In addition, actions being taken at the Emergency Response Centers (ERC) set up at the seismic-isolated building on-site and the Headquarters in Tokyo will be shared focusing on the human aspects related to the accident progress. This includes difficult decisions to dispatch first responders to the field, in the

  12. Environmental remediation following the Fukushima-Daiichi accident

    Energy Technology Data Exchange (ETDEWEB)

    Tagawa, A.; Miyahara, K.; Nakayama, S. [Japan Atomic Energy Agency - JAEA, 4-49 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1184 (Japan)

    2013-07-01

    A wide area of Fukushima Prefecture was contaminated with radioactivity released by the Fukushima Daiichi nuclear accident. The decontamination pilot projects conducted by JAEA aimed at demonstrating the applicability of different techniques to rehabilitate affected areas. As most radioactive cesium is concentrated at the top of the soil column and strongly bound to mineral surfaces, there are 3 options left to decrease the gamma dose rate (usually measured 1 m above the ground surface): the stripping of the contaminated topsoil (i.e. direct removal of cesium), the dilution by mixing and the soil profile inversion. The last two options do not generate waste. As the half-distance of {sup 137}Cs gammas in soil is in the order of 5-6 cm (depending on density and water content), the shielding by 50 cm of uncontaminated deep soil would theoretically reduce gamma doses by about 3 orders of magnitude. Which option is employed depends basically on the Cesium concentration in the topsoil, averaged over a 15-cm thickness. The JAEA's decontamination pilot projects focus on soil profile inversion and topsoil stripping. Two different techniques have been tested for the soil profile inversion: one is the reversal tillage by which surface soil of thickness of several tens of cm is reversed by using a tractor plough and the other is the complete interchanging of contaminated topsoil with uncontaminated subsoil by using a back-hoe. Reversal tillage with a tractor plough cost about 30 yen/m{sup 2}, which is an order of magnitude lower than that of topsoil-subsoil interchange (about 300 yen/m{sup 2}). Topsoil stripping is significantly more costly (between 550 yen/m{sup 2} and 690 yen/m{sup 2} according to the equipment used)

  13. Activities for the remediation of TEPCO's Fukushima Daiichi nuclear power plant

    International Nuclear Information System (INIS)

    Kinoshita, Hirofumi; Kometani, Yutaka; Asano, Takashi; Ishiwata, Masayuki; Fukasawa, Tetsuo; Tadokoro, Takahiro; Nagumo, Yasushi; Kani, Yuko; Matsui, Tetsuya

    2013-01-01

    With the aim of fulfilling recovery work for the Fukushima Daiichi NPP, technological efforts have been made for the development of a survey robot system, adequate communication infrastructure technologies, high radiation environment compatible gamma cameras, heavy machinery-type robots (ASTACO-SoRa), remote decontamination devices (AROUNDER), and contaminated waste water treatment system. We have developed a new type of absorbents which remove cesium (Cs) and strontium (Sr) simultaneously at a high removal rate of 99 % or more. We will provide valuable solutions and rational systems for waste water treatment using this developed adsorbent as well as other various adsorbents for the recovery of Fukushima Daiichi NPP

  14. Severe accident management: radiation dose control, Fukushima Daiichi and TMI-2 nuclear plant accidents

    International Nuclear Information System (INIS)

    Shaw, Roger

    2014-01-01

    This presentation presents valuable dose information related to the Fukushima Daiichi and Three Mile Island Unit 2 (TMI-2) Nuclear Plant accidents. Dose information is provided for what is well known for TMI-2, and what is available for Fukushima Daiichi. Particular emphasis is placed on the difference between the type of reactors involved, overarching plant damage issues, and radiation worker dose outcomes. For TMI-2, more in depth dose data is available for the accident and the subsequent recovery efforts. The comparisons demonstrate the need to understand the wide variation in potential dose management measures and outcomes for severe reactor accidents. (author)

  15. Lessons learned from the Fukushima Dai-ichi accident and responses in NRA regulatory requirements

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi

    2014-01-01

    The author would like to present significant lessons learned from the TEPCO’s Fukushima Dai-ichi accident and responses in regulatory requirements developed by the Nuclear Regulation Authority for power-producing light water reactors. The presentation will cover prevention of structures, systems and components failures, measures to prevent common cause failures, prevention of core damage, mitigation of severe accidents, emergency preparedness, continuous improvement of safety, use of probabilistic risk assessment, and post-accident regulation on the Fukushima Dai-ichi. (author)

  16. Activities for the remediation of TEPCO's Fukushima Daiichi nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kinoshita, Hirofumi; Kometani, Yutaka; Asano, Takashi; Ishiwata, Masayuki; Fukasawa, Tetsuo [Hitachi-GE Nuclear Energy, Ltd., 2-2, Omika-cho, 5-chome, Hitachi-shi Ibaraki-ken, 319-1221 (Japan); Tadokoro, Takahiro; Nagumo, Yasushi; Kani, Yuko; Matsui, Tetsuya [Hitachi Research Laboratory, Hitachi, Ltd. 2-2, Omika-cho, 5-chome, Hitachi-shi Ibaraki-ken, 319-1221 (Japan)

    2013-07-01

    With the aim of fulfilling recovery work for the Fukushima Daiichi NPP, technological efforts have been made for the development of a survey robot system, adequate communication infrastructure technologies, high radiation environment compatible gamma cameras, heavy machinery-type robots (ASTACO-SoRa), remote decontamination devices (AROUNDER), and contaminated waste water treatment system. We have developed a new type of absorbents which remove cesium (Cs) and strontium (Sr) simultaneously at a high removal rate of 99 % or more. We will provide valuable solutions and rational systems for waste water treatment using this developed adsorbent as well as other various adsorbents for the recovery of Fukushima Daiichi NPP.

  17. Fukushima Daiichi - delivery of contaminated water into the Pacific ocean and possible consequences for the marine ecosystem; Fukushima Daiichi. Ableitungen und deren moegliche Auswirkungen in der Meeresumwelt

    Energy Technology Data Exchange (ETDEWEB)

    Nies, Hartmut [Bundesamt fuer Seeschifffahrt und Hydrographie (BSH), Hamburg (Germany). Abt. Meereskunde

    2015-06-01

    The nuclear power plant Fukushima Daiichi is sited at the coast of the Japanese island Honshu. Most of the cooling water for the three destroyed reactors units 1-3 and the nuclear fuel in the spent fuel pool of unit-4 were uncontrolled delivered into the groundwater and the Pacific Ocean. As a consequence high concentrations of I-131, Cs-134 and Cs-137 in the coastal waters have to be assumed. The contribution analyzed the possible consequences for the marine ecosystem. A drift time of 5 to 7 years toward the coast of North America is expected. The planning of the marine monitoring program MEXT is described. Radiation measurements in the coastal water up to 200 km distance from Daiichi were performed. The highest radionuclide concentrations of Cs-137 and Cs-134 were found in the fine grained sediments. No increased radioactivity in seafood is expected.

  18. Research and development towards decommissioning of Fukushima Daiichi Nuclear Power Plants

    International Nuclear Information System (INIS)

    Minato, Kazuo

    2013-01-01

    Towards the decommissioning of Fukushima Daiichi Nuclear Power Plants, science-based research and development is important and useful, as well as technology and engineering development. Research and development activities based on radiation chemistry, radiochemistry, thermodynamics, etc., have contributed to safe and efficient decommissioning of the plants. (author)

  19. JANSI’s Activities for Reflecting Lessons Learned from Fukushima Daiichi Accident

    International Nuclear Information System (INIS)

    Kugo, Akihide

    2014-01-01

    Conclusion: JANSI will continue to lay the groundwork for preventing an accident like the Fukushima Daiichi from ever happening again. JANSI will develop the system to provide an opportunity of “awareness” for operators to enhance nuclear safety and to follow-up their efforts continuously

  20. Fukushima Daiichi nuclear acccident. Damaged facilities of the site - Situation as on March 2018

    International Nuclear Information System (INIS)

    2018-03-01

    After a recall of the events that led to the Fukushima Daiichi accident, this note presents the situation in March 2018 of the actions of control of the damaged facilities and of their effluents. The last part presents the three steps of the facility control recovery plan retained by TEPCO

  1. Fukushima Daiichi: implications for carbon-free energy, nuclear nonproliferation, and community resilience.

    Science.gov (United States)

    Hall, Howard L

    2011-07-01

    Implications of the nuclear power plant accidents at Fukushima Daiichi are explored in this commentary. In addition to questions of nuclear reactor regulatory standards, broader implications on noncarbon-emitting energy production, nuclear nonproliferation objectives, and community resilience and emergency response against catastrophic events are explored. Copyright © 2011 SETAC.

  2. Peace Education, Domestic Tranquility, and Democracy: The Fukushima Daiichi Nuclear Disaster as Domestic Violence

    Science.gov (United States)

    Ide, Kanako

    2014-01-01

    This article is an attempt to develop a theory of peace education through an examination of the Fukushima Daiichi nuclear disaster. It examines why Japan did not avoid this terrible nuclear disaster. This is an educational issue, because one of the major impacts of Fukushima's catastrophe is that it indicates the failure of peace education. In…

  3. Station black out of Fukushima Daiichi Nuclear Power Station Unit 1 was not caused by tsunamis

    International Nuclear Information System (INIS)

    Ito, Yoshinori

    2013-01-01

    Station black out (SBO) of Fukushima Daiichi Nuclear Power Station Unit 1 would be concluded to be caused before 15:37 on March 11, 2011 because losses of emergency ac power A system was in 15:36 and ac losses of B system in 15:37 according to the data published by Tokyo Electric Power Co. (TEPCO) in May 10, 2013. Tsunami attacked the site of Fukushima Daiichi Nuclear Power Station passed through the position of wave amplitude meter installed at 1.5 km off the coast after 15:35 and it was also recognized tsunami arrived at the coast of Unit 4 sea side area around in 15:37 judging from a series of photographs taken from the south side of the site and general knowledge of wave propagation. From a series of photographs and witness testimony, tsunami didn't attack Fukushima Daiichi Nuclear Power Station uniformly and tsunami's arrival time at the site of Unit 1 would be far later than arrival time at the coast of Unit 4 sea side area, which suggested it would be around in 15:39. TEPCO insisted tsunami passed through 1.5 km off the coast around in 15:33 and clock of wave amplitude meter was incorrect, which might be wrong. Thus SBO of Fukushima Daiichi Nuclear Power Station Unit 1 occurred before tsunami's arrival at the site of Unit 1 and was not caused by tsunami. (T. Tanaka)

  4. Outline of the Fukushima Daiichi Accident. Lessons Learned and Safety Enhancements

    Directory of Open Access Journals (Sweden)

    Hirano Masashi

    2017-01-01

    This paper briefly presents the outline of the Fukushima Daiichi accident and summarizes the major lessons learned having been drawn and safety enhancements having been done in Japan for the purpose of giving inputs to the discussions to be taken place in the Special Invited Session “Fukushima, 5 years after”.

  5. Measuring Radioactivity from Fukushima Daiichi in New Mexico

    International Nuclear Information System (INIS)

    McNaughton, Michael

    2011-01-01

    On March 11, 2011, the Fukushima Daiichi nuclear power plant was damaged by the tsunami that followed the 'Great East Japan Earthquake,' and the reactor subsequently leaked radioactive material. In response, LANL augmented the routine ambient (AIRNET) and stack (Rad-NESHAP) measurements with three high-volume samplers: No.167 at the Old White Rock Fire Station; No.173 at the TA-49 gate, and No.211 at the Los Alamos Medical Center. Previous accidents, such as the Three-Mile-Island accident in 1979 and the Chernobyl accident in 1986, indicated that the most likely releases were (a) the noble gases: krypton and xenon; and (b) the volatile elements: cesium, tellurium, and iodine. At the latitude of Fukushima, the predominant winds across the Pacific Ocean are from west to east, and models predicted that the plume would arrive in the western US on about March 18. By this time the shorter-lived isotopes would have decayed. Therefore, the expected radionuclides were xenon-133, cesium-134, cesium-136, cesium-137, tellurium-132, iodine-131, and iodine-132. As expected, cesium-134, cesium-136, cesium-137, tellurium-132, iodine-131, and iodine-132 were all detected by all three high-volume samplers during March 17-21. The concentrations peaked during the March 24-28 period. After this, concentrations of all nuclides declined. In general, the concentrations were consistent with those measured by the EPA RadNet system and many other monitoring systems throughout the world. At the time of writing, preliminary results from the AIRNET and Rad-NESHAP systems are being reported. More detailed results are described in LA-UR-11-10304 and will be reported in full in the annual environmental report for 2011. All previous releases from nuclear reactors have been dominated by noble gases, primarily krypton and xenon, which are not measured by the high-volume samplers or the AIRNET system. However, in sufficient concentrations these and other fission products would be detected by NEWNET

  6. US Efforts in Support of Examinations at Fukushima Daiichi – 2016 Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Amway, P. [Exelon Corp., Chicago, IL (United States); Andrews, N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bixby, Willis [WWBX Consulting, Crofton, MD (United States); Bunt, R. [Southern Nuclear. Birmingham, AL (United States); Corradini, M. [Univ. of Wisconsin, Madison, WI (United States); Ellison, P. [GE-Hitachi, Wilmington, NC (United States); Farmer, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Farthing, T. [GE-Hitachi, Wilmington, NC (United States); Francis, M [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gabor, J. [Jensen Hughes, Baltimore, MD (United States); Gauntt, R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Henry, C. [Fauske and Associates, LLC, Burr Ridge, IL (United States); Humrickhouse, P. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kraft, S. [Nuclear Energy Inst., Washington, DC (United States); Linthicum, R. [Exelon Corp., Chicago, IL (United States); PWR Owners Group; Luangdilok, W. [Fauske and Associates, LLC, Burr Ridge, IL (United States); Lutz, R. [Lutz Nuclear Consulting, Asheville, NC (United States); Luxat, D. [Jensen Hughes, Baltimore, MD (United States); Maddox, J. [Inst. for Nuclear Power Operations, Atlanta, GA (United States); Negin, C. [CANegin & Associates; Paik, C. [Fauske and Associates, LLC, Burr Ridge, IL (United States); Plys, M. [Fauske and Associates, LLC, Burr Ridge, IL (United States); Rempe, J. [Rempe and Associates, Idaho Falls, ID (United States); Robb, K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sanders, R. [AREVA Federal Services, Charlotte, NC (United States); Wachowiak, R. [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Williamson, B. [Tennessee Valley Authority, Knoxville, TN (United States)

    2016-08-01

    Although it is clear that the accident signatures from each unit at the Fukushima Daiichi Nuclear Power Station (NPS) [Daiichi] differ, much is not known about the end-state of core materials within these units. Some of this uncertainty can be attributed to a lack of information related to cooling system operation and cooling water injection. There is also uncertainty in our understanding of phenomena affecting: a) in-vessel core damage progression during severe accidents in boiling water reactors (BWRs), and b) accident progression after vessel failure (ex-vessel progression) for BWRs and Pressurized Water Reactors (PWRs). These uncertainties arise due to limited full scale prototypic data. Similar to what occurred after the accident at Three Mile Island Unit 2, these Daiichi units offer the international community a means to reduce such uncertainties by obtaining prototypic data from multiple full-scale BWR severe accidents. Information obtained from Daiichi is required to inform Decontamination and Decommissioning activities, improving the ability of the Tokyo Electric Power Company Holdings (TEPCO) to characterize potential hazards and to ensure the safety of workers involved with cleanup activities. This document reports recent results from the US Forensics Effort to use information obtained by TEPCO to enhance the safety of existing and future nuclear power plant designs. This Forensics Effort, which is sponsored by the Reactor Safety Technologies Pathway of the Department of Energy Office of Nuclear Energy Light Water Reactor (LWR) Sustainability Program, consists of a group of US experts in LWR safety and plant operations that have identified examination needs and are evaluating TEPCO information from Daiichi that address these needs. Examples presented in this report demonstrate that significant safety insights are being obtained in the areas of component performance, fission product release and transport, debris end-state location, and combustible gas

  7. US Efforts in Support of Examinations at Fukushima Daiichi - 2016 Evaluations

    International Nuclear Information System (INIS)

    Amway, P.; Andrews, N.; Bixby, Willis; Bunt, R.; Corradini, M.; Ellison, P.; Farmer, M.; Farthing, T.; Francis, M; Gabor, J.; Gauntt, R.; Henry, C.; Humrickhouse, P.; Kraft, S.; Linthicum, R.; Luangdilok, W.; Lutz, R.; Luxat, D.; Maddox, J.; Negin, C.; Paik, C.; Plys, M.; Rempe, J.; Robb, K.; Sanders, R.; Wachowiak, R.; Williamson, B.

    2016-01-01

    Although it is clear that the accident signatures from each unit at the Fukushima Daiichi Nuclear Power Station (NPS) [Daiichi] differ, much is not known about the end-state of core materials within these units. Some of this uncertainty can be attributed to a lack of information related to cooling system operation and cooling water injection. There is also uncertainty in our understanding of phenomena affecting: a) in-vessel core damage progression during severe accidents in boiling water reactors (BWRs), and b) accident progression after vessel failure (ex-vessel progression) for BWRs and Pressurized Water Reactors (PWRs). These uncertainties arise due to limited full scale prototypic data. Similar to what occurred after the accident at Three Mile Island Unit 2, these Daiichi units offer the international community a means to reduce such uncertainties by obtaining prototypic data from multiple full-scale BWR severe accidents. Information obtained from Daiichi is required to inform Decontamination and Decommissioning activities, improving the ability of the Tokyo Electric Power Company Holdings (TEPCO) to characterize potential hazards and to ensure the safety of workers involved with cleanup activities. This document reports recent results from the US Forensics Effort to use information obtained by TEPCO to enhance the safety of existing and future nuclear power plant designs. This Forensics Effort, which is sponsored by the Reactor Safety Technologies Pathway of the Department of Energy Office of Nuclear Energy Light Water Reactor (LWR) Sustainability Program, consists of a group of US experts in LWR safety and plant operations that have identified examination needs and are evaluating TEPCO information from Daiichi that address these needs. Examples presented in this report demonstrate that significant safety insights are being obtained in the areas of component performance, fission product release and transport, debris end-state location, and combustible gas

  8. The third update of the Fukushima Daiichi Nuclear Station accident. September 1 through November 30, 2011

    International Nuclear Information System (INIS)

    Shibutani, Yu

    2011-01-01

    This article provides the third update of the Fukushima Daiichi accident that occurred on March 11, 2011. In the report of the first update of the Fukushima Daiichi accident on March 11 through May 31, the situation was reported on both on-site and off-site of the Fukushima Daiichi, including; failed cooldown of decay heat and meltdown of stricken reactors; emergency evacuation of local residents, radioactive contamination, spread of biased rumors by the information closure by government, regional cooperation with China, Taiwan and Korea, and visit of IAEA investigation team to Japan. The report of the second update on June 1 through August 31 reported the issues of, harsh public criticism against government and electric power companies, results of the public opinion poll, a sort of gentlemen's agreements between nuclear power companies and local governments which would be peculiar tradition in Japan, the first revision of the road map to cold shutdown of stricken reactors, and submission of report on Fukushima Daiichi accident to International Atomic Energy Agency (IAEA). This article provides the third update from September 1 through November 30, particularly on the issues of the second revision of the road map where the “cold shutdown” state should be reached before the end of 2011, the overview of governmental organization on the overall energy and nuclear policy, and the establishment of the nuclear disaster response headquarters (HQ) in the Prime Minister's Office. The HQ in collaboration with Tokyo Electric Power Company (TEPCO) decided the framework of road map plans, provision of various assistance and compensation for the residents affected by the nuclear incident, redefinition by the Nuclear Safety Commission for evacuation areas, recovery process of radioactive decontaminated areas, investigation and verification of the Fukushima Daiichi accident, reorganization of TEPCO management and financial system, establishment of damage compensation scheme

  9. Radiological and geophysical changes around the Fukushima Daiichi Nuclear Power Plant since the accident to the present time

    Science.gov (United States)

    Kolotkov, Gennady

    2013-04-01

    Detailed analysis of accidental released of radioactive material from Fukushima Daiichi nuclear power plant has shown that long-lived radionuclides add considerable support for intensity of ion formation. Based on the results of airborne monitoring by MEXT and DOE (total surface deposition of Cs134 and Cs137 inside 80 km zone of Fukushima Daiichi NPP) it has been calculated the spatial distribution of the intensity of ion formation and atmospheric electric conductivity. The evidence of plutonium in the Fukushima radioactive trace allows calculates the concentration of small, intermediate and large ions. The results show the excess of these parameters by several orders of magnitude since the accident to the present time. For example the concentration of small air ion in the area of Chernobyl is 7±2?102 cm-3, the Fukushima Daiichi NPP ones is 1.3?106 cm-3. The difference in the atmospheric bipolar electric conductivity is about 24 fS/m between the Chernobyl and the Fukushima Daiichi ones. The evaluation technique was used after Chernobyl disaster allows to make an analysis of ecological, hygiene requirements and other problems into the troposphere and on the soil intensity of ion formation in the area of Fukushima Daiichi nuclear power plant. The standard ion air differ by four orders of magnitude in the case for Fukushima Daiichi ones. Comparative study of the radiophysical characteristics of the atmosphere with the analogous ones in Chernobyl and application of identification of various types of the air pollution is discussed.

  10. Evaluation of re-criticality potential in Fukushima Dai-ichi reactors following core damage accidents

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The re-criticality potential of the debris-bed, formed of the degraded core materials, cannot be ruled out during the cooling-down procedure of the Fukushima Dai-ichi NPPs. In this study the re-criticality potential has systematically investigated based on the core disruption phase analysis using a IMPACT-SAMPSON code prepared by The Institute of Applied Energy (IAE). The results obtained for the re-criticality potential, characterized by the eigen-values k-eff dependent on the debris composition formed at the core, RPV bottom, and PCV pedestal, are reflected to the arguments on the re-criticality prevention measures, such as timing and concentration of boron-compounds, during the cooling-down process of the Fukushima Dai-ichi NPPs. (author)

  11. Current status and future planning of Fukushima Daiichi Nuclear Power Station after Great East Japan earthquake

    International Nuclear Information System (INIS)

    Inouer, Y.

    2012-01-01

    Fukushima Daiichi Nuclear Power Station (NPS) clean-up and decommissioning activities require a lot of R and D and careful project management due to its severity of damage. Inability of access inside the reactor and turbine buildings due to harsh environment results in large uncertainties which make the project planning difficult R and R activities will be conducted in parallel with on-site clean-up and maintenance activities. In order to cope with this unprecedented challenge, the government, laboratories, academicians, vendors, manufacturers, and other partners have joined together to support tokyo electric Power Company, Inc (TEPCO). This paper will summarize the current status and mid-and long-term plan for the clean-up and decommissioning of Units 1 to 4 of Fukushima Daiichi NPS as of March, 2012. (Author) 15 refs.

  12. Safety technical investigation activities for shipment of damaged spent fuels from Fukushima Daiichi Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Japan Nuclear Energy Safety Organization(JNES) carries out the investigation for damaged fuel transportation from Fukushima Daiichi Nuclear Power Station(1F) under safety condition to support Nuclear Regulation Authority (NRA). In 2012 fiscal year, JNES carried out the investigation of spent fuel condition in unit 4 of 1F and actual result of leak fuel transport in domestic /other countries. From this result, Package containing damaged fuel from unit 4 in 1F were considered. (author)

  13. Fukushima Daiichi Nuclear Power Plant accident: facts, environmental contamination, possible biological effects, and countermeasures

    OpenAIRE

    Anzai, Kazunori; Ban, Nobuhiko; Ozawa, Toshihiko; Tokonami, Shinji

    2011-01-01

    On March 11, 2011, an earthquake led to major problems at the Fukushima Daiichi Nuclear Power Plant. A 14-m high tsunami triggered by the earthquake disabled all AC power to Units 1, 2, and 3 of the Power Plant, and carried off fuel tanks for emergency diesel generators. Despite many efforts, cooling systems did not work and hydrogen explosions damaged the facilities, releasing a large amount of radioactive material into the environment. In this review, we describe the environmental impact of...

  14. Distribution of dose rates due to fallout from the Fukushima Daiichi reactor accident

    International Nuclear Information System (INIS)

    Minato, Susumu

    2011-01-01

    A number of dose rate data taken after the Fukushima Daiichi reactor accident occurred have been collected through official websites of prefectural governments. Subtracting natural background dose rates from these data, contributions due to fallout alone were evaluated. A train-borne survey was carried out to verify the accuracy of the contour map. The dose rate variation pattern obtained by the survey coincided fairly well with that of the map. (author)

  15. Decontamination and concrete core sampling by teleoperated robot at Fukushima Daiichi reactor buildings

    International Nuclear Information System (INIS)

    Watanabe, Masaru; Onitsuka, Hironori; Shimonabe, Noriaki; Fujita, Jun; Matsumura, Takumi; Okumura, Atsushi

    2015-01-01

    For decommissioning of Fukushima daiichi nuclear power station, reduction of the dose equivalent rates inside the reactor buildings is an important issue. Concrete core sampling from the buildings to investigate the contamination is necessary for study about effective decontamination. However, dose rate inside the reactor buildings is very high. For example, dose rate of 1st floor on the Unit 1 is 1.2 - 1820 [mSv / h], the Unit 2 is 2.5 - 220 [mSv / h] and Unit 3 is 2.2 - 4780 [mSv / h]. So it is difficult for workers to work long hours. Therefore, a teleoperated robot, named 'MHI-MEISTeR (Mitsubishi Heavy Industries - Maintenance Equipment Integrated System of Telecontrol Robot)', has been developed to conduct operations like concrete core samples from the reactor buildings. Actually, some concrete core samples from Fukushima daiichi were taken by MHI-MEISTeR. In addition, MHI-MEISTeR is designed as a versatile robot, and so it can conduct suction / blast decontamination works as well as concrete core sampling. The above operations were performed by MHI-MEISTeR in Fukushima daiichi nuclear power station. (author)

  16. What happened at Fukushima Daiichi Nuclear Power Plants. Verification of effects of earthquake and resulting tsunami

    International Nuclear Information System (INIS)

    Yamazaki, Tatsuhiro

    2012-01-01

    At 14:46 on March 11, 2011, the Tohoku District-off the Pacific Ocean Earthquake occurred. The magnitude of this earthquake was 9.0, the largest in Japan's recorded history, and afterwards enormous tsunami struck the Pacific coast of Tohoku District. This great earthquake and resulting tsunami struck the Fukushima Daiichi Nuclear Power Plants (NPPs) of Tokyo Electric Power Co. (TEPCO), whose cooling function was lost and suffered a severe nuclear accident. This article described the mechanism and safety measure of BWR type NPPs and verified how the great earthquake and resulting tsunami affected NPPs. Progression of the accident at Fukushima Daiichi NPPs was outlined. Damage by the earthquake could not be fully inspected but might not be significant to safety systems. However, the earthquake of longer duration time as much as about 250 sec caused failure of breaker or lightening arrester and also damage on electric facility such as transmission line insulator. Tsunami or inundation height was as high as O.P. (Onahama Pile) +11.5-15.5 m for Unit 1-4 reactor area while designed as O.P. +5.7 m, which caused blackout (power outage) and a reactor core meltdown at Fukushima Daiichi NPPs. (T. Tanaka)

  17. The NEA benchmark study of the accident at the Fukushima Daiichi NPP

    International Nuclear Information System (INIS)

    Koganeya, Toshiyuki

    2015-01-01

    In November 2012, the NEA, under the aegis of the Committee on the Safety of Nuclear Installations (CSNI), initiated a joint research project called the Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF). Objectives of this project include supporting Fukushima Daiichi decommissioning by analysing accident progression and the current status of the reactors, such as fuel debris distribution in the reactor pressure vessels and primary containment vessels in preparation for fuel debris removal. A second objective of the project is to improve SA (severe analysis) codes through comparisons with data from the Fukushima reactors. So as to enhance communication between analysts and those involved in decommissioning activities, participants in the project have been discussing the remaining uncertainties in relation to understanding the accident and the data needs from the viewpoint of the analysts. Since the accident sequences at the Fukushima Daiichi site include a wide range of phenomena, a phased approach is being applied in this benchmark exercise while awaiting more detailed information on debris examination and other factors. This article provides an overview of the project (scope, input data and boundary conditions, participants (from eight countries), analytical approach - common case and best estimate case) as well as an outline of the project's next phase (BASF phase 2) that begins in June 2015

  18. Thermal stratification in a scaled-down suppression pool of the Fukushima Daiichi nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Byeongnam, E-mail: jo@vis.t.u-tokyo.ac.jp [Nuclear Professional School, The University of Tokyo, 2-22 Shirakata, Tokai-mura, Ibaraki 319-1188 (Japan); Erkan, Nejdet [Nuclear Professional School, The University of Tokyo, 2-22 Shirakata, Tokai-mura, Ibaraki 319-1188 (Japan); Takahashi, Shinji [Department of Nuclear Engineering and Management, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan); Song, Daehun [Nuclear Professional School, The University of Tokyo, 2-22 Shirakata, Tokai-mura, Ibaraki 319-1188 (Japan); Hyundai and Kia Corporate R& D Division, Hyundai Motors, 772-1, Jangduk-dong, Hwaseong-Si, Gyeonggi-Do 445-706 (Korea, Republic of); Sagawa, Wataru; Okamoto, Koji [Nuclear Professional School, The University of Tokyo, 2-22 Shirakata, Tokai-mura, Ibaraki 319-1188 (Japan)

    2016-08-15

    Highlights: • Thermal stratification was reproduced in a scaled-down suppression pool of the Fukushima Daiichi nuclear power plants. • Horizontal temperature profiles were uniform in the toroidal suppression pool. • Subcooling-steam flow rate map of thermal stratification was obtained. • Steam bubble-induced flow model in suppression pool was suggested. • Bubble frequency strongly depends on the steam flow rate. - Abstract: Thermal stratification in the suppression pool of the Fukushima Daiichi nuclear power plants was experimentally investigated in sub-atmospheric pressure conditions using a 1/20 scale torus shaped setup. The thermal stratification was reproduced in the scaled-down suppression pool and the effect of the steam flow rate on different thermal stratification behaviors was examined for a wide range of steam flow rates. A sparger-type steam injection pipe that emulated Fukushima Daiichi Unit 3 (F1U3) was used. The steam was injected horizontally through 132 holes. The development (formation and disappearance) of thermal stratification was significantly affected by the steam flow rate. Interestingly, the thermal stratification in the suppression pool vanished when subcooling became lower than approximately 5 °C. This occurred because steam bubbles are not well condensed at low subcooling temperatures; therefore, those bubbles generate significant upward momentum, leading to mixing of the water in the suppression pool.

  19. The reactor accident in Fukushima Daiichi. The consequence of design deficiencies and inadequate safety engineering; Der Reaktorunfall in Fukushima Daiichi. Folge fehlerhafter Auslegung und unzureichender Sicherheitstechnik

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-03-15

    The reactor accident in Fukushima Daiichi is discussed in the frame of design deficiencies and inadequate safety engineering. The progress of the accident as consequence of the earthquake and the tsunami is described. The radiological situation for the public is supposed to be blow the dose limit of 20 mSv/year. The WHO and UNSCEAR (United Nations Scientific Committee on the Effects of Atomic radiation) did not observe acute radiation injuries. The Japanese authorities have classified the accident to 7 of the INES scale. The German Atomforum e.V. considers the safety engineering of German NPPs to be superior to the Japanese situation due to higher emergency energy supply, extensive measures to reduce the hydrogen accumulation and mitigating measures for the accident management. German NPPS are considered highly robust as the EU stress tests have shown.

  20. Hydrogen combustion in a flat semi-confined layer with respect to the Fukushima Daiichi accident

    Energy Technology Data Exchange (ETDEWEB)

    Kuznetsov, Mike, E-mail: kuznetsov@kit.edu [Karlsruhe Institute of Technology, 76131 Karlsruhe (Germany); Yanez, Jorge [Karlsruhe Institute of Technology, 76131 Karlsruhe (Germany); Grune, Joachim; Friedrich, Andreas [Pro-Science GmbH, 76275 Ettlingen (Germany); Jordan, Thomas [Karlsruhe Institute of Technology, 76131 Karlsruhe (Germany)

    2015-05-15

    Graphical abstract: - Highlights: • Critical conditions for flame propagation regimes in a layer geometry are analyzed. • Numerical simulation of hydrogen explosion reproduces real strength of shock waves. • From 80 to 200 kg of hydrogen were exploded during Fukushima (Unit I) accident. • A sonic deflagration with TNT equivalent of 800 kg was the most probable regime. - Abstract: Hydrogen accumulations at the top of a containment or reactor building may occur due to the interaction of molten corium and water followed by a severe accident of a nuclear reactor (TMI, Chernobyl, Fukushima Daiichi). The hydrogen that is released from the reactor accumulates usually as a stratified semi-confined layer of hydrogen–air mixture. A series of large scale experiments on hydrogen combustion and explosion in a semi-confined layer of uniform and non-uniform hydrogen–air mixtures in the presence of obstructions or without them was performed at the Karlsruhe Institute of Technology (KIT). Different flame propagation regimes from slow subsonic to relatively fast sonic flames and then to detonations were experimentally investigated in different geometries and then simulated with COM3D code with respect to evaluate the amount of hydrogen that was involved in the Fukushima Daiichi Accident (FDA). The experiments were performed in a horizontal semi-confined layer with the dimensions 9 × 3 × 0.6 m with/without obstacles opened from below. The hydrogen concentration in the mixtures with air was varied in the range of 10–34 vol.% without or with a gradient of 20–60 vol.%H{sub 2}/m. Effects of hydrogen concentration gradient, layer thickness, obstruction geometry, average and maximum hydrogen concentration on the flame propagation regimes were investigated with respect to evaluate the maximum pressure loads on internal structures. Blast wave strength and dynamics of propagation after the explosion of the hydrogen–air mixture layer were numerically simulated to reproduce

  1. Insights Gained from Forensic Analysis with MELCOR of the Fukushima-Daiichi Accidents.

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, Nathan C. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gauntt, Randall O. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-10-01

    Since the accidents at Fukushima-Daiichi, Sandia National Laboratories has been modeling these accident scenarios using the severe accident analysis code, MELCOR. MELCOR is a widely used computer code developed at Sandia National Laboratories since ~1982 for the U.S. Nuclear Regulatory Commission. Insights from the modeling of these accidents is being used to better inform future code development and potentially improved accident management. To date, our necessity to better capture in-vessel thermal-hydraulic and ex-vessel melt coolability and concrete interactions has led to the implementation of new models. The most recent analyses, presented in this paper, have been in support of the of the Organization for Economic Cooperation and Development Nuclear Energy Agency’s (OECD/NEA) Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF) Project. The goal of this project is to accurately capture the source term from all three releases and then model the atmospheric dispersion. In order to do this, a forensic approach is being used in which available plant data and release timings is being used to inform the modeled MELCOR accident scenario. For example, containment failures, core slumping events and lower head failure timings are all enforced parameters in these analyses. This approach is fundamentally different from a blind code assessment analysis often used in standard problem exercises. The timings of these events are informed by representative spikes or decreases in plant data. The combination of improvements to the MELCOR source code resulting from analysis previous accident analysis and this forensic approach has allowed Sandia to generate representative and plausible source terms for all three accidents at Fukushima Daiichi out to three weeks after the accident to capture both early and late releases. In particular, using the source terms developed by MELCOR, the MACCS software code, which models atmospheric dispersion and

  2. The Fukushima Daiichi Accident. Report by the Director General [Chinese Version

    International Nuclear Information System (INIS)

    2015-08-01

    This report presents an assessment of the causes and consequences of the accident at the Fukushima Daiichi nuclear power plant in Japan, which began on 11 March 2011. Caused by a huge tsunami that followed a massive earthquake, it was the worst accident at a nuclear power plant since the Chernobyl disaster in 1986. The report considers human, organizational and technical factors, and aims to provide an understanding of what happened, and why, so that the necessary lessons learned can be acted upon by governments, regulators and nuclear power plant operators throughout the world. Measures taken in response to the accident, both in Japan and internationally, are also examined. The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is also available separately in Arabic, Chinese, English, French, Russian, Spanish and

  3. The Fukushima Daiichi Accident. Report by the Director General [Japanese Version

    International Nuclear Information System (INIS)

    2015-08-01

    This report presents an assessment of the causes and consequences of the accident at the Fukushima Daiichi nuclear power plant in Japan, which began on 11 March 2011. Caused by a huge tsunami that followed a massive earthquake, it was the worst accident at a nuclear power plant since the Chernobyl disaster in 1986. The report considers human, organizational and technical factors, and aims to provide an understanding of what happened, and why, so that the necessary lessons learned can be acted upon by governments, regulators and nuclear power plant operators throughout the world. Measures taken in response to the accident, both in Japan and internationally, are also examined. The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is also available separately in Arabic, Chinese, English, French, Russian, Spanish and

  4. The Fukushima Daiichi Accident. Report by the Director General [Spanish Version

    International Nuclear Information System (INIS)

    2015-08-01

    This report presents an assessment of the causes and consequences of the accident at the Fukushima Daiichi nuclear power plant in Japan, which began on 11 March 2011. Caused by a huge tsunami that followed a massive earthquake, it was the worst accident at a nuclear power plant since the Chernobyl disaster in 1986. The report considers human, organizational and technical factors, and aims to provide an understanding of what happened, and why, so that the necessary lessons learned can be acted upon by governments, regulators and nuclear power plant operators throughout the world. Measures taken in response to the accident, both in Japan and internationally, are also examined. The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is also available separately in Arabic, Chinese, English, French, Russian, Spanish and

  5. The Fukushima Daiichi Accident. Report by the Director General [Russian Version

    International Nuclear Information System (INIS)

    2015-08-01

    This report presents an assessment of the causes and consequences of the accident at the Fukushima Daiichi nuclear power plant in Japan, which began on 11 March 2011. Caused by a huge tsunami that followed a massive earthquake, it was the worst accident at a nuclear power plant since the Chernobyl disaster in 1986. The report considers human, organizational and technical factors, and aims to provide an understanding of what happened, and why, so that the necessary lessons learned can be acted upon by governments, regulators and nuclear power plant operators throughout the world. Measures taken in response to the accident, both in Japan and internationally, are also examined. The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is also available separately in Arabic, Chinese, English, French, Russian, Spanish and

  6. Corium Configuration and Penetration Tube Failure for Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    An, Sang Mo; Lee, Jae Bong; Kim, Hwan Yeol; Song, Jin Ho

    2016-01-01

    For the LWRs (light water reactors), the penetration tubes at the reactor vessel lower head are regarded as the most vulnerable structures along with a global vessel failure during a severe accident because they can be seriously damaged by a corium melt or debris relocated into the lower plenum of the vessel. The research on the penetration tube failure is of higher importance in the BWRs, as it could lead to melt discharge into the containment and subsequent release of radioactive materials to the environment due to the containment failure. There are more than one hundred of penetration tubes in the Fukushima Daiichi NPPs (nuclear power plants), such as ICM-GTs (in-core monitoring guide tubes), CRGTs (control rod guide tubes) and drain tubes. The ICM-GTs include SRMs (source range monitors), IRMs (intermediate range monitors), LPRMs (local power range monitors) and TIPs (traversing in-core probes), which are much thinner than other tubes. The experimental researches to investigate the corium configuration and the penetration tube failure for the Fukushima Daiichi NPPs were introduced and some meaningful results were summarized. It was shown that the corium ingot was separated into two layers, of which the upper layer was metal-rich while the lower one was oxide-rich. It seemed that B 4 C would contribute to reducing the density of the metallic melt. The two-layered configuration will provide useful information to understand the core melt progression and post-recovery actions for the Fukushima Daiichi NPPs. In addition, we performed a large scale penetration tube failure experiment for the SRM/IRM guide tube, and showed high possibilities of large amount of corium discharge out of the reactor vessel lower head, which followed by the tube melting in a very short time. We are planning to perform the penetration tube failure experiments for another dry tube of ICM-GT (LPRM guide tube), and later for the wet tube (CRGT)

  7. IAEA Coordinates International Mission on Remediation of Areas Off-site Fukushima Daiichi NPP

    International Nuclear Information System (INIS)

    2011-01-01

    Full text: The International Atomic Energy Agency (IAEA) will dispatch an international expert mission to Japan to assist the country in its planning to remediate the areas off-site from the Fukushima Daiichi Nuclear Power Plant. Following a request by the Government of Japan, the mission, comprising 12 international and IAEA experts from several countries, will visit Japan between 7 and 15 October 2011 under the leadership of Mr. Juan Carlos Lentijo, General Director for Radiation Protection at Spain's nuclear regulatory authority. The team will go to several locations in the Fukushima Prefecture and conduct meetings in Tokyo with Japanese officials to: Provide assistance to Japan in its plans to manage remediation efforts; Review the country's remediation strategies, plans and work; and Share its findings with the international community. The IAEA mission will provide an opportunity for the international experts to exchange views with the Japanese authorities involved in the decontamination effort and other interested parties. It will also provide an opportunity for the IAEA to take stock of lessons learned from this important decontamination initiative. At the end of the mission a preliminary summary report will be provided to the Government of Japan and be made publically available. The team is also planning to hold a press briefing at the end of the mission. The final report of the mission will be presented to the Government in the month following the conclusion of the mission. Background The accident at Fukushima Daiichi Nuclear Power Plant has led to the radiological contamination of large areas. The Government of Japan has been formulating a strategy and plans to implement countermeasures to remediate these areas. The IAEA organized an International Fact Finding Expert Mission Of The Fukushima Daiichi Nuclear Power Plant Accident Following The Great East Japan Earthquake And Tsunami, which was held between 24 May and 2 June 2011. The current mission is a

  8. Hydrogen combustion in a flat semi-confined layer with respect to the Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Kuznetsov, M.; Yanez, J.; Grune, J.; Friedrich, A.; Jordan, T.

    2012-01-01

    The hydrogen accumulation at the top of containment or reactor building may occur due to an interaction of molten corium and water followed by a severe accident of a nuclear reactor (TMI, Chernobyl, Fukushima Daiichi). The hydrogen, released from the reactor, accumulates usually as a stratified semi-confined layer of hydrogen-air mixture. A series of large scale experiments on hydrogen combustion and explosion in a semi-confined layer of uniform and non-uniform hydrogen-air mixtures in presence of obstructions or without them was performed at the Karlsruhe Inst. of Technology (KIT). Different flame propagation regimes from slow subsonic to relative fast sonic flames and then to the detonations were experimentally investigated in different geometries and then simulated with COMSD code with respect to evaluate amount of burnt hydrogen taken place during the Fukushima Daiichi Accident (FDA). The experiments were performed in a horizontal semi-confined layer with dimensions of 9x3x0.6 m with/without obstacles opened from below. The hydrogen concentration in the mixtures with air was varied in the range of 0-34 vol. % without or with a gradient of 0-60 vol. %H 2 /m. Effects of hydrogen concentration gradient, thickness of the layer, geometry of the obstructions, average and maximum hydrogen concentration on flame propagation regimes were investigated with respect to evaluate the maximum pressure loads of internal structures. Blast wave strength and dynamics of propagation after explosion of the layer of hydrogen-air mixture was numerically simulated to reproduce the hydrogen explosion process during the Fukushima Daiichi Accident. (authors)

  9. Corium Configuration and Penetration Tube Failure for Fukushima Daiichi Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    An, Sang Mo; Lee, Jae Bong; Kim, Hwan Yeol; Song, Jin Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    For the LWRs (light water reactors), the penetration tubes at the reactor vessel lower head are regarded as the most vulnerable structures along with a global vessel failure during a severe accident because they can be seriously damaged by a corium melt or debris relocated into the lower plenum of the vessel. The research on the penetration tube failure is of higher importance in the BWRs, as it could lead to melt discharge into the containment and subsequent release of radioactive materials to the environment due to the containment failure. There are more than one hundred of penetration tubes in the Fukushima Daiichi NPPs (nuclear power plants), such as ICM-GTs (in-core monitoring guide tubes), CRGTs (control rod guide tubes) and drain tubes. The ICM-GTs include SRMs (source range monitors), IRMs (intermediate range monitors), LPRMs (local power range monitors) and TIPs (traversing in-core probes), which are much thinner than other tubes. The experimental researches to investigate the corium configuration and the penetration tube failure for the Fukushima Daiichi NPPs were introduced and some meaningful results were summarized. It was shown that the corium ingot was separated into two layers, of which the upper layer was metal-rich while the lower one was oxide-rich. It seemed that B{sub 4}C would contribute to reducing the density of the metallic melt. The two-layered configuration will provide useful information to understand the core melt progression and post-recovery actions for the Fukushima Daiichi NPPs. In addition, we performed a large scale penetration tube failure experiment for the SRM/IRM guide tube, and showed high possibilities of large amount of corium discharge out of the reactor vessel lower head, which followed by the tube melting in a very short time. We are planning to perform the penetration tube failure experiments for another dry tube of ICM-GT (LPRM guide tube), and later for the wet tube (CRGT)

  10. Emergency operating procedures improvement based on the lesson learned from the Fukushima Daiichi accident

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Wen-Hsiung, E-mail: whwu1127@aec.gov.tw [Atomic Energy Council, 2F., No. 80, Sec.1, Chenggong Rd., Yonghe Dist., New Taipei City 234, Taiwan (China); Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Sec. 2, Guangfu Rd., Hsinchu City 300, Taiwan (China); Liao, Lih-Yih, E-mail: lyliao@iner.gov.tw [Institute of Nuclear Energy Research, Atomic Energy Council, No. 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 325, Taiwan (China)

    2016-12-01

    Highlights: • Discuss the problem of EOPs at the time of Fukushima accident to deal with the prolonged SBO. • Elaborate the potential risk accompanied with the emergency depressurization in the SBO. • Describe a special guideline to cope with Fukushima-like accidents and provide its technical basis. • Point out that Fukushima accident might have been prevented if improved EOPs had been used. • Propose key points and suggestions for improving the EOPs. - Abstract: One of the lessons learned from the Fukushima Daiichi accident is the emergency operating procedures (EOPs) have to be improved. The BWR Owners’ Group revised the emergency procedure guidelines and addressed the lesson learned from the Fukushima Daiichi accident in revision 3 in order to avoid loss of turbine-driven makeup water systems during reactor depressurization. However, the improvement deserves much more attention. The existing EOPs at the time of the accident may not be adequate enough for the prolonged station blackout condition, because resources required for performing the EOPs are vastly unavailable or gradually exhausted. The improved EOPs must not only permit early reactor pressure vessel depressurization, but also address the risk accompanied with the emergency depressurization. For this reason, Taiwan Power Company proposed the Ultimate Response Guideline (URG) to cope with Fukushima-like accidents. The main content of the URG is a two-stage depressurization strategy, namely the controlled depressurization and the emergency depressurization. The technical basis of the two-stage depressurization strategy was discussed in this paper. The effectiveness of the URG was verified by using TRAC/RELAP Advanced Computational Engine (TRACE). Besides, the emergency responses performed by Fukushima Daini nuclear power plant (Fukushima Daini NPP) were found to be very similar to the URG. The consequences of Fukushima Daini NPP somehow demonstrate that the URG is effective for Fukushima

  11. Fukushima Daiichi Nuclear Power Plant accident: facts, environmental contamination, possible biological effects, and countermeasures.

    Science.gov (United States)

    Anzai, Kazunori; Ban, Nobuhiko; Ozawa, Toshihiko; Tokonami, Shinji

    2012-01-01

    On March 11, 2011, an earthquake led to major problems at the Fukushima Daiichi Nuclear Power Plant. A 14-m high tsunami triggered by the earthquake disabled all AC power to Units 1, 2, and 3 of the Power Plant, and carried off fuel tanks for emergency diesel generators. Despite many efforts, cooling systems did not work and hydrogen explosions damaged the facilities, releasing a large amount of radioactive material into the environment. In this review, we describe the environmental impact of the nuclear accident, and the fundamental biological effects, acute and late, of the radiation. Possible medical countermeasures to radiation exposure are also discussed.

  12. MDEP Common Position CP-STC-02. Common Position Addressing Fukushima Daiichi Nuclear Power Accident

    International Nuclear Information System (INIS)

    2016-09-01

    Following the nuclear accident in Japan as a consequence of the earthquake and tsunami, the MDEP Members provide the following information, based on initial information available, to ensure adequate safety of new reactor design activities being undertaken pursuant to the MDEP program of work. Due to the extensive nature of the magnitude and duration of the Fukushima Daiichi NPP accident, it is important to consider lessons learnt at an early stage of the design. In this context, the extensive work done by the IAEA, the International Atomic Energy Agency, is also acknowledged. Vendors, licensees and applicants involved in New Design activities should examine the implications of the Fukushima Daiichi NPP accident and identify relevant issues to be taken into account to strengthen defense in depth. Those lessons learnt should include, but not be limited to, plans to assess the following: - Provisions taken in the design basis concerning flooding, earthquake, other extreme natural phenomena and combinations of external event hazards appropriate to each country, - The robustness of the plant to maintain its safety functions beyond the design basis hazards, - The capability of the plant to withstand extended loss of all electrical power supplies as well as prolonged loss of ultimate heat sink and other essential supplies, and - The capability of the plant to cope with such extreme situations, including provisions to manage severe accidents (such as combustible gas management). In assessing these areas, the effect of multiple units and nuclear fuel storages should be considered. The MDEP regulators will strive to harmonize approaches to incorporate lessons learnt in their ongoing national safety reviews of new reactors. Based on the design-specific common positions, this paper identifies the approaches to address potential safety improvements for several designs as related to lessons learned from the Fukushima Daiichi NPP accident or related issues. Designs being

  13. Telephone counseling for the public after the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Horiguchi, T.; Kojima, K.; Itoh, T.

    2011-01-01

    After the Fukushima Daiichi Nuclear Power Plant accident, Kinki University Atomic Energy Research Institute provided telephone counseling services in order to respond the public's growing concerns about radiation and nuclear energy. Three telephone lines were newly installed for the counseling and the number of consultation marked 705 between March 24 and April 2. In this report, by summarizing the contents of the counseling, we will show what the public concerned about shortly after the accident and report how we responded to the concerns. (author)

  14. SFR Safety Consideration in Light of Fukushima Dai-ichi Accident

    International Nuclear Information System (INIS)

    Yamaguchi, Akira

    2013-01-01

    SFR Considerations: Fukushima Dai-ichi Accident: • Combined LORL and LOHS type initiated from SBO; • High pressure water-steam cooling system: – Depressurization - Not needed; – Ultimate heat sink - Robust (NC to atmosphere); – Continuous injection - Not needed (large sensible heat capacity). • Severe accident management: – RPV failure resulted in depressurization - Elevated temperature; – Heat sink to atmosphere - Freeing risk, sodium fire risk; – Mobile power supply - External resource may not be needed; – Seawater injection with fire engines - Sodium injection not needed; • Containment performance and accessibility: – Containment - Large containment volume and low pressure system; – Explosives - Sodium fire and hydrogen explosion

  15. Analysis of Fukushima Daiichi Nuclear Power Station severe accident using MAAP4.05

    International Nuclear Information System (INIS)

    Yoo, Jae S.; Suh, Kune Y.; Kim, Dong M.

    2011-01-01

    Rather extensive reactor core meltdown and partial melt-through that took place at the Fukushima Daiichi nuclear power plants (NPPs) on March 11, 2011 had been caused by a massive earthquake followed by tsunami rarely seen in history. The happening had turned into an unprecedented serious accident since the Chernobyl Unit 4 in 1986 that extended over multiple reactors simultaneously. A previous documentary survey, NUREG-1150 report provides significant insights into how a severe accident might develop at a boiling water reactor (BWR) and the range of consequences. NUREG-1150 did identify the importance of loss of power accidents for a BWR. This paper describes recent analyses of the Fukushima Daiichi NPPs severe accident. Calculations were performed with the MAAP4.05 code by modifying the parameter file for the Peach Bottom Unit 2, a BWR 4 type in the Mark-I containment. Generally this is the same type of reactor as Fukushima Daiichi Units 2 and 3. This resulted in good understanding of the response of this type of early BWRs to prolonged loss of diesel generators and batteries. There is clearly vulnerability with this early type of BWRs which would be less onerous than later existing plant and new build designs. This analysis, however, was based on rather limited amount of information obtained at the time of preparing this report and adopted various estimates and assumptions for conditions necessary to run the analysis. Hence there persists considerable uncertainty in the results. MAAP4.05 was run pursuant to the observed data and chronology of Fukushima Daiichi Units 1 through 3 reported by the Tokyo Electric Power Company (TEPCO) as well as the Japanese Government. Severe accident scenarios have not only gone far beyond the design basis, but also exceeded the extent of multiple breakdowns assumed in the preparation for such accident management measures as the malfunction or loss of all the emergency core cooling system (ECCS) combined with the extended loss of

  16. Radiological protection and the Fukushima Daiichi accident. Responses of the key international organisations

    Energy Technology Data Exchange (ETDEWEB)

    Clement, Christopher

    2017-10-01

    The Fukushima Daiichi nuclear power plant accident in March 2011 shook the radiological protection world. All major organisations in the radiological protection field turned their eyes to Japan. Their actions, driven by their mandates, are reflected in their respective landmark reports on the accident. Reports of the International Commission on Radiological Protection, World Health Organisation, United Nations Scientific Committee on the Effects of Atomic Radiation, and International Atomic Energy Agency are summarised. Collaboration between key international organisations is strong, based in part on informal interactions which need to be backed up with formal relations to ensure solid long-term collaboration.

  17. Investigation and evaluation for environmental impact at Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    2012-01-01

    In 2012, JNES investigated the weather data and the environmental monitoring data and constructed the method to specify contribution of the environmental impact from each plant based on the dose analysis result at Unit 1-3 of Fukushima Daiichi NPP accident. JNES calculated the dose rate in an accident early stage based on analysis of a monitoring data. Moreover, JNES evaluated the dose by additional release of the radioactive material in case of assuming the loss of coolant injection to a nuclear reactor by the request of NISA. (author)

  18. Dose rate evaluation of workers on the operation floor in Fukushima-Daiichi Unit 3

    Science.gov (United States)

    Matsushita, Kaoru; Kurosawa, Masahiko; Shirai, Keisuke; Matsuoka, Ippei; Mukaida, Naoki

    2017-09-01

    At Fukushima Daiichi Nuclear Power Plant Unit 3, installation of a fuel handling machine is planned to support the removal of spent fuel. The dose rates at the workplace were calculated based on the source distribution measured using a collimator in order to confirm that the dose rates on the operation floor were within a manageable range. It was confirmed that the accuracy of the source distribution was C/M = 1.0-2.4. These dose rates were then used to plan the work on the operation floor.

  19. WHO's public health agenda in response to the Fukushima Daiichi nuclear accident

    International Nuclear Information System (INIS)

    Van Deventer, Emilie; Del Rosario Perez, Maria; Carr, Zhanat; Tritscher, Angelika; Fukushima, Kazuko

    2012-01-01

    The World Health Organization (WHO) has responded to the 2011 East-Japan earthquake and tsunami through the three levels of its decentralised structure. It has provided public health advice regarding a number of issues relating to protective measures, potassium iodide use, as well as safety of food and drinking water, mental health, travel, tourism, and trade. WHO is currently developing an initial health risk assessment linked to a preliminary evaluation of radiation exposure around the world from the Fukushima Daiichi nuclear accident. Lessons learned from this disaster are likely to help future emergency response to multi-faceted disasters. (note)

  20. Abbreviations [Annex to The Fukushima Daiichi Accident, Technical Volume 5/5

    International Nuclear Information System (INIS)

    2015-01-01

    This annex is a list of abbreviations used in the publication The Fukushima Daiichi Accident, Technical Volume 5/5. The list includes the abbreviations for: • General Safety Requirements; • International Commission on Radiological Protection; • Intensive Contamination Survey Area; • International Experts Meeting; • Ministry of Education, Culture, Sports, Science and Technology; • Ministry of the Environment; • Nuclear Damage Compensation and Decommissioning Facilitation Corporation; • Nuclear Emergency Response Headquarters; • nuclear power plant; • Nuclear Safety Commission; • OECD Nuclear Energy Agency; • Special Decontamination Area; • Specific Safety Requirements; • technical cooperation; • Three Mile Island; • United Nations Scientific Committee on the Effects of Atomic Radiation

  1. Emergency operating procedures improvement based on the lesson learned from the Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Wu, Wen-Hsiung; Liao, Lih-Yih

    2016-01-01

    Highlights: • Discuss the problem of EOPs at the time of Fukushima accident to deal with the prolonged SBO. • Elaborate the potential risk accompanied with the emergency depressurization in the SBO. • Describe a special guideline to cope with Fukushima-like accidents and provide its technical basis. • Point out that Fukushima accident might have been prevented if improved EOPs had been used. • Propose key points and suggestions for improving the EOPs. - Abstract: One of the lessons learned from the Fukushima Daiichi accident is the emergency operating procedures (EOPs) have to be improved. The BWR Owners’ Group revised the emergency procedure guidelines and addressed the lesson learned from the Fukushima Daiichi accident in revision 3 in order to avoid loss of turbine-driven makeup water systems during reactor depressurization. However, the improvement deserves much more attention. The existing EOPs at the time of the accident may not be adequate enough for the prolonged station blackout condition, because resources required for performing the EOPs are vastly unavailable or gradually exhausted. The improved EOPs must not only permit early reactor pressure vessel depressurization, but also address the risk accompanied with the emergency depressurization. For this reason, Taiwan Power Company proposed the Ultimate Response Guideline (URG) to cope with Fukushima-like accidents. The main content of the URG is a two-stage depressurization strategy, namely the controlled depressurization and the emergency depressurization. The technical basis of the two-stage depressurization strategy was discussed in this paper. The effectiveness of the URG was verified by using TRAC/RELAP Advanced Computational Engine (TRACE). Besides, the emergency responses performed by Fukushima Daini nuclear power plant (Fukushima Daini NPP) were found to be very similar to the URG. The consequences of Fukushima Daini NPP somehow demonstrate that the URG is effective for Fukushima

  2. Electrical systems design applications on Japanese PWR plants in light of the Fukushima Daiichi Accident

    International Nuclear Information System (INIS)

    Nomoto, Tsutomu

    2015-01-01

    After the Fukushima Daiichi nuclear power plant (1F-NPP) accident (i.e. Station Blackout), several design enhancements have been incorporated or are under considering to Mitsubishi PWR plants' design of not only operational plants' design but also new plants' design. Especially, there are several important enhancements in the area of the electrical system design. In this presentation, design enhancements related to following electrical systems/equipment are introduced; - Offsite Power System; - Emergency Power Source; - Safety-related Battery; - Alternative AC Power Supply Systems. In addition, relevant design requirements/conditions which are or will be considered in Mitsubishi PWR plants are introduced. (authors)

  3. Situation of Fukushima Dai-ichi power plant in Japan - June 1, 2011 status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on June 1, 2011 by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the cores of reactors 1, 2 and 3 of the Fukushima I site (Dai-ichi) and of the different spent fuel pools is briefly presented as well as the actions in progress for the control of environmental radioactive releases and for the progressive recovery of the facilities control. (J.S.)

  4. Situation of Fukushima Dai-ichi power plant in Japan - May 25, 2011 status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on May 25, 2011 by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the cores of reactors 1, 2 and 3 of the Fukushima I site (Dai-ichi) and of the different spent fuel pools is briefly presented as well as the actions in progress for the control of environmental radioactive releases and for the progressive recovery of the facilities control. (J.S.)

  5. Evaluation of seismic design by students made after Fukushima Dai-ichi accident

    International Nuclear Information System (INIS)

    Sugiyama, Ken-ichiro

    2012-01-01

    The sense of anxiety for safety of nuclear power plants among people in Japan has not disappeared after Fukushima Dai-ichi accident because of a typical country with frequent earthquakes. The provision of information for seismic design in nuclear power plants prepared for easier comprehension is always required in any kind of study meetings for the social acceptance of nuclear power plants. In the present paper, the effect of the provision of information made an attempt for students in Hokkaido University is reported. (author)

  6. In-core monitor housing replacement at Fukushima Daiichi Unit No.4

    International Nuclear Information System (INIS)

    Arai, Tomoyuki

    1999-01-01

    The in-core monitor (ICM) housing replacement of a Boiling Water Reactor (BWR) has been completed at Fukushima-Daiichi Unit No. 4 (1F4) of the Tokyo Electric Power Company (TEPCO) in Japan. Since cracking of the inside surface of an ICM housing was found in this unit, the ICM housing was replaced with one made of low-carbon stainless steel (SS) to improve Intergranular Stress Corrosion Cracking (IGSCC) resistance. This project is the first application of the replacement procedure for the ICM housing and employs various advanced technologies. The outline of the ICM housing replacement project and applied technologies are discussed in this paper. (author)

  7. Development of prediction models for radioactive caesium distribution within the 80-km radius of the Fukushima Daiichi nuclear power plant

    International Nuclear Information System (INIS)

    Kinase, Sakae; Sato, Satoshi; Saito, Kimiaki; Takahashi, Tomoyuki; Sakamoto, Ryuichi

    2014-01-01

    Preliminary prediction models have been studied for the radioactive caesium distribution within the 80-km radius of the Fukushima Daiichi nuclear power plant. The models were represented by exponential functions using ecological half-life of radioactive caesium in the environment. The ecological half-lives were derived from the changes in ambient dose equivalent rates through vehicle-borne surveys. It was found that the ecological half-lives of radioactive caesium were not constant within the 80-km radius of the Fukushima Daiichi nuclear power plant. The ecological half-life of radioactive caesium in forest areas was found to be much larger than that in urban and water areas. (authors)

  8. Analysis of accident progression in the TEPCO Fukushima Daiichi Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    One of the objectives of this study is to investigate the early stage of the TEPCO Fukushima Daiichi accident and to check the validity of the countermeasures against the accident. Last year the early stage of the accident was analyzed with use of RELAP5 code, and the longer term analysis was done by MELCOR code. This year, the simulation of reactor water level instrumentation behavior by MELCOR code was performed. Another objective of this study is to analyze of the long term cooling after the Fukushima Daiichi accident by TRACE5 code. In order to simulate the cooling conditions in Fukushima plants after the accident, the parametric calculations were done on the assumption of the existence of steam/liquid leak in Reactor Pressure Vessel (RPV) and Pressure Containment Vessel (PCV) and the variety of debris distribution in RPV and PCV. As a result, the debris distribution in RPV and PCV was estimated by referring plant parameter such as reactor pressure and temperature. (author)

  9. Dose estimation from food intake due to the Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    Yamaguchi, Ichiro; Terada, Hiroshi; Kunugita, Naoki; Takahashi, Kunihiko

    2013-01-01

    Since the Fukushima Daiichi nuclear power plant accident, concerns have arisen about the radiation safety of food raised at home and abroad. Therefore, many measures have been taken to address this. To evaluate the effectiveness of these measures, dose estimation due to food consumption has been attempted by various methods. In this paper, we show the results of dose estimation based on the monitoring data of radioactive materials in food published by the Ministry of Health, Labour and Welfare. The Radioactive Material Response Working Group in the Food Sanitation Subcommittee of the Pharmaceutical Affairs and Food Sanitation Council reported such dose estimation results on October 31, 2011 using monitoring data from immediately after the accident through September, 2011. Our results presented in this paper were the effective dose and thyroid equivalent dose integrated up to December 2012 from immediately after the accident. The estimated results of committed effective dose by age group derived from the radioiodine and radiocesium in food after the Fukushima Daiichi nuclear power plant accident showed the highest median value (0.19 mSv) in children 13-18 years of age. The highest 95% tile value, 0.33 mSv, was shown in the 1-6 years age range. These dose estimations from food can be useful for evaluation of radiation risk for individuals or populations and for radiation protection measures. It would also be helpful for the study of risk management of food in the future. (author)

  10. FUKUSHIMA DAI-ICHI ACCIDENT: LESSONS LEARNED AND FUTURE ACTIONS FROM THE RISK PERSPECTIVES

    Directory of Open Access Journals (Sweden)

    JOON-EON YANG

    2014-02-01

    Full Text Available The Fukushima Dai-Ichi accident in 2011 has affected various aspects of the nuclear society worldwide. The accident revealed some problems in the conventional approaches used to ensure the safety of nuclear installations. To prevent such disastrous accidents in the future, we have to learn from them and improve the conventional approaches in a more systematic manner. In this paper, we will cover three issues. The first is to identify the key issues that affected the progress of the Fukushima Dai-Ichi accident greatly. We examine the accident from a defense-in-depth point of view to identify such issues. The second is to develop a more systematic approach to enhance the safety of nuclear installations. We reexamine nuclear safety from a risk point of view. We use the concepts of residual and unknown risks in classifying the risk space. All possible accident scenarios types are reviewed to clarify the characteristics of the identified issues. An approach is proposed to improve our conventional approaches used to ensure nuclear safety including the design of safety features and the safety assessments from a risk point of view. Finally, we address some issues to be improved in the conventional risk assessment and management framework and/or practices to enhance nuclear safety.

  11. Fukushima Dai-Ichi accident: Lessons Learned and Future Actions from the Risk Perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Jooneon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-02-15

    The Fukushima Dai-Ichi accident in 2011 has affected various aspects of the nuclear society worldwide. The accident revealed some problems in the conventional approaches used to ensure the safety of nuclear installations. To prevent such disastrous accidents in the future, we have to learn from them and improve the conventional approaches in a more systematic manner. In this paper, we will cover three issues. The first is to identify the key issues that affected the progress of the Fukushima Dai-Ichi accident greatly. We examine the accident from a defense-in-depth point of view to identify such issues. The second is to develop a more systematic approach to enhance the safety of nuclear installations. We reexamine nuclear safety from a risk point of view. We use the concepts of residual and unknown risks in classifying the risk space. All possible accident scenarios types are reviewed to clarify the characteristics of the identified issues. An approach is proposed to improve our conventional approaches used to ensure nuclear safety including the design of safety features and the safety assessments from a risk point of view. Finally, we address some issues to be improved in the conventional risk assessment and management framework and/or practices to enhance nuclear safety.

  12. A Remote-operated System to Map Radiation Dose in the Fukushima Daiichi Primary Containment Vessel

    Science.gov (United States)

    Nancekievill, M.; Jones, A. R.; Joyce, M. J.; Lennox, B.; Watson, S.; Katakura, J.; Okumura, K.; Kamada, S.; Katoh, M.; Nishimura, K.

    2018-01-01

    This paper describes the development of a submersible system based on a remote-operated vehicle coupled with radiation detectors to map the interior of the reactors at the Fukushima Daiichi nuclear power station. It has the aim oflocating fuel debris. The AVEXIS submersible vehicle used in this study has been designed as a low-cost, potentially disposable, inspection platform that is the smallest of its class and is capable of being deployed through a 150 mm diameter access pipe. To map the gamma-ray environment, a cerium bromide scintillator detector with a small form factor has been incorporated into the AVEXIS to identify radioactive isotopes via gamma-ray spectroscopy. This provides the combined system with the potential to map gamma-ray spectra and particle locations throughout submerged, contaminated facilities, such as Units 1, 2 and 3 of the Fukushima Daiichi nuclear power plant. The hypothesis of this research is to determine the sensitivity of the combined system in a submerged environment that replicates the combination of gamma radiation and water submersion but at lower dose rates.

  13. The Fukushima Daiichi Accident. Technical Volume 4/5. Radiological Consequences. Annexes

    International Nuclear Information System (INIS)

    2015-08-01

    The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is available separately in Arabic, Chinese, English, French, Russian, Spanish and Japanese

  14. The Fukushima Daiichi Accident. Technical Volume 3/5. Emergency Preparedness and Response. Annexes

    International Nuclear Information System (INIS)

    2015-08-01

    The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is available separately in Arabic, Chinese, English, French, Russian, Spanish and Japanese

  15. The Fukushima Daiichi Accident. Technical Volume 1/5. Description and Context of the Accident. Annexes

    International Nuclear Information System (INIS)

    2015-08-01

    The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is available separately in Arabic, Chinese, English, French, Russian, Spanish and Japanese

  16. Response to the accident at TEPCO's Fukushima Daiichi Nuclear Power Plants

    International Nuclear Information System (INIS)

    Nei, Hisanori

    2012-01-01

    This article was reading from the author's plenary lecture at the thermal and nuclear power generation convention 2011, which was summary of the author edited report of Japanese government to IAEA ministerial conference on nuclear safety. The article consisted of (1) outlines of occurrence and development of the accident at TEPCO's Fukushima Daiichi Nuclear Power Plants (NPPs), (2) comparison of Fukushima Daiichi NPPs with other NPPs (Fukushima Daini, Onagawa and Tokai Daini NPPs), (3) major countermeasures to settle the situation regarding the accident, (4) comprehensive safety evaluation of other NPPs as response to the accident and (5) lessons learned from the accident so far. It was highly important to ensure power supplies and robust cooling functions of reactors, pressure containment vessels and spent fuel pools. 28 lessons were categorized into five groups such as (1) strengthen preventive measures against a severe accident, (2) enhancement of response measures against severe accidents, (3) enhancement of nuclear emergency responses, (4) reinforcement of safety infrastructure and (5) thoroughness of safety culture. (T. Tanaka)

  17. Radioactive pollution from Fukushima Daiichi nuclear power plant in the terrestrial environment.

    Science.gov (United States)

    Tazoe, H; Hosoda, M; Sorimachi, A; Nakata, A; Yoshida, M A; Tokonami, S; Yamada, M

    2012-11-01

    Major contaminants from venting and hydrogen explosions at the Fukushima Daiichi nuclear reactors between 12 and 15 March 2011 were transported northwestward and deposited on soil and plants via precipitation. Surface soils and plant leaves were sampled at 64 sites in the Fukushima Prefecture. The highest concentrations of (134)Cs (84.4 kBq kg(-1)) and (137)Cs (82.0 kBq kg(-1)) in surface soils were observed at Nagadoro in Iidate village located 32 km northwest from the Fukushima Daiichi nuclear power plant. Furthermore, (131)I, (129)Te, (129 m)Te, (110 m)Ag and (140)La were detected in the same samples. Outer surface of plant leaves, such as bamboo, cabbage and grasses were highly contaminated at the high-dose rate areas of Tsushima and Minami-Tsushima in Namie town. Mugwort leaves that grew after the pollution event had extremely low concentration of radionuclides; however, the plant/soil radiocaesium ratio was 0.023 ± 0.006. It is anticipated that decomposition of fallen leaves will promote recycling of radionuclides in the environment.

  18. Fiscal 1997 report on the results of the research on the development of high-performance industrial furnaces. Volume 2; 1997 nendo seika hokokusho (koseino kogyoro no kaihatsu ni kansuru kenkyu seika hokokusto)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    A R and D was conducted for the purpose of developing remarkable energy conservation/CO2 reduction technologies. In fiscal 1997, the five working groups about the following were formed to have animated discussions: the basic research, heating furnace, heat treatment furnace, melting furnace, and tubular heating furnace. The research subjects are the pursuit/deepening of the base study on flame structures in high temperature air combustion, critical heat recovery of the system in high temperature air combustion, examination of the basic common technology on the ultimate optimization of the material heat transfer, construction of general-purpose experimental database, setting-up of design standards for general-purpose high-performance industrial furnaces, presentation of examples of the actual trial design based on the design standards and feasibility study of the practical application, preparatory support of the field test project on high-performance industrial furnaces for commercialization/diffusion/spread, etc. Further, how to arrange the developmental results was studied to make the results of the project useful for study of the prompt commercialization. 442 refs., 1444 figs., 311 tabs

  19. Fiscal 1997 report on the results of the research on the development of high-performance industrial furnaces. Volume 3; 1997 nendo seika hokokusho (koseino kogyoro no kaihatsu ni kansuru kenkyu seika hokokusto)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    A R and D was conducted for the purpose of developing remarkable energy conservation/CO2 reduction technologies. In fiscal 1997, the five working groups about the following were formed to have animated discussions: the basic research, heating furnace, heat treatment furnace, melting furnace, and tubular heating furnace. The research subjects are the pursuit/deepening of the base study on flame structures in high temperature air combustion, critical heat recovery of the system in high temperature air combustion, examination of the basic common technology on the ultimate optimization of the material heat transfer, construction of general-purpose experimental database, setting-up of design standards for general-purpose high-performance industrial furnaces, presentation of examples of the actual trial design based on the design standards and feasibility study of the practical application, preparatory support of the field test project on high-performance industrial furnaces for commercialization/diffusion/spread, etc. Further, how to arrange the developmental results was studied to make the results of the project useful for study of the prompt commercialization. 442 refs., 1444 figs., 311 tabs.

  20. The Fukushima Daiichi Accident. Technical Volume 4/5. Radiological Consequences

    International Nuclear Information System (INIS)

    2015-08-01

    This technical volume describes the consequences associated with radioactivity and radiation from the accident at the Fukushima Daiichi nuclear power plant (NPP) for people and the environment. A number of international organizations have already issued reports on the potential health and environmental consequences of the accident, notably the World Health Organization (WHO) and the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). The intention of the assessments presented in this volume is to build on their work, using more recent data where available. Quantitative information arising from both personal and environmental monitoring has been provided by the Government of Japan. Section 4.1 provides the best estimates of the magnitude and form of radioactive releases during the accident to the atmosphere and directly into the surrounding sea. It also explains the movement of the discharged radionuclides through air and water and the eventual deposition of the atmospheric activity on land in Japan and other countries worldwide, as well as on the open oceans. The goal is to provide a consolidated repository of information on releases to, and levels of radionuclides in, the environment. Some of this information is used in the analyses in subsequent sections of this volume. Section 4.2 gives an overview of exposures to the main groups of emergency workers at the Fukushima Daiichi NPP, to groups of off-site workers and to members of the public. Where sufficient data are available, average effective dose and thyroid equivalent doses derived from personal measurements are compared with the results of previous assessments for specific locations, population groups and time periods. Section 4.3 summarizes relevant aspects of the system of radiation protection in place at the time of the accident. It includes an overview of the legislation and guidance used to implement the radiation protection framework in Japan. This section also provides a

  1. The Scope of the Common Commercial Policy after Lisbon: The Daiichi Sankyo and Conditional Access Services Grand Chamber Judgments

    NARCIS (Netherlands)

    Ankersmit, L.J.

    2014-01-01

    This case note discusses two important recent judgments rendered by the ECJ on the scope of the Common Commercial Policy. In Daiichi Sankyo (Case C-414/11), the Court overturned its previous case law on TRIPs in light of the entry into force of the Lisbon Treaty. In Conditional Access Services (Case

  2. Research on vitrification technology to immobilize radioactive sludge generated from Fukushima Daiichi power plant. Enhanced glass medium

    International Nuclear Information System (INIS)

    Amamoto, Ippei; Kobayashi, Hidekazu; Kitamura, Naoto; Takebe, Hiromichi; Mitamura, Naoki; Tsuzuki, Tatsuya; Fukayama, Daigen; Nagano, Yuichi; Jantzen, Tatjana; Hack, Klaus

    2016-01-01

    The search for an enhanced glass medium to immobilize the sludge at the Fukushima Daiichi Nuclear Power Plant is our main purpose. The iron phosphate glass (IPG) is a potential candidate as we set about assessing it by means of theoretical and experimental investigation. Based on the results of this study, the IPG showed favorable characteristics as a vitrification medium for the sludge. (author)

  3. Addenda to the second update of the Fukushima Daiichi Nuclear Power Station accident. June 1 to August 31, 2011

    International Nuclear Information System (INIS)

    2011-01-01

    These addenda provide the figures and tables for helping readers to understand the article titled 'the second update of the Fukushima Daiichi Nuclear Power Station (NPS) accident' by SHIBUTANI Yu. These figures and tables are mainly referred from 'Additional Report of the Japanese Government to the IAEA - The Accident at the Tokyo Electric Power Company Inc. (TEPCO) Fukushima Daiichi NPS - September 2011, Nuclear Emergency Response Headquarters Government of Japan' and the website of Prime Minster of Japan and His Cabinet, Nuclear and Industrial Safety Agency (NISA), Ministry of Education, Culture, Sports, Science and Technology (MEXT), TEPCO and Japan Atomic Industrial Forum Inc. (JAIF). The contents of this addenda cover (1) summary of 28 learned lessons, (2) status of each unit of Fukushima Daiichi NPS, (3) alternative core cooling system, (4) spent fuel pool alternative cooling system, (5) outline of waste water storage and treatment system, (6) prevention of environmental release of radioactive materials and monitoring, (7) environmental effect caused by the accident, and (8) influence of Fukushima Daiichi accident on electricity supply in Japan. (author)

  4. No mixed feelings : The post-Lisbon Common Commercial Policy in Daiichi Sankyo and Commission v. Council (Conditional Access Convention)

    NARCIS (Netherlands)

    Larik, J.E.

    2015-01-01

    Double case note on the scope of the EU's Common Commercial Policy and the future of "mixed agreements" based on the two ECJ Grand Chamber Judgements Case C-414/11, Daiichi Sankyo Co. Ltd and Sanofi-Aventis Deutschland GmbH v. DEMO Anonimos Viomichaniki kai Emporiki Etairia Farmakon, Judgment of the

  5. The second update of the Fukushima Daiichi Nuclear Station accident. June 1 through August 31, 2011

    International Nuclear Information System (INIS)

    Shibutani, Yu

    2011-01-01

    The Fukushima Daiichi accident occurred on March 11, 2011. The Japanese government and Tokyo Electric Power Company (TEPCO) encountered great deal of difficulties to stabilize the nuclear power reactor. Although the maximum radiation level has decreased, it still accounts for one-fifth of the level detected as of end of August 2011. There are currently growing concerns regarding the complexities of nuclear energy that are faced by the society of Japan. Owing to the occurrence of the Fukushima Daiichi accident, the firm belief on absolute safety of Japan's nuclear power plants has suddenly collapsed. Over the past decades, people tended to trust the government and electric power companies, which assured the safety and ensured about the necessity of nuclear power. However the recent disaster that took place in Fukushima has triggered public anger and distrusts that lead to negative campaigns against nuclear energy, in addition to oppositions against the government and nuclear power companies. The harsh public criticism has forced the government to separate the Nuclear and Industrial Safety Agency (NISA) from affiliation with the Ministry of Economy, Trade and Industry (METI). This action was taken since NISA had expressed contradictions with METI, which is the promoting agency for nuclear energy, The nation-wide opinion poll and surveys undertaken by Asahi Shimbun, a leading Japanese daily newspaper, has announced that 74% of respondents supported the policy to phase-out all nuclear power plants with the final goal to completely end the operation of nuclear plants. A mere 14% of the respondents disagree. There are approximately 100,000 or more residents that evacuated from the dangerous Fukushima Daiichi zone and were suffering from immediate threats such as radiation exposure, health problems, sanitary contamination, products shipment ban, business slump, groundless rumors, etc. These conditions have severely weakened their capability to completely recover and

  6. Outline of the Fukushima Daiichi Accident. Lessons Learned and Safety Enhancements

    Science.gov (United States)

    Hirano, Masashi

    2017-09-01

    Abstract. On March 11, 2011, an earthquake and subsequent tsunamis off the Pacific coastline of Japan's Tohoku region caused widespread devastation in Japan. As of June 10, 2016, it is reported that a total of 15,894 people lost their lives and 2,558 people are still unaccounted for. In Fukushima Prefecture, approximately 100,000 people are still obliged to live away from their homes due to the earthquake and tsunami as well as the Fukushima Daiichi accident. On the day, the earthquake and tsunami caused severe damages to the Tokyo Electric Power Company (TEPCO)'s Fukushima Daiichi Nuclear Power Station (NPS). All the units in operation, namely Units 1 to 3, were automatically shut down on seismic reactor protection system trips but the earthquake led to the loss of all off-site electrical power supplies to that site. The subsequent tsunami inundated the site up to 4 to 5 m above its ground level and caused, in the end, the loss of core cooling function in Units 1 to 3, resulting in severe core damages and containment vessel failures in these three units. Hydrogen was released from the containment vessels, leading to explosions in the reactor buildings of Units 1, 3 and 4. Radioactive materials were released to the atmosphere and were deposited on the land and in the ocean. One of the most important lessons learned is an importance to prevent such large scale common cause failures due to extreme natural events. This leads to a conclusion that application of the defense-in-depth philosophy be enhanced because the defense-in-depth philosophy has been and continues to be an effective way to account for uncertainties associated with risks. From the human and organizational viewpoints, the final report from the Investigation Committee of the Government pointed out so-called "safety myth" that existed among nuclear operators including TEPCO as well as the government, that serious severe accidents could never occur in nuclear power plants in Japan. After the accident, the

  7. Fiscal 1998 research report. Construction model project of the human sensory database; 1998 nendo ningen kankaku database kochiku model jigyo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    This report summarizes the fiscal 1998 research result on construction of the human sensory database. The human sensory database for evaluating working environment was constructed on the basis of the measurement result on human sensory data (stress and fatigue) of 400 examinees at fields (transport field, control room and office) and in a laboratory. By using the newly developed standard measurement protocol for evaluating summer clothing (shirt, slacks and underwear), the database composed of the evaluation experiment results and the comparative experiment results on human physiological and sensory data of aged and young people was constructed. The database is featured by easy retrieval of various information concerned corresponding to requirements of tasks and use purposes. For evaluating the mass data with large time variation read corresponding to use purposes for every scene, the data detection support technique was adopted paying attention to physical and psychological variable phases, and mind and body events. A meaning of reaction and a hint for necessary measures are showed for every phase and event. (NEDO)

  8. Report on results of R and D of coal liquefaction technology in fiscal 1981; 1981 nendo sekitan ekika gijutsu no kenkyu kaihatsu seika setsumeisho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-03-01

    This paper explains the results of development of coal liquefaction technology under the Sunshine Project in fiscal 1981. In connection with solvent extraction and liquefaction, an 1 t/day experimental plant was completed for bituminous coals and operated continuously for 153 hours. An examination also started for the development of a 250 t/day pilot plant. As the element studies, R and D is in progress on the solvent extraction and liquefaction process, solid-liquid separation, secondary hydrogenation, and plant materials. In brown coals, the construction work of a 50 t/day pilot plant started for the purpose of establishing liquefaction technology for brown coal in Victoria State, Australia, with a part of the equipment manufactured. As the element studies, research was conducted on primary hydrogenation, deliming, secondary hydrogenation, dehydration and catalysts. In solvolysis liquefaction, a short-time concluding liquefaction reaction was continuously performed by a plant of 1 t/day scale. In direct hydro-liquefaction, a 2.4 t/day experimental plant was constructed, with the element studies conducted successively. In other words, researches were carried out by the bench scale plant on liquefaction, solid-liquid separation, iron-based catalysts, catalyst and reutilization, motive force recovery system by hydrohoist, and effect of preheating and deaeration. (NEDO)

  9. Summary of results of research on magneto hydrodynamic (MHD) generation in fiscal 1977; 1977 nendo denji ryutai (MHD) hatsuden kenkyu seika gaiyo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-08-01

    This is the summary of results of the research on MHD generation in fiscal 1977. In the experimental studies on MHD generators using a copper/iron magnet, the combustor of the Mark 7 generator was manufactured and installed, as were the supply systems of fuel, oxygen, air, seed, sulfur dioxide, cooling water, etc., respectively of the Mark 7 generator based on the design implemented in the previous year. In the studies on element technologies, various tests were performed, namely, immersion tests by K{sub 2}SO{sub 4} solution for electrode materials; tests of corrosion resistance, thermal shock resistance, and compatibility with electrode materials, for insulation wall materials; and material selection tests, based on a dynamic state, for consumption quantity and distribution, surface temperature and heat flow, measurement of arc spot generating critical current and electrode lowering voltage, etc.. In the research on the MHD generation system, examinations were carried out on the position of MHD generation as a total system, as well as on a system of a practical plant, MHD generation for peak load, superconducting magnet, etc. In addition, examinations were also conducted on the Mark 7 calculation, Mark 8 plan, surveys on overseas trend, etc. (NEDO)

  10. Fiscal 1993 report on technological results. R and D on micromachine technology; 1993 nendo micro machine gijutsu no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    Researches on basic element technology of micromachines are conducted with the view of establishing a mechanical system constituted of minute functional elements that perform autonomous operations in a narrow small part of complicated equipment in a power station for example or in a living body. The areas of activity are 1. research on micro actuators and 2. research on basic technology of micromachine; 1 is classified into researches of (1) shape-memory actuator, (2) bending and stretching type actuator, and (3) integrated micro actuator, while 2 is classified into researches of (1) total system for medical diagnosis, (2) micro tactile sensing technology and laser applied diagnosis/treatment technology, and (3) blood pressure/blood circulation sensing technology. In 1-(1), a chemo-mechanical actuator was studied using a shape memory alloy (SMA) and a high polymer gel, and in 1-(2), an SMA and bimetal were employed as a source of the driving force. Further, examination was also made on a fluid driving type actuator. (NEDO)

  11. FY 2000 report on the results of the R and D of fundamental technologies for semi conductivity applications; 2000 nendo chodendo oyo kiban gijutsu kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-05-01

    In relation to the project on the R and D of fundamental technologies for semi conductivity applications, the FY 2000 results were summed up. As to the study of the high temperature superconductivity mechanism, it was found out that a theoretical model of the strong scattering limit in d-wave superconductor can be used for the breaking of superconductivity due to Zn impurities. Concerning the study of the critical current mechanism, the elucidation was proceeded with of the magnetic flux pinning and grain-boundary conduction mechanism. Relating to the development of element technology of bulks with great electromagnetic force, the mechanical strength of superconducting bulk materials was raised to 100MPa or more by the epoxy resin impregnation method. As to the development of the basic technology for fabrication of high next-generation current conductors, the expansion was confirmed of conditions for growing single grains in the zone-melt process for very fine filaments. About the development of technology of single crystal substrates, in the development of the pseudo single crystalline film growth process by LPE method, a yield ratio of high quality crystal of 63% was achieved. Concerning the development of technology of thin film/multi-layer, the area of uniform composition/thickness of NdBa{sub 2}Cu{sub 3}O{sub 7-x} MOCVD films was enlarged up to 20mm square. (NEDO)

  12. Research and development on fusion zones in fiscal 1999. Third volume. Biomolecular mechanism and design; 1999 nendo yugo ryoiki kenkyu kaihatsu seika hokokusho. 3. Biomolecular mechanism and design

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    It was intended to elucidate the structures of living organisms having excellent functions and the principles of these functions, and to create cells, structural bodies and molecular mechanisms that substitute these functions outside the bodies of the living organisms. Therefore, research and development has been performed on the fundamental technologies, whose achievements are compiled. In the research of creating cultured bones and cartilages, marrow cells and cartilage cells were cultured while providing physiological active materials and mechanical stimulation. Porous ceramics and porous biodegradating polymers coated with collagen were used as the substrate materials to have created artificial cartilages. In the research of structural change in a molecule motor, a low temperature electron microscope was used to make the structure visualized successfully for the first time. In the research of creating an artificial liver, the world's first cells like stem cells separated and refined from liver cells were cultured three dimensionally in a bio-reactor using special cultivation solution to have established the basic technology. In the research of libozyme, sensor function and high catalytic function were realized successfully in the cells by dimerizing libozymes. (NEDO)

  13. Fiscal 1974 Sunshine Project result report. Research on solar energy utilization systems (solar heat power generation); 1974 nendo taiyo energy riyo system chosa kenkyu seika hokokusho. Taiyonetsu hatsuden

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-03-01

    This report summarizes the fiscal 1974 research result on solar heat power generation. The following are promising as solar heat power plant sites in Japan: Large-scale sites such as the foot of volcanos, riverbed, railway site and road, medium-scale sites such as isolated island, saltpan site and industrial park, and small-scale sites such as factory site, factory roof floor, housing complex, warehouse and school. Based on the primary concept design of both curved reflector type and tower type 1,000kW class solar heat power plants, various requirements were clarified roughly. It was clarified that food, fiber and non-ferrous metal factories can cover 80-90% of their thermal energy requirements with high- temperature solar heat, while factories related to food and fiber can cover even nearly 100% of their electric power requirements with solar heat. Study was also made on specifications of a solar simulator as common use facility necessary for characteristic evaluation of equipment and materials for solar heat power generation systems. (NEDO)

  14. Fiscal 2000 report on results of R and D of welfare techno-system in Mitaka City; 2000 nendo walfare techno system kenkyu kaihatsu (Mitaka) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Studies were made for the purpose of probing effects of utilizing body sensory game machines for the functional recovery training and exercise of the elderly and handicapped, with the fiscal 2000 results reported. In the verification by existing game machines, a game center was made available free of charge, providing free experience for the elderly, with the image traced of the elderly for the game machines based on the record of the machines used, questionnaires and interviews. In addition, four body-sensory game machines that were supposed to be effective for the exercise of the joints were installed in a day care center for six months, with a verification test performed on the adaptability of the elderly to the speed and the like of the game machines. In the development of a game machine intended for the exercise of the lower extremities, researchers tackled the development of a game machine in which an entertainment/amusement nature was added to the exercise of the lower extremities. An experimental model was developed based on a principle providing a virtual reality as if the user were walking in a tourist area of scenic beauty by moving a scenery linked with a foot pedal type exercising pattern. (NEDO)

  15. Fiscal 1999 report on result of the model project for waste heat recovery in hot blast stove; 1999 nendo netsufuro hainetsu kaishu model jigyo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    For the purpose of curtailing energy consumption of the steel industry, a heavy energy consuming industry in China, a model project was carried out for waste heat recovery in a hot blast stove, with the fiscal 1999 results reported. In the process of this project, a heat exchanger for recovering heat is installed in the exhaust gas flue of a hot blast stove in ironworks, with sensible heat recovered through a heating medium. The heat exchanger for recovering heat and the preheating heat exchanger, which was installed in the main pipe for blast furnace gas and for combustion air, were connected by pressure piping, with the blast furnace gas and the combustion air preheated. In addition, a heating medium circulating pump for transporting the heating medium is installed, as are an expansion tank for absorbing expansion/contraction due to change in temperature, a heating medium storage tank for accepting the entire heating medium in the system for the maintenance of the equipment, and heating medium feeding pump, for example. This year, on the basis of the 'Agreement Annex', basic designs and detailed designs were performed for each equipment in the waste heat recovering equipment for the hot blast stove. Further, procurement and manufacturing were implemented for various component parts and devices of the waste heat recovering equipment. (NEDO)

  16. FY 1998 report on the R and D of micromachine technology. R and D of micromachine technology; 1998 nendo micromachine gijutsu no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    In the comprehensive investigational study of micromachine technology, the paper aims at clarifying the improvement of functional devices and the future development of micromachine technology for establishment of the technology needed to realize a micromachine system composing of small-functional elements for conducting diagnosis/cure/repair, movement and independent work in small portions in living organism, disaster site, etc. and a medical-use micromachine system to analyze/react on a trace of liquid. In this fiscal year, the following were carried out: 1) study of micromachine systems, 2) study of a medical-use micromachine system to analyze/react on a trace liquid, and 3) comprehensive investigational study. In 1), studies were made toward the minuteness and improvement of micro laser catheter and micro tactile sensor catheter as functional devices which become the main components of micro catheter for cerebrovascular diagnosis/therapy use and toward the minuteness and improvement of disaster relief use micromachine system. In 2), study was made of element technology of a micro-machine system having functions of sampling/analysis/reaction of a trace of liquid. (NEDO)

  17. FY 1998 annual report on the research and development of non-linear, opto-electronic materials; 1998 nendo hisenkei hikari denshi zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The final assessment of researches on non-linear, opto-electronic materials was conducted in FY 1988. These researches are evaluated as the world-level basic researches, high in potential of giving ripple effects on various areas. The R and D themes are organic, low-molecular-weight materials; technology for orientation-controlled crystal growth; conjugated polymer films; microcrystallite-doped glasses using vapor deposition and stuffing method; glass composite materials using sol-gel method and ultra-low melting point glass; nanoparticle-dispersed glasses using super-cooling technology; materials dispersed in organic compounds; organic superlattice formation; three-dimensionally superstructured materials; and comprehensive surveys and researches. The researches and surveys on the common basic techniques were recommissioned to Universities of Tokyo, Keio Gijuku, Nagoya, Tohoku and Hokkaido. These themes are analytical methods for non-linear optical characteristics; morphology-controlled crystal growth of nonlinear-optical organic materials and fundamental studies on all-optical devices; large enhancement of optical nonlinearity and its mechanism in nanocrystals embedded in matrices; improvement of organic materials for high performance; and ultrafast nonlinear optical processes and their application for controlling ultrafast optical pulses. (NEDO)

  18. Fiscal 1976 Sunshine Project result report. Research on solar energy utilization systems (total system); 1976 nendo taiyo energy riyo system chosa kenkyu seika hokokusho. Total system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-03-01

    For every solar energy utilization field, its background, feasibility, impact in practical use, and R and D policy in Japan were studied. Heating and hot water supply by solar energy are already practical because of less technical problems and reasonable profitability, and cooling is also practical as far as a technical viewpoint. At present, the technical level of solar heat power generation is in the stage of basic technology, however, in the future, development of economically reasonable systems will be demanded as well as establishment of its technology. The most difficult problem for realizing practical solar cell power generation systems is cost reduction. It is also another problem that a big demand of Si for solar cells further exceeds the current yield of Si in a semiconductor industry. A small-scale hybrid solar cell power generation system applicable to the roof of general residences is already feasible. Although a solar furnace is still poor in application to industrial fields, it is expected as the leading part for a future solar heat chemical industry. (NEDO)

  19. R and D on new energy technologies. Outlines of fiscal 1976 research results; Shin energy gijutsu kenkyu kaihatsu 1976 nendo kenkyu seika no gaiyo. Kenkyu kaihatsuhi kamihanki

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-07-01

    This report outlines the results of (1) 8 researches on solar energy technology, (2) 4 researches on hydrogen energy, and (3) 4 general researches. (1) includes the prototype measuring instrument of near IR solar direct radiation using an interference filter to measure solar spectral irradiance, the prototype small-scale solar heat power model system, selective absorption and transmission films as solar heat power generation materials, InP solar cell and new solar cell system configuration, micro-wave power transmission of solar energy, and the expansion turbine using low-boiling point coolant for space power generation. (2) includes the hydrogen energy system, high-temperature thermolysis of water at 1,000 degrees C, prototype zirconia single-crystals for new solid electrolyte fuel cells, and the large-capacity high- temperature solid electrolyte fuel cell power system. (3) includes the total new energy system, the prototype superconducting magnet for energy storage, study on mechanism of an anomalous absorption effect by irradiation of strong laser beam onto high-temperature high-density ionized gas, and low-temperature difference power generation in the ocean. (NEDO)

  20. Achievement report for fiscal 1998. Research and development of advanced functional materials designing platform; 1998 nendo kokino zairyo sekkei platform no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Stated in this paper are the reports of the working groups (WGs) for the above-named endeavor and the reports on the achievements of the universities to whom the jobs had been commissioned. WG1 carried out research and development related to the coarse-grained molecular dynamics method. WG2 dealt with mesoscale structures, which are quite larger than atoms, such the phase separated structure of polymer molecules and interfacial structures, worked for the construction of a general-purpose simulator system for reproducing/predicting their dynamic properties, and studied the properties of polymers by use of the said simulator system. WG3 worked on polymeric phenomena large in scale in terms of both space and time. Faculty of Engineering, Yamagata University, constructed a materials physical property database necessary in designing materials by simulation. Institute of Industrial Science, Tokyo University, studied the viscoelastic phase isolation at the quantitative level. Tokyo University's Faculty of Engineering-managed study teams investigated the nano-scale structures and properties of polymer materials. Faculty of Engineering, Tokyo Institute of Technology, performed research and development about the meso-scale behavior of multi-constituent polymers. (NEDO)

  1. Fiscal 1997 report on the results of the international standardization R and D. Robot control system; 1997 nendo seika hokokusho kokusai hyojun soseigata kenkyu kaihatsu. Robot seigyo system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    R and D of the robot control system was conducted in the following items: 1) integrated open control system, 2) remote control robot manipulation language, 3) human factor robot use built-in LAN system, 4) built-in actuator driver. In 1), there were some problems to be pointed out around the system, but the effectiveness was confirmed as system architecture of each verification item. In 2), development/design were made of RCML(R-Cube Manipulation Language) as a remote robot manipulation language, telecommunication protocol, and the experimental system, and the international standardization was targeted. In 3), the R and D was conducted of the realtime telecommunication protocol which clears the standards for the distributed control required for construction of human factor robot and the advanced realtime micro-controller, ULSI, which is the one that the protocol was made IC. In 4), an intelligent connector for built-in actuator was developed which enables saving of wiring in robot system and plug-in connection. 13 refs., 186 figs., 53 tabs.

  2. Fiscal 1998 'Plant Biotechnology in the 21st Century' workshop report; '21 seiki no shokubutsu biotechnology' workshop 1998 nendo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The workshop was opened with the opening remarks by Yamada (President of Nara Institute of Science and Technology (NIST)), the overview of plant biotechnology in the 21st century from academia by Shinmyo (Professor of NIST), and the overview of such technology from Ministry of International Trade and Industry by Katao (Chief of Chemical Industry Division). Lectures and discussions of various topics were conducted for 2 days as follows. The effectiveness of a genomic DNA array method for obtaining the genes for switching genes according to daytime, nighttime, drying, salt, high temperature and low temperature for every plant. Current transfer technology of large DNA fragments into plant cell nuclei and chloroplast. Biological evaluation of the physiological functions and complex stress tolerance capacity transformed by transferring complex stress tolerance genes and useful genes for productivity improvement and value addition. Discussion was also held on the importance of a basic research for biotechnology in the 21st century. (NEDO)

  3. Achievement report for fiscal 1998. Development of environmentally friendly universal controller; 1998 nendo kankyo taio universal controller no kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    Research and development was carried out for an 'environmentally friendly universal controller (UC)' which would be 'user-friendly and energy-saving' when used with electrical home appliances. An environmentally friendly UC is a remote controller which utilizes an infrared two-way communication function and becomes capable of dealing with any appliance upon downloading remote control information from the appliance involved. Studies were conducted for the development of controller hardware and software therefor and for the development of electrical home appliances to correspond to their specifications. In relation with energy conservation, studies centered about reduction in power consumption while on standby and unnecessary power consumption. As the result, an environmentally friendly UC protocol was newly developed and, based on the protocol, plural numbers of controllers, appliances, and network gateways were tentatively fabricated, and were examined for their function, behavior, and operational interchangeability. Systems aiming at reducing power consumption while on standby and unnecessary power consumption were built by way of experiment, and were checked for performance. It was then concluded that a reduction of several billion kWh might be achieved. (NEDO)

  4. Research and development on fusion zones in fiscal 1999. Third volume. Biomolecular mechanism and design; 1999 nendo yugo ryoiki kenkyu kaihatsu seika hokokusho. 3. Biomolecular mechanism and design

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    It was intended to elucidate the structures of living organisms having excellent functions and the principles of these functions, and to create cells, structural bodies and molecular mechanisms that substitute these functions outside the bodies of the living organisms. Therefore, research and development has been performed on the fundamental technologies, whose achievements are compiled. In the research of creating cultured bones and cartilages, marrow cells and cartilage cells were cultured while providing physiological active materials and mechanical stimulation. Porous ceramics and porous biodegradating polymers coated with collagen were used as the substrate materials to have created artificial cartilages. In the research of structural change in a molecule motor, a low temperature electron microscope was used to make the structure visualized successfully for the first time. In the research of creating an artificial liver, the world's first cells like stem cells separated and refined from liver cells were cultured three dimensionally in a bio-reactor using special cultivation solution to have established the basic technology. In the research of libozyme, sensor function and high catalytic function were realized successfully in the cells by dimerizing libozymes. (NEDO)

  5. Fiscal 2000 survey report on R and D results of advanced clean energy vehicle; 2000 nendo kokoritsu clean energy jidosha no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    With problems inherent to clean energy vehicles such as cruising distance, fuel supply and fuel consumption, ACEVs (advanced clean energy vehicles) are in demand featuring both low pollution and high efficiency compatibly. This paper explains the fiscal 2000 results of development. The target is, by using oil-alternative fuel, to reduce driving energy consumption and carbon dioxide emission to less than half and to control the life cycle cost (total of manufacturing cost, operating cost, fuel cost, etc.) to not more than twice as much as those of conventional vehicles. As ACEVs, an ANG (adsorbed natural gas) engine and flywheel battery mounted passenger car was selected, as were a CNG ceramics engine and capacitor mounted truck, CNG engine and lithium-ion battery mounted truck, LNG engine and capacitor mounted bus, and a DME engine and capacitor mounted bus. All are hybrid systems with an energy saving device. In the research of synthetic fuels, the results of the studies were summarized including the effect of various synthetic light oils on engine performance, fuel characteristics, effect of PM grain size and the optimum properties. (NEDO)

  6. FY 1998 report on the results of the project on the next generation structure housing development; 1998 nendo jisedai kozo jutaku kaihatsu jigyo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The purpose of this project is to develop/verify technology to design/construct a structural body of multiple dwelling house which is highly durable and usable at maximum of the limited space with no projections of poles/beams, and is also to develop/verify a composite system of a structure and each house in which residential space can freely be changed horizontally/vertically in response to the leveling-up of living and changes in life style. The following were conducted: construction of an experimental house group with next generation structure; development of technology of effective space utilization/high durability body construction; development of technology of structural analysis/design systematization of antiseismic/damping system; development of commercialization of technology to heighten frame durability, development of technology to heighten durability of finishing materials of a body; development of low cost construction technology; development of technology of interface between a body and each house; verification of housing performance using a next generation body system; generalization of next generation frame system/house system. To reflect the results of the research quickly, the details of the research are systematized, and a draft is worked out of a guide for constructing the next generation frame system/house system which were arranged between the current architecture related laws and business as a general multiple dwelling house. (NEDO)

  7. Achievement report for fiscal 2000 on development of technology to evaluate reliability of petroleum refining facilities; 2000 nendo sekiyu seisei setsubi shinraisei hyoka nado gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    This paper reports the achievements in fiscal 2000 in development of a technology to evaluate reliability of petroleum refining facilities. The development efforts were made mainly on analyses by simulation and neural net (NN) that utilize computers. In the high-temperature system facilities, the creep damage generation is governed by different factors including impurities. The evaluation on joint life requires simultaneous use of low temperature zone long-time test. Verification was made on application of non-destructive inspection, such as use of ultrasonic waves in the accelerated creep zone. Defect detecting capability was identified when an ultrasonic wave flaw detection model is used for buried piping. In the pulse eddy current flaw detection, a coil most superb in totality was selected by means of simulation, by which corrosion and wall thickness of piping and devices were detected from outside the sheathing materials. Development was made on a technology to diagnose and evaluate corrosion of tank in operation by using the AE method. The remaining life of transformers is determined by how seriously the coil insulating paper has been deteriorated, and furfural in the oil was found effective for the parameters. Particularly, application of the NN was revealed to be effective in estimating electric motor deterioration. A high-temperature sulfide corrosion rate estimating model was developed from the operation and measurement data of the facilities by applying the NN and TCBM. (NEDO)

  8. Achievement report for fiscal 1990 on research and development of photoreactive materials; 1990 nendo hikari hanno zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-03-01

    Activities were performed with an objective to establish fundamental technologies related to photoreactive materials capable of ultra-high density and high resolution indication by controlling structures and assemblies of molecules by using light. The activities were taken in the four fields of elucidation of photoreactive mechanisms and fundamental properties, development of the materials, material processing and constituting technologies, and evaluation technologies. Specifically speaking, the activities were developed on the multiplexing technology applicable to ultra-high density recording, sensitivity responsiveness, and material stability in photochromic materials and photochemical hole burning (PHB) materials. For the photochromic materials, development was performed on photochromic materials to form associations, and on a thin film forming technology by means of the organic molecular beam epitaxial process. For the PHB materials, research was implemented on use of the materials at elevated temperatures, development was made on quinone-based materials, research on enhancement of multiplexity, development on porphyrine-based materials, and research on the organizing technology. In the research of the use at elevated temperatures, development was progressed on a material that can retain under the liquefied nitrogen temperature the status of wavelength multiplexed recording that has been formed under the liquefied helium temperature. (NEDO)

  9. Survey report for fiscal 1998. Achievement report on research and development of direct methanol fuel cell; 1998 nendo direct methanol nenryo denchi no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-01

    Research and development has been performed on a direct methanol fuel cell (DMFC) to generate electric power through direct chemical reaction of methanol not being given modification as a fuel cell to be used for automotive engines. This paper summarizes the achievements in fiscal 1998. In the research of the membranes to conduct ions for the DMFC, an ion conduction membrane which introduces POSS group as the methanol eliminating functional group was prepared to achieve enhancement in tensile strength, heat resistance, and ion conductivity. In the power generation characteristics of the DMFC, verification was given on power generation performance with as high main power density as 0.1 W/cm{sup 2} by using the available electrolytic membranes and electrode catalysts. The characteristics showed effectiveness of the DMFC as the electric power supply source. In addition, fundamental findings were obtained on factors affecting the power generation characteristics of the DMFC as a result of generating power under different conditions. Research and development was given also on the water-methanol-ion exchange polymeric membrane, ion exchange membranes provided with lipophilic and water repellent electrolyte, solid polymeric membranes having high proton conductivity and low methanol permeability, and a new micro-porous filling type polymeric membrane. (NEDO)

  10. Fiscal 1997 report on technological results. R and D on micromachine technology; 1997 nendo micromachine gijutsu no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    Researches on basic element technology of micromachines are conducted that operate autonomously in a narrow small part in a complicated apparatus or in vivo. The areas of activity are 1. research on micromachine systems and 2. comprehensive investigation and research. In 1, (1) a micro catheter and (2) a micro tactile sensor catheter were studied while, in 2, basic technology and technological problems, particularly those problems concerning sophistication in the medical field were examined and studied. Further, in (1), with the purpose of developing a micro laser catheter for diagnosis/treatment, researches were implemented on the technology of integrating micro laser and an optical fiber which were components of the catheter and on the fabrication of the fine diameter of a micro catheter as well as on the characteristical improvement of the base body on which minute elements were mounted. In (2), characteristical improvement and sophistication were carried out for a high sensitivity contact pressure sensor and a diagnostic tactile sensor, which are mounted on a catheter having a positive bulge control mechanism for insertion into body cavity, with a sensor probe manufactured experimentally. (NEDO)

  11. 1998 Annual Study Report. New industry supporting type international standard development program (Comprehensive survey); 1998 nendo seika hokokusho. Shinki sangyo shiengata kokusai hyojun kaihatsu jigyo (sogo chosa)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Summarized herein are results of the survey on a total of 13 themes for international standardization. These themes are for standardization of (1) color control, (2) securing interoperability between optical disk systems, (3) digital image processing for home digital electronic appliances, (4) securing interconnectability between home electronic information appliances, (5) production process systems, (6) testing and evaluation methods for fine ceramic materials for communications, (7) evaluation methods for high-temperature properties of new glass melts, (8) corrosion testing and evaluation methods for surface-treated steel plates, (9) testing and evaluation methods for high-purity titanium, (10) testing and evaluation methods for plastic optical fibers, (11) evaluation methods for high-strength, large-size steel pipe characteristics for superhigh-pressure natural gas pipelines, (12) methods for measuring mileage of hybrid electric vehicles, and (13) methods for determining recycle ratios of automobile components. This comprehensive survey also includes overseas trends for the standardization, establishment/expansion of the international standardization processes, and standardization for determining recycle ratios of home electric appliances. (NEDO)

  12. FY 1999 report on the results of the investigational study of dioxin emission mechanism/control; 1999 nendo dioxin hassei kiko yokusei chosa kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    For the purpose of promoting the utilization of energy from waste, studies were conducted on the dioxin emission mechanism and non-Br base fire retardant materials which emit no Br base dioxin, and the FY 1999 results were summarized. In the study, using a small-fluidized bed experimental incinerator, survey was made of effects of organic/inorganic chlorine included in solid general waste on the formation/discharge of dioxins. As a result of the experiment, it was found out that organic chlorine compounds discharge more dioxins than inorganic ones, and that the combustion method in which rapid formation of volatile matter in furnace is controlled to realize the homogeneous mixed state is important for control of dioxins. In the study of non-Br base fire retardant materials, a preliminary experiment was conducted on new fire retardant materials added with inorganic carrier, metal complex, etc. to make the confirmation of fire retardation by liquid phase reaction of polymer in combustion conditions and the study of fire retardation by separating liquid phase reaction, pyrolysis reaction, and gaseous phase reaction. Further, simulation of the combustion of polymer materials was carried out. (NEDO)

  13. FY 2000 report on the results of the development of the next generation chemical process technology; 2000 nendo jisedai kagaku process gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    The R and D were conducted on the next generation chemical process by which no energy losses are produced and the amount of the waste is made extremely small by the new catalytic reaction, the reaction using next generation separation/reaction membrane, etc., and the FY 2000 results were summed up. As to the development of the selective oxidation technology of saturated hydrocarbon, the basic knowledge/information were obtained on the following: construction of the catalytic principle toward the highly selective catalytic partial oxidation, elucidation of the reaction mechanism in alkane oxidation and design of the high functional catalyst, functional design in butane oxidation, characterization of the alkane oxidation catalyst and the application to the catalytic development, synthesis of the alkane selective oxidation catalyst, etc. Relating to the development of the process technology using the new reaction mechanism, a target value of equilibrium conversion of 10% or more was achieved using membrane reactor in the dehydrogenation of ethyl benzene. Further, as to the high performance selective membrane and low temperature active catalyst that are indispensable to the element technology, the continuous study was made, and at the same time themes in this study were arranged. (NEDO)

  14. Japan`s Sunshine Project. 1991 annual summary of coal liquefaction and gasification; 1991 nendo sunshine keikaku seika hokokusho gaiyoshu. Sekitan no ekika gas ka

    Energy Technology Data Exchange (ETDEWEB)

    1992-07-01

    Out of the research and development on the 1991 Sunshine Project, the results of coal liquefaction/gasification are reported. The basic research of coal liquefaction/gasification is conducted. The research plan for a 150 ton/day scale pilot plant (PP) is worked out for the development of bituminous coal liquefaction technology by NEDOL process. Data of PSU (Process Support Units) operation, especially, are studied. Concerning the data obtained through dismantling of the 50 ton/day PP in Australia which uses Australian Victoria coal due to completion of its operation and also obtained from its support research, they are reflected in the design of a demonstration plant, and the results are arranged for study. Research and development on refining technology of coal-derived liquid such as Illinois coal liquid and on application technology of its products are made. For the development of coal-use hydrogen production technology, conducted is the research of a high temperature gasification PP by entrained flow bed process which is the core of the coal gasification technology. Elementary study with a 2 ton/day furnace is made for the development of the entrained flow bed coal gasification combined cycle power generation system. Also conducted are PP construction, adjusting operation and the overall research operation.

  15. FY 1999 achievement report on the R and D of welfare techno-systems (Kyoto); 1999 nendo welfare techno system kenkyu kaihatsu (Kyoto) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The R and D were carried out of various kinds of physically functional substitution equipment which supplements the worsened functional ability of the aged/handicapped. In the research on various prototypes of physically functional substitution equipment, experiments on the use were conducted using Japanese speech recognition devices/programs which are standard products commercially available, so that the aged/handicapped can operate equipment (various devices such as home electric appliances) by speech (words). Further, the specifications were studied for technology to use the Japanese speech recognition technique for physically substitution functions. In the R and D of information infrastructure and various kinds of physically functional substitution equipment, the specifications were established for technology to operate lighting equipment, heater and TV by the Japanese speech, and the experiment was made using the prototype manufactured. As a result, the power source operation by speech of TV/lighting desk lump/electric stove has been finished almost certainly. Further study is needed such as TV channel selection by remote control. The investigation was made of the aid needs for the handicapped. (NEDO)

  16. Fiscal 2000 achievement report. Research and development of low-pollution brown coal utilization technology; 2000 nendo seika hokokusho. Kattan no teikogai riyo gijutsu no kenkyu kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Studies were made for developing low-pollution easy-to-operate industrial furnaces for use in small and medium size plants in Indonesia. In this fiscal year, two kinds were selected out of Indonesia yielded brown coals, which were then subjected to test combustion in a bench scale fluidized bed combustor for examination for their combustion characteristics and environmental impact generating characteristics. The nitrogen oxides from the brown coals were found to mark approximately 100 ppm at an excess air ratio of 1.4, which was higher than in the case of bituminous coal. The NOx concentration level was found to be lower in the circulation fluidized bed boiler than in the spreader stoker fired boiler. Combustion efficiency exceeding 98% was achieved. A survey was conducted of brown coal users in various industrial fields in Indonesia. It was then concluded that the tested method not be recommended for use in small businesses in the textile industry because there would be no economic profit or improved efficiency for them but that it would be feasible in the plantation industry where the fluidized bed combustion/heat exchanger aided indirect process and the use of electrical dust precipitators would protect products from contamination. (NEDO)

  17. Fiscal 2000 report on results of R and D of welfare techno-system in Takaoka City; 2000 nendo welfare techno system kenkyu kaihatsu (Takaoka) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    R and D was conducted on a 'system for monitoring living situation of elderly people' for the purpose of supporting the elderly living alone, with the fiscal 2000 results reported. In the development of a knowledge engineering system, a system was developed estimating the present position of an elderly person in his home or calculating his daily living activities, by analyzing data measured by infrared sensors, and thereby automatically inferring his behavior or health condition. In the research for practicability of the system, infrared sensors and sensors for detecting opening/closing of a door were improved, which included improvement by using telephone lines for example. In the demonstrative experiment, data were obtained which seemed to show a change for the worse of a disability condition due to senile dementia, or else, which appeared to be an inability to move occurring finally as a result of gradual deterioration of health. Another data measured disclosed that elderly people, unlike a normal life pattern, were living in a state with night and day reversed. From these results, the system can safely be said to have a function for monitoring the lives of the elderly people in point of their mind and body. (NEDO)

  18. Fiscal 1996 report on technological results. R and D on micromachine technology; 1996 nendo micromachine gijutsu no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    Researches on basic element technology of micromachines are conducted that operate autonomously in a narrow small part in a complicated apparatus or in vivo. The areas of activity are (1) research on micromachine systems, (2) a subminiature liquid synthesizing system, and (3) comprehensive investigation and research. In (1), the researches were carried out on the miniaturization and functional combination of a micro laser catheter and a micro tactile sensor catheter, which are the primary components of a coeliac diagnostic and therapeutic system, a 'micro catheter for cerebral blood vessel/treatment', as a micromachine system in the medical field. In (2), R and D was conducted on a system element technology assuming it contributed to a subminiature liquid synthesizing system capable of preparing various liquids including pharmaceuticals accurately with a trace amount. In (3), examination was made on the application area of a micromachine system with priority given to a medical field and also on technological subjects to be tapped, as well as on the contents of (2), with a device installed for evaluating the operating characteristic of a distribution type fluid actuator as needed for the development. (NEDO)

  19. Summary of FY 1980 results of Sunshine Project. Development of coal liquefaction techniques; 1980 nendo sekitan ekika gijutsu no kaihatsu seika hokokusho. Sunshine keikaku itaku kenkyu kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-03-01

    This report summarizes the results of the 3 R and D themes for coal liquefaction techniques, pursued by the Sunshine Project; (1) development of solvent extraction type liquefaction plant, and brown coal liquefaction technique R and D demonstration surveys, (2) development of solvolysis type liquefaction plant, and (3) development of direct hydrogenation type liquefaction plant. For the theme (1), the 1 T/D test plant, solid/liquid separator and small-size continuous settlement separator are constructed, and partly completed. The elementary studies include solvent extraction type liquefaction process, materials for coal liquefaction plant and solid/liquid separation. Australia's Victoria brown coal and Chinese coal are studied to clarify the possible problems involved in liquefaction of these coal species for commercialization of the liquefaction techniques in the early stage. The elementary techniques studied include dehydration of brown coal, milling at high temperature in oil, de-ashing, and secondary and primary hydrogenation. For the theme (2), the 1 T/D plant is inspected and maintained to clarify the problems involved in the continuous operation, revamped and repaired as necessary, given preventive maintenance, and tested for operability confirmation. The elementary studies include solvolysis type liquefaction process, scale-up, hydrogenation plant for solvolysis pitch. For the item (3), the 2.4 T/D test plant is constructed, and the elementary studies are conducted, for, e.g., liquefaction reactions in the presence of an iron-based catalyst. (NEDO)

  20. Fiscal 1975 Sunshine Project. Technology assessment on coal gasification and liquefaction; 1975 nendo sekitan no gas ka ekika gijutsu no technology assessment seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-03-31

    This research was intended to find the desirable direction of technological development, by discussing the effects of coal gasification/liquefaction technologies from every angle, for the purpose coping with the social demand for steadily and continuously obtaining clean energy. This year, the examination was conducted not only on the energy conversion technologies of coal gasification/liquefaction, but also on the impact generating from the entire supply system of coal energy from coal mine development to mining, transportation, storage and conversion to secondary energy. For this purpose, while the outline was grasped of coal resources in the world as well as each technology for the mining, transportation, storage, electric power generation by gasification, and high calorie gasification, a case study was made on the assumption that electric power generation and high calorie gasification were conducted by importing 1,000 tons of coal from overseas, extracting the impact on the basis of this case study. In addition, examination was made on the position of coal energy in the energy supply of the future, with an impact investigated on condition that about 300 million tons were imported equivalent to roughly 16% of energy supply in the year 2000 or about. (NEDO)

  1. Achievement report for fiscal 1998 on Welfare Technosystem Oita research and development; 1998 nendo Walfare technosystem kenkyu kaihatsu (Oita) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Before a welfare facility is introduced into a home, studies should be sufficiently conducted about the circumstances of daily life, not only of the aged user but also of the family members who take care of the aged user. In the development of handrails, it is found that plastic foam containing wood flour presents the feel of wood, easy to bend when heated. Materials are investigated for flexural strength, and ABS (acrylonitrile butadiene styrene) is chosen as the suitable material. As for devices to assist toileting, a system is developed under which the patient's legs are raised. Since there are arguments for and against the operation itself of mechanically raising a patient's legs, however, efforts will continue to develop much advanced systems. In the study of walk and transfer behavior, a toilet frame mockup is designed and manufactured, which is for collecting data. In an preliminary experiment, tests are conducted about a transfer from a chair to another and, assuming a physically handicapped patient, a transfer from a wheelchair. The data thus collected are to be subjected to analysis and image processing by the use of measuring sensors. Development is described of interfaces, for use in devices to serve as information mediums, which consider the cognition characteristics of the aged people. As for the development of devices for communication, environmental control, and display, their basic operation and feasibility are discussed. Actualities of costumes for physically handicapped people are also investigated, and development is carried out as required. (NEDO)

  2. FY 2000 report on the results of the R and D of solid oxide fuel cells (SOFC); 2000 nendo kotai denkaishitsugata nenryo denchi no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-05-01

    Development of fuel cell power generation technology and R and D of solid oxide fuel cells were carried out, and reports of the FY 2000 results of companies were summed up. As to the R and D of the cell module, the R and D on the wet type cylinder module were made jointly by Toto Ltd., Kyushu Electric Power Co. and Nippon Steel Corp. As to the R and D of materials/basic technology, the following were conducted: evaluation of reliability of the cell module (evaluation of thermal cycle characteristics, etc.) by Chubu Electric Power Co., evaluation of reliability of the cell module (cell characteristics/stress evaluation) by Tokyo Gas Co. Ltd., cost reduction of cell materials (evaluation of chemical characteristics) by Central Research Institute of Electric Power Industry, and cost reduction of cell materials (evaluation of mechanical/thermal characteristics) by Japan Fine Ceramics Center. Concerning the system study, study of the system (adaptation fields of the small system and the optimization) was conducted by Nippon Steel Corp. (NEDO)

  3. Preliminary reports on fiscal 2000 results of project for subsidizing international joint research; 2000 nendo kokusai kyodo kenkyu josei jigyo seika hokoku kai yokoshu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    This paper presents preliminary reports on fiscal 2000 results of project for subsidizing international joint research sponsored by NEDO. For international joint research teams doing excellent studies, their research expenses are subsidized, thereby promoting international research exchange, enhancing international level of industrial technology and contributing to the formation of basis for innovative industrial technology. The projects relating to the global environmental field are implemented jointly with RITE. The contents of the report to be published are, in the global environmental field (practicability study), development of oil substitute resources, reproducible resources, and technologies for producing polymeric and plastic materials benign to the earth by microorganism using carbon dioxide. In the substance/material field, the contents of the report are innovative production and device application of tunable photonic crystals using electronic penetration network; development of new synthesis process of innovative nitride, creation and theoretical calculation of electromagnetic function; studies on quantum transportation in superconductor and semiconductor bonding structures; and studies on quantum liquid and solid, and application to materials science and technology. (NEDO)

  4. FY 1993-1999 report on all the results of the development of high performance industrial furnace; Koseino kogyoro no kaihatsu sogo seika hokokusho (1993 - 1999 nendo)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    Since an phenomenon was found out that NOx emission, which was thought to be increased, will be decreased by burning the high temperature preheated air jetting it at high speed (high temperature air combustion) in industrial furnace, there appeared a possibility of technical breakthrough for achieving the heightening of energy utilization efficiency and NOx reduction by exhaust heat recovery at the same time. This project aims at conducting full-scale experiments based on the basement technology including the theoretical elucidation of the combustion mechanism and high temperature air combustion by using various experimental facilities. Further, making full use of the most up-to-date analysis methods and constructing general-purpose database, the development is also aimed at of high performance industrial furnaces such as various heating furnace, heat treat furnace and melting furnace, with the assumption of prompt commercialization of the results of the development. As a result, targets were achieved such as energy saving of 30% or more, downsizing of 20% and a remarkable NOx reduction. Core technologies of this project are in-system limit heat recovery technology, high temperature air combustion technology, temperature field control technology (furnace temperature leveling technology) and high exergy heat transfer technology (furnace temperature heightening technology). (NEDO)

  5. Fiscal 1998 research achievement report. Development of key technology for high-efficiency semiconductor manufacturing process; 1998 nendo kokoritsu handotai seizo process kiban gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-01

    In the development of large-aperture/high-density plasma technology, research and development was carried out for balanced electron drift plasma technologies for uniform control of plasma density and the like, such as an excited plasma source and plasma drift to enable wide-range plasma generation in a chamber. In the development of high-efficiency exposure technology, studies were made for stable generation and control of short wavelength excimer laser and for higher-speed large-aperture mask writing by use of an electron beam. In the development of higher-speed processing and energy-efficient technologies, research and development was conducted involving probe card technology for increasing the speed of semiconductor inspection, software-aided virtual tester technology, local energy-efficient cleaning technology in wafer processing and transportation, sheet-type flexible manufacturing system, and the like. (NEDO)

  6. Fiscal 2000 report on result of R and D of underground storage technology for carbon dioxide; 2000 nendo nisanka tanso chichu choryu gijutsu kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-06-01

    This paper presents the fiscal 2000 results of R and D of underground storage technology for carbon dioxide. As basic experiments, a measurement apparatus was manufactured for simulating the pressure and temperature conditions in aquifers to measure the rate at which CO{sub 2} is dissolved in water and the reactivity between CO{sub 2} and rocks, with the basic performance verified. Methods were investigated and classified that monitor environmental impact and safety. For the purpose of anticipating the long-term behaviors of CO{sub 2} sequestered underground, a simulator was developed, extracting, from investigation of the literature, natural phenomena required for the anticipation. As the system studies, examination was conducted for analysis of the energy balance of the underground storage technology, rational design (safety and economy) of an entire system ranging from source to storage point, investigation from social and economic perspectives, and estimation of the effect of suppressing global warming. In the injection experiment, Minami-Nagaoka natural gas field was selected as a prospective experiment site from the characteristics of the cap rock and aquifer. One injection well was drilled to a depth of 1,230 m, with investigations performed such as physical well-logging and core sampling. Existing data were utilized in the simulation study of CO{sub 2} behavior underground during the injection period. The information of the basic geophysical survey/exploratory well by the Japan National Oil Corporation was collected and compiled, with the preliminary geological study undertaken in the areas described. (NEDO)

  7. Report on achievements in fiscal 1999. Research and development of nanometer controlled optical disk system; 1999 nendo nanometer seigyo hikari disk system no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    Organizational strengthening is urged in industrial technological power in information recording area which is comparable with information communications being the main pillar of the innovation in the information technology in Japan. Extremely large expectations and heavy responsibilities are placed on the next generation optical memory technology, which is one of the strong points of Japan who plays a part in the above information recording area. The present project has been performing organizational research and development to achieve creation of new industries, with the following research themes as the main subjects: (1) nanometer controlled optical memory technology, (2) magnetic section responsive and three-dimensional optical memory, (3) ultra precision pit depicting technology, and (4) ultra precision pit measuring technology. The project is two years old this year, in which it was aimed to 'develop an optical memory technology with recording density of 100 Gb/in{sup 2} or more, transfer velocity of 100 Mbps or higher, and access time of 10 ms or less'. In order to achieve and establish the interim target set for fiscal 2000 among the above aims, intending 'trial fabrication of a disk having recording density of 40 to 50 Gb/in{sup 2}, the technical problem extraction and the specifications to realize a 100 Gb/in{sup 2} system', fiscal 1999 has performed researches on 'density and accuracy improvement on the prototype disk by improving the existing devices and introducing new devices'. This paper reports the developmental research theme No. 1. (NEDO)

  8. FY 1984 annual report on the research and development of automatic sewing systems. Total systems; 1984 nendo jido hosei system no kenkyu kaihatsu seika hokokusho. Total system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-03-01

    The automatic sewing system technique research association has been commissioned by the Agency of Industrial Science and Technology for (research and development of automatic sewing systems). This program covers R and D of the elementary techniques for total systems and sewing preparation/processing, sewing/assembling, cloth handling, and system management/control. This report describes the results of the R and D efforts for the total systems. For producing diversified products in small quantities, which is the object of this R and D program, the target is set to reduce processing time by at least 50% from the current level. The efforts to achieve this target by solving the problems involved therein are made from the side of developing FMS and FA procedures, and apparel side. The program for the former investigates the required functions of individual sub-systems that constitute the total system, to clarify the technical targets of the core elementary techniques for each sub-system. The program for the latter analyzes the sewing steps for producing diversified clothes types, specifications for automatic operation, integration, standardization and coding of the steps, and so on, based on the results of studies on basic apparel types. (NEDO)

  9. Achievement report for fiscal 1984 on Sunshine Program. Basic research on coal type and gasification characteristics; 1984 nendo tanshu to gas ka tokusei no kiso kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-03-01

    The study of pressurized fluidized gasification of coal chars started in fiscal 1975, and a 0.2t/d unit was in operation until fiscal 1979. Since fiscal 1980, a 1t/d unit has been in operation. In fiscal 1984, an entrained bed gasification furnace was constructed, capable of high-temperature gasification of various coals, and it is now undergoing a test operation. This report consists of pressurized gasification tests for coal char, the result of a study on the effect of coal type on the char gasification reaction rate, and the result of experiments on the treatment of coal liquefaction residue, all accomplished in the 1t/d gasification unit. For the investigation of the effect of coal type, chars of 13 types of coals are subjected to reaction tests in the carbon dioxide gas, and weight reduction rates and changes in residue surface areas are determined while reaction is under way. The results are analyzed and parameters are made clear that enable a quantitative assessment of the effect of coal type on gasification reaction rates. Pulverized grains and coal liquefaction residue are blended and gasified in the fluidized bed in the presence of oxygen and steam. As the result, a gas capable of 2,000kcal/Nm{sup 3} containing 30% hydrogen and 25% carbon monoxide is acquired, when catalyst grains in the residue are segregated. (NEDO)

  10. Fiscal 1997 report on the results of the international standardization R and D. Overall survey; 1997 nendo seika hokokusho kokusai hyojun soseigata kenkyu kaihatsu. Sogo chosa

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The paper summed up the results of the survey of tackling with the international standardization by enterprises and organizations involved in the standardization in the U.S., Europe and Japan, the results of the R and D on 20 themes for the international standardization, and the development toward the international standardization. As the R and D themes, the following were selected: the development of chemical method to analyze/evaluate metallic coatings of surface treated steel coating sheets, R and D of the basic evaluation method of functional composite particles, international standards for computer/manikins, basic technology of color image management, study on optimizing design/evaluation technology using quality engineering, study of the international standardization by economic evaluation of environmental impacts, R and D of the standardization of a method to test acceleration life of phosphorous acid fuel cells, development of a test method of halogen-free flame-retardant cables and a study of the cable standards, standard measuring methods of hormone effects of chemical substances, quantification of the sensory evaluation and international standardization in the paint field, experimental study on the international standardization for immunochemical measurement of chemical substances, etc. 24 figs., 16 tabs.

  11. Reports on 1974 result of Sunshine Project. Research on tar sand and oil shale; 1974 nendo tar sand oyobi oil shale ni kansuru chosa kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-04-04

    The purpose of this research is to grasp the policy of the oil sand resource countries, the properties and existing conditions of the resources, effects of the oil sand resources on a long term energy supply/demand, etc., and to clarify the meaning and position of the researches on the development of oil sand resources in the future energy policy of Japan. The quantities of oil sand resources are mostly in the process of investigation except Alberta province of Canada and are estimated to be two trillion barrels. The quantity for which strip mining is possible is about 90 billion barrels, which are mostly located in the Athabasca region. The oil sand holding countries take a policy of positively developing oil sand. No barriers are particularly provided against the introduction of foreign technology and capital. Where the prospects are possible for the development of oil sand are Canada and Venezuela. R and D should be emphasized on the refining of bitumen and the extraction method within the oil reservoir. The investment per b/d is about 15-20 thousand dollars, which is likely to be more than twice as much as for the North Sea oilfields. The properties and quality of the synthetic crude oil are superior while the risk of exploitation is small; therefore, oil sand will be competitive with crude oil in the future. (NEDO)

  12. Report on achievements in fiscal 1998. Research and development of a welfare techno-system; 1998 nendo welfare techno system kenkyu kaihatsu (Sapporo) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The surveys and studies having been performed in the present fiscal year are as follows: (1) in the surveys and studies on self-reliant and at-home care-taking for elderly people living in residential houses, using biological information of snowy and cold districts as the parameters, (a) effect of changing the attitude in two-step ascent and descent motions was studied, (b) stair ascent and descent motions were analyzed, (c) standing-up motion using a sitting position handrail was analyzed, and (d) stride-over motion patterns and hip joint movements were experimented; (2) in the studies of a living environment system to support self-reliant way of living of elderly and physically handicapped people in snowy and cold districts, studies were made on (a) shapes of entrance and exit spaces of a residential house, and features of moving motions of elderly and physically handicapped people, (b) living activity patterns and pleasantness centering around the living section in the house of the at-home elderly people, (c) forms of approach spaces for independent residential houses that consider snow disposal: (3) in development and improvement of care-taking devices with importance placed on physical and psychological adapting function of the users and harmony with the users, studies were given on (a) noise characteristics of rooms in which at-home welfare devices are installed, (b) colors and recognizability of switches on welfare devices for elderly persons, (c) drive experiments of moving devices in winter, and (d) motion simulation of ridable devices; and studies were made on (4) moving and riding welfare device systems for elderly and physically handicapped people in snowy and cold districts, and (5) user interface of motor-driven wheelchairs. (NEDO)

  13. Achievement report on research and development on fusion zones in fiscal 1999. Second volume. Chemo-intelligence; 1999 nendo yugo ryoiki kenkyu kaihatsu seika hokokusho. 2. Kemo intelligence

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    With an objective to artificially realize diverse functions and structures using as a trigger the molecule recognition in living things and organisms, researches and surveys were performed on chemo-intelligence. This paper reports the achievements in fiscal 1999. In a theoretical approach to elucidate inter-molecular interactions, research was performed on hydrogen bondage, CH-{pi} interactions and stacking by using the computerized chemical method. In the design and synthesis of host molecules, development was carried out on a synthesizing method based on large ring compounds and non-ring compounds utilizing the interactions having weak hydrogen bondage, and molecular design utilizing the conformity in sizes and shapes of the molecules. In structuring the host molecules having a function to recognize neutral molecules, research was executed on capturing and activation of neutral organic molecules as the artificial host molecules. In addition, investigations were given on the latest information about separation of ionic substance recognizing compounds and their application to sensing, structure of ultra-molecular construction and the function thereof, and approaches aimed at their use as materials and applications. (NEDO)

  14. Achievement report for fiscal 1998 on Welfare Technosystem Oita research and development; 1998 nendo Walfare technosystem kenkyu kaihatsu (Oita) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Before a welfare facility is introduced into a home, studies should be sufficiently conducted about the circumstances of daily life, not only of the aged user but also of the family members who take care of the aged user. In the development of handrails, it is found that plastic foam containing wood flour presents the feel of wood, easy to bend when heated. Materials are investigated for flexural strength, and ABS (acrylonitrile butadiene styrene) is chosen as the suitable material. As for devices to assist toileting, a system is developed under which the patient's legs are raised. Since there are arguments for and against the operation itself of mechanically raising a patient's legs, however, efforts will continue to develop much advanced systems. In the study of walk and transfer behavior, a toilet frame mockup is designed and manufactured, which is for collecting data. In an preliminary experiment, tests are conducted about a transfer from a chair to another and, assuming a physically handicapped patient, a transfer from a wheelchair. The data thus collected are to be subjected to analysis and image processing by the use of measuring sensors. Development is described of interfaces, for use in devices to serve as information mediums, which consider the cognition characteristics of the aged people. As for the development of devices for communication, environmental control, and display, their basic operation and feasibility are discussed. Actualities of costumes for physically handicapped people are also investigated, and development is carried out as required. (NEDO)

  15. Fiscal 1976 Sunshine Project result report. Research on solar energy utilization systems (photovoltaic power generation); 1976 nendo taiyo energy riyo system chosa kenkyu seika hokokusho. Taiyoko hatsuden

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-03-01

    This report describes the fiscal 1976 research result on the technical and economical perspectives of various solar cells, high-efficiency solar cell and its evaluation technique, and a photovoltaic power generation system and its applications. On Si single-crystal slice solar cell, it was pointed out that cost reduction by automatic production process using no vacuum process is essential. On Si thin film solar cell, some problems to be solved for development of particle accelerating growth technique were pointed out. Study was also made on 2-6 group compound semiconductor solar cell, 3-5 group bulk crystal solar cell, 3-5 group thin film solar cell, solar collection solar cell, and raw polycrystal Si materials. On photovoltaic power generation systems, it was reconfirmed through reconsideration of power generation systems for every application that the photovoltaic power generation system for residences is promising. On medium- scale power generation systems, study was made on power load and system configuration in consideration of applications to electric railway, highway, and power source of isolated islands. (NEDO)

  16. FY 1991 Report on the results of the researches on nonlinear photoelectronic materials; 1991 nendo hisenkei hikari denshi zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-03-01

    The nonlinear optics with light-light conversion and electro-optical effects are expected to be the optical materials of the next generation for their functions of, e.g., conversion of the infrared laser beams into visual light, and optical switching. The efforts are directed to development of the procedures for exploring and designing various raw materials, and technologies for synthesizing the raw materials and for producing and evaluating the materials, in order to develop highly nonlinear, high-speed responding materials. Three areas are studied; for the organic materials, the chiral nonlinear effects are demonstrated and the new procedure for determining electrical susceptibility ({gamma}) is developed; for the dispersed materials, highly nonlinear susceptibility of glass dispersed with fine particles of semiconductors, e.g., CuCl, is realized, and possibility of controlled dispersion of fine semiconductor particles in an organic polymer is established; and for development of the superlattice-based materials, the layered structures of thin organic superlattice films are studied, the thin semiconductor films of high purity and little defects are prepared, and development of the three-dimensional structures is started. The individual researches are conducted, 3 for the organic materials, 4 for the dispersed materials, and 2 for the superlattice-based materials. The targets of susceptibility and response are 10{sup -8}esu or more and 10ps or less, respectively. (NEDO)

  17. Report on the achievements in the Sunshine Project in fiscal 1986. Surveys on coal type selection (coal type survey); 1986 nendo tanshu sentei chosa seika hokokusho. Tanshu chosa

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-03-01

    The purpose of the present study is to elucidate coal quality features of different types of coals and identify the relationship between the coal quality features and the liquefaction characteristics by performing liquefaction characteristic evaluation tests. Based on the result therefrom, a method is established for coal field assessment that can estimate yield of liquefaction in coal fields and coal mines to serve for selection of coal types suitable for liquefaction. Coal quality feature surveys and liquefaction characteristics evaluation tests under the standard conditions have been completed on 48 coal types including Canadian, Australian and American coals. Elucidating the coal quality features of different coals can specify parameters for the coal quality features related to the liquefaction characteristics. Coal ranks elucidate the vitrinite reflectance, structure constituent factors the vitrinite content, composite factors the volatile matter content, quantity of heat generation, and number of H/C and O/C atoms. Investigating the relationship between the coal quality features and the liquefaction characteristics can provide fundamental data for primary screening of raw material coals for liquefaction. The result of the liquefaction characteristics evaluation test under the standard conditions can be the detailed comparative data relative to data derived from the simplified liquefaction characteristics test that is performed to estimate liquefaction yield of specific coal field and coal mine. (NEDO)

  18. Report on 1981 result of Sunshine Project. Research on direct liquefaction reactor of coal; 1981 nendo sekitan no chokusetsu ekika hannoki no kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-07-01

    This paper explains the results of research on direct liquefaction reaction of coal in fiscal 1981. The direct liquefaction is a reaction of three phases, gas-liquid-solid, under high temperature and high pressure. A tube type was employed in order to increase volume efficiency of the reactor, the continuous phase disperse number was decreased in order to bring it close to plug flow, and the paste Re number was increased to some extent in order to prevent sedimentation of coal particles. Hydrogen was supplied from the tube halfway for the purpose of supplementing the lowering of hydrogen partial pressure with the progress of reaction. A gas-liquid separator was installed so that increase in gas quantity was controlled in the rear stage of the reactor. As for catalysts, iron ore-sulfur system was examined which was promising as a disposable catalyst in place of the conventional iron system. Effect of catalytic addition was clearly recognizable in comparison with non-catalytic, with an exothermic peak observed comparable to the coal hydrogenation reaction of 350-420 degree C. Its catalytic effect was also presumable from the high pressure differential thermal analysis curve. The catalytic mechanism in the case where sulfur is added to hematite and limonite is similar to that of Fe{sub 2}O{sub 3} - sulfur catalyst, with the center of activity supposed to be Fe{sub 1-x}S. The catalytic effect is largely dependent on the particle size. (NEDO)

  19. Sunshine Program for fiscal 1981. Research on direct coal-liquefaction reactor; 1981 nendo sekitan chokusetsu ekika hannoki no kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-04-17

    The research aims to develop a new-type high-efficiency reactor for direct coal-liquefaction from a reaction engineering viewpoint and, at the same time, to settle problems expected to occur in industrializing this technique. The research items are Item 1 on the analysis of characteristics of a tubular continuous reactor and Item 2 on high-activity catalysts. Under Item 1, on the assumption that liquefaction reaction is dominantly a reaction in a continuous phase, a reactor is selected in consideration of homogeneous-phase reaction, and operating conditions are set according to the selected reactor and to the liquefaction reaction characteristics. A somewhat large Re number is assigned to the paste. Since the hydrogen partial pressure lowers with the progress of reaction, hydrogen is resupplied at the middle of the reaction tube. The volume of gas increases toward the final stage of reaction, decreasing the continuous phase holdup. Since it is undesirable to let the decrease stand, a vapor-liquid separator is provided for the control of the gas volume. In this fiscal year, investigation is conducted into details so as to determine if the reactor is equipped with intended characteristics. Under Item 2, the iron ore is deemed to be the most promising as disposal catalysts for liquefaction. In this fiscal year, studies are conducted to disclose the activity etc. of catalysts of this type. (NEDO)

  20. FY 1993 Research and development of advanced ceramic gas turbines. Researches on social adaptability; 1993 nendo senshingata ceramic gas turbine no kenkyu kaihatsu seika hokokusho. Shakai tekigosei kenkyu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-05-01

    The ceramic gas turbines (CGT's) for, e.g., cogeneration and portable power generation systems are studied and evaluated for their environmental preservation, energy saving and economic characteristics. Types of utilization and market sizes are also studied for, e.g., portable power generation systems. The items studied include current status of cogeneration systems in USA, and recognition of cogeneration systems in Japan. The study results lead to the conclusions that the biaxial CGT for portable power generation systems is a promising substitute for diesel engines as the power source in the future, and 300kW class CGT's will have the markets of 170,000 units and potentially 450,000 units, because of their expected wide applicability. The studies on their economic, energy-saving and environmental load reduction effects indicate that one unit brings the economic effects totaling 616,000 yen, due to reduced fuel consumption and NOx abatement. They could reduce NOx emissions by 8,090 t/y for automobiles and 6,570 t/y for the others, when they fill the potential markets. (NEDO)

  1. Fiscal 1976 Sunshine Project result report. Research on solar energy system (weather survey); 1976 nendo taiyo energy system no kenkyu seika hokokusho. Kisho chosa

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-03-31

    This report describes the fiscal 1976 research result on weather survey for solar energy systems. Study was made on preparation of the global solar radiation (GSR) map of Japan. To obtain the estimation equation of GSR based on related weather data, analysis was made on data at A type GSR observation sites and related weather data. As some factors effective for estimating monthly mean GSR, a relative sunshine duration, snowfall index (ratio of days more than 10cm in snowfall) and solar altitude index (sine of solar altitude at culmination hour) were selected. The estimation equation was prepared on the basis of these above factors. GSR was affected by relative sunshine duration exceedingly, snowfall by 12%, and solar altitude difference by 6% within an error of 5%. The monthly and annual GSR maps were prepared every site by the above calculation. The continuous observation results in Kagoshima and Fukuoka by recording direct pyranometers are presented. Scattered solar radiation is defined as the difference between simultaneously measured GSR and direct solar radiation. Weather data preparation in Fukuoka for design of solar cooling/heating and hot water supply systems is also described. (NEDO)

  2. Achievement report on research and development in the Sunshine Project in fiscal 1977. Hydrogen energy; 1977 nendo seika hokokusho gaiyoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-04-01

    This paper summarizes achievements in the Sunshine Project related to hydrogen energy in fiscal 1977. In the electrolytic process in hydrogen manufacturing technologies, new composite materials are developed in relation with membranes and electrodes as the high temperature and pressure water decomposition method. A bench-scale water decomposition tank using organic polymer ion exchange membranes is fabricated on a trial basis and tested for studying solid electrolyte decomposition method. In hydrogen manufacturing technologies using thermo-chemical process, discussions are being given on cycles of iron systems, iodine systems and hybrid systems (mixture of thermo and photo chemistry and electrochemistry). For hydrogen transporting and storing technologies, metal hydrides most suitable for hydrogen storage are developed, and storage systems are studied. In hydrogen combustion, elucidation is made on fundamental conditions for mixed and single combustion technologies suitable for prevention of reverse ignition and suppression of NOx generation. Studies are also being made on fuel cells using aqueous solution and solid electrolytes. Studies on hydrogen fueled engines are also described. In hydrogen safety assuring technologies, discussions are being given on prevention of explosion disasters, prevention of embrittlement of materials due to hydrogen and criteria for safety assuring technologies. Descriptions are given also on studies on total hydrogen energy systems and hydrogen fueled automobiles. (NEDO)

  3. Fiscal 2000 research achievement report. Super-advanced electronics technologies development promotion project; 2000 nendo kenkyu seika hokokusho. Cho sentan gijutsu kaihatsu sokushin jigyo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-01

    For the construction of a common base of key technologies in the domain of electronics and information with the influence propagating across a wide range of industries, research and development was conducted of technologies of ultrafine working process, technologies of ultimate measurement, analysis, and control, technologies of new functional electronic materials, etc. Studied in the field of electron beam lithography were high precision and large area imaging technology, highly accurate electron optics control system technology, and beam monitoring technology. Studied in the field of ultrashort wavelength electromagnetic wave patterning system technology were proximity ultrashort wavelength electromagnetic wave patterning system technology, reduced ultrashort wavelength electromagnetic wave patterning system technology, and ultrahigh precision new materials patterning technology. Also studied were technologies of super-advanced plasma measurement, analysis, and control, and technology of super-advanced cleaning. In the field of technologies of new functional elements and films, studies were conducted about technologies of highly sensitive GMR (giant magnetoresistive) film and head fabrication process for contact magnetic recording and technologies of a spin-valve head with submicron track width for contact magnetic recording. (NEDO)

  4. Summarized achievement report on the Sunshine Project in fiscal 1979. Hydrogen energy; 1979 nendo sunshine keikaku seika hokokusho gaiyoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-04-01

    This paper summarizes the achievement report on the Sunshine Project in fiscal 1979 for hydrogen energy research. In hydrogen manufacturing technologies, the paper describes improvement in membrane performance and discussions on electrode materials in high temperature and pressure electrolysis. In the thermo-chemical method, hydrolysis of iron bromide (II) in the iron system cycle was compared to three kinds of reaction patterns corresponding to phase change, and evaluation was given as the hydrogen generating reaction. In the iodine system the first stage oxidation and reduction reaction of MgO-I{sub 2} was subjected to a continued experiment by using a batch autoclave. Discussions were continued on device materials for the iodine cycle. In the light irradiation electrolytic method for the mixed cycle, the light intensity was experimented at a force 12 times greater than that of the solar beam, and a reaction rate of 80% was achieved. Raising the temperature causes the reaction rate to decline, but it can be supplemented by raising the light intensity. A heat diffusion column was found effective in HI decomposition (hydrogen acquisition). For hydrogen transportation and storage, researches are continued on metal hydrides. In hydrogen utilization technologies, combustion, fuel cells (using high temperature solid and alkaline aqueous solution electrolytes), and hydrogen engines are studied. This paper also describes studies on hydrogen safety assuring measures and energy systems. (NEDO)

  5. Report on achievements in fiscal 1999. Research and development of advanced function creating and processing technologies; 1990 nendo senshin kino soshutsu kako gijutsu no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-03-01

    In order to provide materials with superior advanced functions such as high-level biological compatibility, external environment identifying function, chemical reaction activating function, high-performance electromagnetic properties, and corrosion and heat resistant high strength properties, it is intended to establish novel material creating technologies using chemical processing processes that can control finely the compositions and constructions of the materials. The efforts include (1) works on research and development of an ultra-high purity separating technology composed mainly of laser selection and excitation actions for manifestation of new natures such as sensing function, catalytic function, and electromagnetic properties, (2) works on research and development of a micro-fine crystal controlling technology capable of designing materials, such as micro-fine particle synthesizing, dispersing and compounding technologies, micro thin film lamination, and interface controlling technologies to create materials having high strength as well as high tenacity, and (3) works on research and development of high-function organic material synthesizing technologies compounding the utilization of high-grade photons with application of extreme environmental fields such as ferromagnetic fields whose effects are expected on controlling structure like orientation of atomic and molecular levels for the purpose of creating high-function materials having high heat resistance, corrosion resistance, and lubrication performance. (NEDO)

  6. Japan`s New Sunshine Project. 1996 Annual Summary of Coal Liquefaction and Gasification; 1996 nendo new sunshine keikaku seika hokokusho gaiyoshu. Sekitan no ekika gasuka

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    In reference to the results of the research and development under the fiscal 1996 New Sunshine Project, a report was summed up on coal liquefaction and coal gasification. As to the R and D of coal liquefaction technology, researches were conducted on liquefaction characteristics and engineering properties by coal kind, catalysts for coal liquefaction, liquefaction reaction of coal and reformation utilization of the liquefied products, liquefaction reaction mechanism and coking mechanism, solubility of coal in solvent and catalytic reaction mechanism, solvent reaction mechanism by hydrogen donor solvent, etc. Concerning the R and D of coal gasification technology, made were the basic study of eco-technology adaptable gasification technology and the study of coal gasification enhancing technology. Further, as to the development of bituminous coal liquefaction technology, carried out were the study in pilot plants and the support study of pilot plants. Additionally, R and D were done of the basic technology of coal liquefaction such as upgrading technology and environmentally acceptable coal liquefaction technology, and of coal hydrogasification technology. 3 refs., 81 figs., 25 tabs.

  7. Outline of research achievement of fiscal 1983. Development of coal liquefaction technologies; Sekitan ekika gijutsu kaihatsu. 1983 nendo kenkyu seika no gaiyo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-07-01

    Reported are the results of (1) the development of bituminous coal liquefaction technology, (2) development of brown coal liquefaction technology, (3) experimental fabrication and development of plant equipment and materials therefor, and (4) a survey on coal type selection. The goals of the development are mentioned below. Under Item (1), an optimum liquefaction process and a solid/liquid separation process are to be defined, the effect of iron-based catalysts upon liquefaction reaction is to be elucidated, a technology for constructing a direct hydroliquefaction unit is to be established, and a plant using such a unit is to be developed. Under Item (2), an optimum liquefaction technology is to be established, high in economic efficiency and reliability, by subjecting Australia's Victoria brown coal to the direct liquefaction process. In particular, a new brown coal liquefaction technology is to be established, which will be an organic combination of a novel, raw brown coal slurry dehydration technology, a solvent deashing technology, and the secondary hydrogenation technology, all centering on the basic technology of primary hydrogenation. Under Item (3), reactor materials, accessory materials, slurry pumps, etc., are to be experimentally manufactured and developed further. Under Item (4), data are to be collected on coal resources, coal quality, liquefaction characteristics, etc., during the process of technology development for liquefaction, etc. Furthermore, methods are to be established for the effective utilization of liquefaction products and for their optimum refining. (NEDO)

  8. Fiscal 1980 Sunshine Project research report. Research on underground reinjection mechanism of hot water; 1980 nendo nessui no chika kangen mechanism no chosa kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-03-01

    This report summarizes the fiscal 1980 research result on reinjection mechanism of hot water. In the research in Takinoue area, except one well with drop of nearly 2m, no change in underground water level was observed, and no change in water temperature except seasonal change, no change in river water and no leakage of reinjected hot water were also observed. Quantitative simulation was made on hot water supply from the outside strata to storage strata, features of hydraulic structure, pressure fluctuation and water balance, using tracer test data. In Nigori-Gawa area, no clear change in water level and water temperature was found. Various basic parameter data related to water flow in rocks composing storage strata were obtained by tracer test. In the research on the effect of reinjected hot water on the ground, in Takinoue area, fine earthquake was observed on fault planes, however, the spectral analysis result showed no change in ground condition. The precise survey result showed specific fluctuation during last year. In Nigori-Gawa area, fine earthquake was equivalent to that before development. Vertical and horizontal fluctuations were also observed by precise survey. (NEDO)

  9. Achievement report for fiscal 1997 on research and development of solid electrolyte fuel cells; Kotai denkaishitsugata nenryo denchi no kenkyu kaihatsu 1997 nendo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This paper describes the achievements in fiscal 1997 on research and development of solid electrolyte fuel cells. Fuji Electric has demonstrated possibilities of film type cells of predominantly metallic flat plate supporting type of a large-area cell lamination system, and seal-less stack structure. Sanyo Electric has discussed making thinner the composite cell lamination type anode, optimization in sintering temperature, and sealing materials. The Fine Ceramic Center has performed a 1,000-hour test on an La(Sr) MnO{sub 3}-YSZ electrode, in which A-site defect amount was decreased to 0.1-0.02 to stabilize micro-structure air electrodes for an extended period of time. Fujikura has discussed functional materials for high dispersion and slanting in a fuel electrode Ni/YSZ. Mitsubishi Heavy Industries has fabricated MgO-based fuel electrodes on a trial basis, and performed internal reformation and power generation tests by using full-size stacks. Murata Manufacturing Company has verified long-term power generation properties and stability of a three-layered co-sintered film of flat plate type. Mitsui Shipbuilding has reached a near final conclusion on the basic structure of gas separator cells. The Central Electric Power Research Institute has completed a conceptual design on a 300-MW class composite power generation system in which SOFC and gas turbines are combined. The Electric Power Development Company has discussed problems in SOFC composite power generation development using coal gasified fuel. (NEDO)

  10. 1998 Annual Study Report. Standardization for compatibility between home information devices; 1998 nendo seika hokokusho. Joho kaden kikikan no sogo setsuzokusei kakuho no tame no hyojunka

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Wide-band POF covering Gbps as a Japan-made R and D fruit will be commercialized in the near future. It is very important to make an international standard specification for the transmission by the aid of the wide-band POF, which would be basically the standard for the future home networks. The efforts in this year were directed to finding the optimum parameters for widening the band, for which the necessary characteristics related to, e.g., transmission band and bending loss were measured and evaluated, and the specifications covering a certain range were established. The wide POF system is considered to provide the first chance of the optical transmission systems going into homes on a large scale, and the service conditions and regulations for use in homes have been comprehensively studied. These efforts have begun with collection of the measured data in consideration of operating optical elements represented by LD's, their peripheral circuits and the transmitter/receiver assemblies in which they are mounted at S400 or more. Each of the light emitting and receiving sections, including their peripheral circuits, were measured and evaluated, where they were mainly operated at a short wavelength of 650 nm, which is the same as that for the DVD. (NEDO)

  11. FY1999 annual report on the research and development on practical industrial cogeneration technology; 1999 nendo sangyoyo cogeneration jitsuyo gijutsu kaihatsu kenkyu seika

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The basic plan aims to quicken the practical application of the industrial HBGT (hybrid gas turbine) cogeneration technology and thereby to realize high-efficiency energy utilization for reduction in CO2 emission. For this purpose, a medium-scale HBGT, expected to be high in efficiency and low in polluting, and its components are subjected to assessment tests and endurance tests to prove that there are reliability and soundness in HBGT. Ceramic members are developed which are high in strength at elevated temperatures and in resistance to oxidation, and are subjected to assessment so that they will be further improved in reliability and durability. An HBGT is designed, fabricated, and operated. The engine system is tested for performance, and the performance is improved. It is put to a long-term operation, which is to confirm the presence of soundness and reliability in HBGT as an industrial cogeneration system. Industrial fields in which HBGT will be useful are selected and surveys are conducted to find out how it will function in such selected fields. Problems which HBGT will encounter upon practical application are extracted, and measures for solving them are clarified. Such an HBGT will have a shaft output of approximately 8,000kW, engine thermal efficiency of not less than 34%, and a turbine inlet temperature of approximately 1,250 degrees C. (NEDO)

  12. Achievement report for fiscal 2000 on development of technologies to reduce pollutants in oil refining; 2000 nendo sekiyu seisei osen busshitsu teigen nado gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Research and development has been made on technologies to reduce sulfur content in light oil and on optimization of light oil quality. This paper summarizes the achievements in fiscal 2000. In the study of enhancing the desulfurization rate in gas oil deep hydrodesulfurization process, it was found that NiHY zeolite having Ni introduced by using the ion exchange method shows stable activity, whereas the target of sulfur content of 50 ppm or lower was achieved by adding the third constituent and by optimizing the impregnation solution to pH3. In the study of the Ni, Mo/alumina catalyst, the desulfurization activity was enhanced by optimization of carrier pore size to 120 to 140 angstroms and by addition of phosphorus and silica, having the target of sulfur content of 50 ppm or lower achieved. In the research of manufacturing low-sulfur light oil using heavy oil desulfurization and hydrocracking, optimization was performed on the catalyst used in the latter stage of heavy oil desulfurization, and evaluation was given on the performance in combination of commercially available hydrometallation catalyst/middle part HDS catalyst/bottom part HDS catalyst. As a result, achievement of the target of sulfur content in the desulfurized light oil of 300 ppm or lower was verified. Life evaluation test is in continuation on the heavy oil hydrocracking catalyst. (NEDO)

  13. Report on results 1998. Research and development on fusion area. Part 2 (chemo-intelligence); 1998 nendo seika hokokusho. Yugo ryoiki kenkyu kaihatsu daini bunsatsu (chemo-intelligence)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Chemo-intelligence is defined as artificially realizing and then materializing various functions and structures that are caused by the transmission of precise chemical information based on molecular recognition in organisms. Creation of substances/materials having functions no less superior to those of organisms enables environmentally benign, energy-saving, and resource-conserving functional materials to be realized, as materials for separation of toxic and useful substances, their sensing, and the conversion (catalysts). For this purpose, started were a computational chemical approach for molecular design, functional prediction, functional analysis, etc., to realize precise molecular recognition; an approach from synthesis of molecular recognition compounds; an approach from functional manifestation/elucidation, structural analysis, etc.; and also investigation and research on application to the materialization and systematization. The results were summarized by classifying them into molecular interactions, host molecules, ionic substance recognition compounds, super molecular structures, materialization, application, etc.. (NEDO)

  14. Achievement report for fiscal 1998 on Welfare Technosystem Kamogawa research and development; 1998 nendo Welfare technosystem kenkyu kaihatsu (Kamogawa) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Opinions were heard from residents about residences designed for aged people. According to their physical conditions, residents of advanced age may be classified into four groups, that is, 'Aged person who is self-reliant,' 'Patient who can walk using a walking stick or handrail, with a caregiver,' 'Patient who rides a wheelchair, with a caregiver,' 'Patient who is bedridden, with a caregiver.' The collected data will be effectively utilized in the future for planning residences that respect an advanced age. The difference between the four groups ensues from difference in human relationship in the residences and in movement and caregiving in daily life. When a residence in which a patient lives with the family is set forth for premise, what is important is to consider the request of the patient that the residence be functionally perfect and, at the same time, attention must be paid to the psychological desire that the residence be equipped with what a home is generally supposed to offer. Emerging increasingly definite out of the research conducted this fiscal year are policies towards the development of, and the feasibility of, a remotely controlled medical assistance system with patients allowed to stay at home and terminal equipment therefor. An experimentally constructed movement assistance unit is tested at Welfare Technohouse Kamogawa, and findings are obtained about the safe use of a barrier-free condominium thanks to such functions as motor-assisted walking, assistance for standing-up, collision avoidance, etc. (NEDO)

  15. Achievement report for fiscal 1998 on Welfare Technosystem Osaka research and development; 1998 nendo Walfare technosystem kenkyu kaihatsu (Osaka) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Old people's need for illumination is sufficiently covered by the JIS-stipulated illumination range. Although the minimum safe limit for the aged is serval times higher than that of the young, yet electricity saving may still be enhanced by proper adjustment without spoiling amenity for the aged. A hard floor puts a burden on the knees. The degree of fatigue due to the use of footgear is dependent not only on the shape but also on the user's habit. The transfer equipment seat surface height, if improperly set, oppresses the user psychologically and physiologically, the burdens heavier when the seat is lower. As compared with transfer aboard the wheelchair, a horizontal movement on the seat surface by the use of arms (fore and aft, right and left) demands less physiological burden. The above-said matters are taken into consideration when designing transfer equipment. As for emergency information systems, it is necessary to study seat pressure distribution, change in body temperature in a bath, change in blood pressure on the stool, and to develop a pulse counting simulator. A life space simulator and welfare utensil fitness evaluation are discussed. Also discussed are the development of a simulator for the comprehensive evaluation of motorized wheelchairs for their capability to encourage self-reliance, monitoring systems, and supervising/reporting systems (toilet irregularity annunciators etc.). (NEDO)

  16. Report on the achievements in fiscal 1999 of research and development of fusion zones. Calculation science; 1999 nendo yugo ryoiki kenkyu kaihatsu seika hokokusho. Keisan kagaku

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    In order to elucidate the mechanism for specific phenomena from the atom scale to the meso-scale, developmental research has been performed on a fusion type calculation method. This paper reports the achievements in fiscal 1999. In planning the policy of structuring the program package TACPAC and its application method, the program for materials STATE using the classical molecule dynamics method and the biological program, Peach, were selected as the programs to act as the nuclei. In continuing performance improvements respectively in the computer programs to be fused, and improving the performance of the software fused with them, the programs were transferred into a super-computer. As a result, it was found that the classical and the first principle quantum molecular dynamics method program STATE can be executed at high efficiency on the super-computer. In executing the challenging computer simulation and developing a calculation method for large scale systems, researches were performed on alcohol synthesizing reaction on copper surface and the status of association of gene DNA molecules with enzymes, and development was carried out on a matrix generation method to calculate non-empirical molecule trajectories of the large scale systems. (NEDO)

  17. FY 1999 Advanced research and development project under New Sunshine Project. Study on supercritical solvolysis reaction; 1999 nendo chorinkai ryutai riyo gijutsu sendo kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The research and development project is implemented for the chemical processes which utilize supercritical fluids, in order to establish the basic technologies for the environment-friendly chemical processes. For the solvolysis, the conditions under which plastics are hydrolyzed in supercritical water are investigated, and the basic data are obtained for the optimum conditions under which thermoplastic resins are hydrolyzed. The mechanisms involved in hydrolysis of polymers in supercritical water are elucidated to some extent. The environment-friendly process for synthesizing polycarbonate in supercritical carbon dioxide gas is investigated, and the continuous flow sheets are established for securing almost 100% conversion in the presence of an inexpensive catalyst. For the oxidation, the tests are conducted to burn low-grade coal in supercritical water, and the conditions under which it is burnt without releasing acid and toxic gases are found. For the hydrogenation, heavy fuel oil is treated in supercritical water to produce the lighter products. The conditions under which light oils and gases are produced are clarified, and the basic data are obtained for producing light gases from the resultant coke as the by-product. (NEDO)

  18. Achievement report for fiscal 1981 on Sunshine Program. Basic research on solvent treatment technology for coal; 1981 nendo sekitan no yozai shori gijutsu no kiso kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-03-01

    This research aims to prepare basic data on extraction liquefaction, which is one of the techniques of producing clean liquid fuels and chemical materials from coal, and thereby to contribute to the development of this process. The items taken up in this research are Item 1 on basic research using a small reactor, Item 2 on research on short-duration hydrogenation reaction in the intermediate temperature range, and Item 3 on basic research on the realization of a continuous operation. Item 1 is divided into Item (1) on primary hydrogenation extraction and Item (2) on secondary hydrogenation treatment. Under Item (1), hydrogenation characteristics are investigated of low rank coal with the Chinese brown coal heading the list and, under Item (2), the result of cleaner light oil production through secondary hydrogenation using different catalysts and the result of extraction from brown coal though secondary hydrogenation using a Co-Mo based catalyst are stated. Item 3 has been incorporated into Item 2 to stay there from this fiscal year on, and is divided into Item (1) on primary hydrogenation extraction and Item (2) on secondary hydrogenation treatment. Under Item (1), the result of a test operation of a small-size continuous coal hydrogenation extraction liquefaction unit using bituminous coal as specimen is reported and, under Item (2), the outline of a small-size fixed bed hydrogenation treatment unit newly installed this fiscal year is described. (NEDO)

  19. FY 1982 annual report on the research and development of automatic sewing systems; 1982 nendo jido hosei system no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-03-01

    The automatic sewing system technique research association has been commissioned by the Agency of Industrial Science and Technology for (research and development of automatic sewing systems). This program covers R and D of the elementary techniques for total systems and sewing preparation/processing, sewing/assembling, cloth handling, and system management/control. The total system is designed and studied, and automation of the production systems is studied, in order to reduce time for producing unit quantity of diversified types of clothes in small quantities at least by 50% from the current level. The test plant is designed, constructed and operated, to evaluate and confirm its functions for the above purposes. In the FY 1982, the conceptual designs are drawn to establish the overall production systems for producing diversified types of clothes in small quantities. The program for the sewing preparation/processing evaluates various characteristics of cloth to be processed by the sewing system, based on which the cloth characteristics evaluation, cloth stabilization, high-function pattern preparation, and cloth measuring/unfolding/cutting techniques are studied to establish the automatic cloth unfolding/cutting techniques. The FY 1982 efforts are directed to the conceptual designs. (NEDO)

  20. FY 1983 annual report on the research and development of automatic sewing systems. Total systems; 1983 nendo jido hosei system no kenkyu kaihatsu seika hokokusho. Total system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1984-03-01

    The automatic sewing system technique research association has been commissioned by the Agency of Industrial Science and Technology for (research and development of automatic sewing systems). This program covers R and D of the elementary techniques for total systems and sewing preparation/processing, sewing/assembling, cloth handling, and system management/control. This report describes the results of the R and D efforts for the total systems. The basic data are collected for a total of 5 representative types of apparels. The technical problems involved in the current and automatic sewing systems are clarified for each apparel type, to collect the data for studying the test plant plans. The automatic sewing system for each apparel type is illustrated by images, for expressing the system concepts. The concept for the basic designs of the total system is drawn for FMS. For achieving the objective of reducing time for producing unit quantity of diversified types of clothes in small quantities at least by 50% from the current level, the study is focused on how the works are (flown) in the system, for which configuration of each device is studied. The basic specifications are drawn, viewed from development of the total system. (NEDO)

  1. Fiscal 1974-1975 Sunshine Project research report. Hydrogen energy research results (National laboratories and institutes); 1974, 1975 nendo suiso energy kenkyu seika hokokushu. Kokuritsu shiken kenkyusho kankei

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-10-01

    This report summarizes the 21 research results on hydrogen energy promoted by 3 national laboratories and 2 national institutes. (1) Tokyo National Industrial Research Institute (TNIRI): Ca-I system, Mn system, S system and hybrid cycles, and water decomposition reaction by CO as thermochemical hydrogen production technique. (2) Osaka National Industrial Research Institute (ONIRI): Fe system, Cu system and ammonia system cycles, and high-temperature high-pressure water electrolysis. (3) Electrotechnical Laboratory: high- temperature direct thermolysis hydrogen production technique. (4) TNIRI: Mg-base and transition metal-base hydrogen solidification technique. (5) ONIRI: Ti-base and rare metal- base hydrogen solidification technique. (6) Mechanical Engineering Laboratory: hydrogen-fuel engines. (7) Electrotechnical Laboratory and ONIRI: fuel cell. (8) TNIRI: disaster preventive technology for gaseous and liquid hydrogen. (9) Chugoku National Industrial Research Institute: preventing materials from embrittlement due to hydrogen. (10) Electrotechnical Laboratory: hydrogen energy system. (NEDO)

  2. Achievement report on research and development in the Sunshine Project in fiscal 1976. (Electrotechnical Laboratory/Research and development cost); 1977 nendo kenkyu seika no gaiyo (kenkyu kaihatsuhi)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-07-01

    This paper describes achievements in research and development of new energy technologies (the Sunshine Project) in fiscal 1997 at the General Research Institute for Electronics Technologies. In spectral radiance measurement of solar beam, the measurement is continued in ultraviolet and visible ray zones to accumulate and analyze the data, and a near infrared zone measuring device is completed to start the measurement. In solar heat power generation, studies are made on models, devices and materials, and discussions are given on their systematization. Fundamental studies are also being made on solar cells to pursue economical and technological feasibility of solar beam power generation systems. Fundamental studies are being performed to realize thermal electron power generation systems utilizing solar furnaces. Studies are being carried out to elucidate fundamental conditions for a hydrogen manufacturing method using high-temperature pyrolysis of water at 1,000 degrees C or higher. High-temperature solid electrolyte fuel cell elements are fabricated on a trial basis to elucidate the technological problems therein. Energy systems are identified as the sum including the mutual relationship between societies and nature to study optimal systems. Energy conversion utilizing low temperature differential (especially in marine application) is being discussed. The paper also describes studies on super-conducting magnets for energy storage. (NEDO)

  3. Fiscal 1998 research achievement report. Research and development for acceleration of biological resource information infrastructure construction; 1998 nendo seibutsu shigen joho kiban seibi kasokuka kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    To fulfill the above-mentioned purpose, research and development of technologies were carried out involving genetic information measurement, genetic information analysis and utilization, analysis and utilization of information on proteins, and the measurement of biomolecular interaction. In a chapter 'Research and development of genetic information analysis using next-generation genome chip,' gene amplification is effected using RNA-DNA molecules and a method for efficiently building UPD (unilateral protruding DNA) was developed. In a chapter 'Development of international standard DNA chip and analyzing system for analysis of massive gene expression,' a relational database program for activating a system for gene preservation, purification, multiple injection, and management was completed. In a chapter '3D-1D modelling of all the proteins coded on genomes,' this fiscal year, analyses were conducted using Escherichia coli and Bacillus subtilis as model microbes. In a chapter 'Analysis of gene expression clustering,' a software program was developed for measuring and analyzing the budding yeast gene expression profile. (NEDO)

  4. Collection of outlines of achievement reports for fiscal 1976 on Sunshine Program. Hydrogen energy; 1976 nendo sunshine keikakaku seika hokokusho gaiyoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-04-01

    Twenty studies are outlined, which are: Hydrogen production technology using electrolysis (Osaka National Research Institute); Hydrogen production technology using high-temperature/high-pressure electrolysis (Showa Denko K.K., and 1 other); Hydrogen production technologies using thermochemical method (4 articles - Osaka National Research Institute; Tokyo National Research Institute; Hitachi, Ltd.; Mitsubishi Heavy Industries, Ltd.); Water decomposition by thermochemical and photochemical hybrid cycle (Yokohama National University); Hydrogen production technology using direct thermolysis (Electrotechnical Laboratory); Hydrogen solidification technology (2 articles - Osaka National Research Institute; Tokyo National Research Institute); Combustion technology (Osaka National Research Institute); Materials for fuel cells (Osaka National Research Institute); Manufacture of fuel cells (Electrotechnical Laboratory); Systematization of fuel cells (Electrotechnical Laboratory); Hydrogen-fueled engine (Mechanical Engineering Laboratory); Disaster prevention technologies for gaseous and liquid hydrogen, etc. (Tokyo National Research Institute); Prevention of embrittlement of materials used with hydrogen (Chugoku National Research Institute); Refining, transportation, and storage systems, and safety techniques for hydrogen (Industrial Research Institute); Hydrogen energy total system (Electrotechnical Laboratory); Comprehensive examination of hydrogen-using subsystems and peripheral technologies (Electrochemical Society of Japan, and 6 others). (NEDO)

  5. Summary of FY 1980 results of Sunshine Project. Development of coal liquefaction techniques; 1980 nendo sekitan ekika gijutsu no kaihatsu seika hokokusho. Sunshine keikaku itaku kenkyu kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-03-01

    This report summarizes the results of the 3 R and D themes for coal liquefaction techniques, pursued by the Sunshine Project; (1) development of solvent extraction type liquefaction plant, and brown coal liquefaction technique R and D demonstration surveys, (2) development of solvolysis type liquefaction plant, and (3) development of direct hydrogenation type liquefaction plant. For the theme (1), the 1 T/D test plant, solid/liquid separator and small-size continuous settlement separator are constructed, and partly completed. The elementary studies include solvent extraction type liquefaction process, materials for coal liquefaction plant and solid/liquid separation. Australia's Victoria brown coal and Chinese coal are studied to clarify the possible problems involved in liquefaction of these coal species for commercialization of the liquefaction techniques in the early stage. The elementary techniques studied include dehydration of brown coal, milling at high temperature in oil, de-ashing, and secondary and primary hydrogenation. For the theme (2), the 1 T/D plant is inspected and maintained to clarify the problems involved in the continuous operation, revamped and repaired as necessary, given preventive maintenance, and tested for operability confirmation. The elementary studies include solvolysis type liquefaction process, scale-up, hydrogenation plant for solvolysis pitch. For the item (3), the 2.4 T/D test plant is constructed, and the elementary studies are conducted, for, e.g., liquefaction reactions in the presence of an iron-based catalyst. (NEDO)

  6. Fiscal 1975 Sunshine Project research report. Technology assessment on hydrogen energy technology. Part 2; 1975 nendo suiso energy gijutsu no technology assessment seika hokokuksho. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-03-31

    This research assesses the impact of development of practical hydrogen energy technology on the economy, society and environment in Japan, and proposes some effective countermeasures, the required technical development target and a promising promotion system. The example of technology assessment assuming practical technology several tens years after is hardly found. Hydrogen energy technology is in the first stage among (1) initial planning stage, (2) technical research and development stage, (3) practical technology stage and (4) service operation stage. In the first fiscal year, as the first stage of determination of the communication route between society and technology, study was made on the concrete system image of practical technology. In this fiscal year, study was made entirely on preparation of the scenario for imaging the future economy and society concretely, modifying the planning of the hydrogen energy system. Through comparison of the scenario and system, the meaning and problem of the hydrogen energy technology were clarified. (NEDO)

  7. Achievement report for fiscal 1998 on development of advanced household electric appliance recycling technology; 1998 nendo senshinteki kaden recycle gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    With an objective to develop a household electric appliance recycling technology, research and development has been made on crushing of compressors, separation of resins and metals, and regenerative utilization of urethane used as the refrigerator heat insulating material. In the compressor crushing technology, development was made on a ring hammer crusher of wood pattern horizontal type. In the research of the resin-metal separation technology, the dry-type separation and material purity were enhanced successfully by means of classification of materials to be crushed according to grain sizes, and classification using an eddy current screening device and a specific gravity screening device. In the research of the urethane regenerative utilization technology, the contained fluorocarbon was decomposed at the rate of 99.999% by modifying and rinsing the pyrolytic gas from the urethane by means of cracking, having achieved to make the material innocuous. The fuel gas thus obtained can be utilized for electric power generation. In addition, a method to granulate the material was established by mixing it with thermo-plastic resins. It was discovered that using the recovered urethane, which is pulverized smaller than 300 {mu} m, can elevate the heat insulation performance when it is used as the vacuum heat insulator, proving its capability of being re-utilized in refrigerators. (NEDO)

  8. Fiscal 1998 achievement report. Research and development of simplified dioxin analyzing technology, etc.; 1998 nendo dioxin kan'i bunseki gijutsu nado kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    A simplified method is developed, which measures dioxins in flue gas without using GC/MS (gas chromatography/mass spectrometry) of the double focusing type. The sampling device is built of two collecting bottles, containing water and diethylene glycol, and uses no XAD-2 (cross-linked amberlight divinyl benzene) resin. Such a design does not need time consuming Soxlet extraction in the sampling process and shortens the processing time. An HPLC (high performance liquid chromatography) system replaces the convenient column chromatography system in the cleanup process, and this enables automation and rapid treatment. For the measurement of toxicity equivalent, GC/MS is used to separate and quantify 17 kinds of toxic isomers as in the conventional method. The GC/MS is of the quadruple focusing type, however, and this reduces the device cost at the initial stage and shortens the time for operators to acquire the skills of maintenance and operation. Though the quadruple focusing type is inferior to the double focusing type in sensitivity, the shortcoming is compensated for by massive specimen injection using a PTV (programmable temperature vaporizer). The result of a JIS (Japanese Industrial Standard) method and the result of this newly developed method are found to agree excellently with each other. This method is simple and efficient, suitable for use in the analysis of small incinerator flue gas. (NEDO)

  9. Fiscal 2000 achievement report on the research and development of nanometer controlled optical disk system; 2000 nendo nanometer seigyo hikari disk system no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Development proceeded of nanometer controlled optical memory technologies as part of systematic research and development aiming at the reinforcement of industrial technology power in the field of data recording. Activities were conducted in the four fields of (1) high density signal processing technology, (2) high performance disk materials technology, (3) disk substrate fabrication technology, and (4) signal detection technology. Discussed in field (1) were multivalue ROM (read only memory) disk signal regeneration, SIL-LBR (solid immersion lens-laser beam recorder), dry etching process using RIE (reactive ion etching), SHG (second harmonic generation) blue laser, and a multivalue ROM disk evaluation system. Studied in field (2) were the evaluation of ROM disk performance dependent on recording materials, development of high density recording materials, and the evaluation of crystallization induction time using a static tester. Studied in the development of high density recording materials was the formation of microscopic recording marks in a phase shift/surface recording type disk comprising a 4-element (Ag-In-Sb-Te) recording layer and an Ag reflection layer. In fiscal 2000, an attempt was made at the 0.07 {mu}m level. (NEDO)

  10. Fiscal 1974 Sunshine Project result report. Research on solar cooling/heating and hot water supply system; 1974 nendo taiyonetsu reidanbo kyuto system no kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-03-01

    This report describes the fiscal 1974 research result on solar cooling/heating and hot water supply system. This 3- year project from fiscal 1974 to 1976 aims to predict the share of solar energy in future cooling/heating and hot water supply energy demand, and develop simulation technology. The project surveys and analyzes current domestic and overseas development states, and studies various systems to obtain characteristics of every system, pursuit an optimum implementation, and establish a diffusion plan. Future energy consumptions and prices are predicted in relation to energy saving, and the utilization impact of solar energy is analyzed. Study is also made on diffusion plan, profitability and performance evaluation method. Among these schedules, in fiscal 1974 based on the survey and analysis on previous domestic and overseas development states, features and problems were arranged every system and application. The basic study on system simulation, and rough feasibility study on solar heat systems by conventional technique were carried out. The basic data on performance evaluation standards were also prepared. (NEDO)

  11. Achievement report for fiscal 1981 on solar system survey projects implemented overseas. Singapore and Australia; 1981 nendo solar system kaigai chosa jigyo seika hokokusho. Singapore Australia

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-06-01

    During a 20-day survey tour to Singapore and Australia which started on February 7, 1982, visits were paid to 6 universities, 2 national or state research institutes, 2 state government agencies, 6 passive solar facilities, and some industrial societies and solar equipment manufactures. At universities and research institutes, research and experiments are earnestly under way for the development of solar heat collectors, for the research and testing of software programs therefor, and for the research and development of photovoltaic and geothermal power generation systems. In the case of photovoltaic power, in particular, many programs require the construction of pilot plants and simultaneous supply of power to general consumers with tests and experiments continued for the pilot plants for putting the technology to practical use. This is thought to demonstrate the urgent need for measures for out-of-the-way locations. Electric power is priced at 7-8 yen/kWh, approximately half the price in Japan. Marginal supply capability is low because power is generated mainly by coal and no nuclear power is available. Efforts at underground reserves exploitation have become very active and, since there is need to supply power to the back regions, funds are eagerly invested in on-site power generation and photovoltaic power development. In Australia, power supply is monopolized by state governments. Even in Australia, who enjoy 65% self-sufficiency in oil and export a substantial amounts of natural gas and coal, there are enthusiastic efforts at harnessing solar energy. (NEDO)

  12. Report on achievements in fiscal 1999 on research and development of the Welfare Techno-system (Shiga); 1999 nendo Welfare Techno system kenkyu kaihatsu (Shiga) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    Research and development has been performed on a welfare device system that meets the regional needs at the Welfare Techno-house Shiga for the purpose of assisting autonomy in help requiring persons, assisting their social activities, and reducing burdens on helpers. This paper summarizes the achievements in fiscal 1999. In developing a walking action supporting appliance of muscular strength utilizing type, the relationship was investigated between motions of knee joints and muscular output when going up the stairs to perform discussions, experiments and measurements on timing for using auxiliary strength required when the knee joints are bent and stretched. In developing an auxiliary device to support spontaneous movements of lower leg handicapped persons, the standing up motion from the sitting position was analyzed, an action supporting device was designed for the method to help the transfer action, and for transfer actions in vertical and forward-backward directions, and fabrication and experiment were executed thereon. In developing a long-term action and physical condition monitoring system, discussions were given on methods to monitor body action amount and activities in daily life of the subjects, by receiving signals from an acceleration sensor fitted to the front of waist of a subject into a portable digital biological signal monitor. (NEDO)

  13. FY 1991 Report on the results of the research and development of photo-reactive materials; 1991 nendo hikari hanno zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-03-01

    This project is aimed at establishment of the basic technologies for photo-reactive materials capable of, e.g., superhigh-density, superhigh-resolution display using photo-functions to control structures and associated conditions of the molecules. More concretely, the efforts are directed to realization of the technologies for multiplexing, sensitivity-response and material stability, applicable to superhigh-density recording by photochromic and photo-chemical burning (PHB) materials. For the photochromic materials, the long-chain alkyl derivatives of photochromic compounds, e.g., spiropyran and fulgide, are formed into thin films by the LB method, in order to develop organic, superhigh-density recording devices by controlling their associated conditions, and controlling of the photochromism reactions in the films is studied. Those studied for the PHB materials include improvement of heat resistance of the materials, development of quinone-based materials and improvement of their degree of multiplexing, and development of porphyrin-based materials and of technologies for structuring them. The comprehensive survey/research activities include extraction of the problems involved in the themes mainly related to the committee activities, and related technologies. (NEDO)

  14. Achievement report for fiscal 1998 in developing environment corresponding universal controller (Individual report edition); 1998 nendo kankyo taio universal controller no kaihatsu seika hokokusho. Kobetsu hokokuhen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    Research and development has been performed on an 'environment corresponding universal controller (UC)' that realizes 'easiness of use and energy conservation' in correspondence with household electric appliances. This paper summarizes the reports by themes. The summarized development themes include: 'development of a bi-directional controller and TV interface', 'development of a bi-directional remote controller, an infrared ray to radio converter, and an air conditioner corresponding to the bi-directional remote controller', 'development of a UC corresponding air conditioner, and electric power cable transporting gateway', 'development of a universal controller and a control box', and 'development of an energy saving wiring system for the UC remote controller'. This paper also summarizes the works done by research participating departments of each corporation, such as development of UC corresponding video and TV sets (Sanyo Electric), development of UC corresponding TV sets (Toshiba), development of a UC corresponding DVD player (Japan Victor and Victor Techno-brain), and development of a UC relay box and a control box for the existing HA system (PANA R and D). (NEDO)

  15. Fiscal 2000 report on result of project for promoting exchange of international environmental technology information; 2000 nendo kankyo gijutsu kokusai joho koryu sokushin jigyo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    With the purpose of sharing environmental technology information of the APEC countries, the homepage structuring was commenced linking and systematizing the home pages owned by governments, institutions, enterprises, etc., as the APEC Virtual Center (APEC-VC) project, with the fiscal 2000 results reported. In creating the homepage contents, in order to disseminate more useful information for the developing countries, 'Environmental Technology Cooperation for Developing Countries' as the original contents was prepared. In building a search engine, for the purpose of improving convenience for website users of the Virtual Center, APEC VC Japan created a retrieval system on the site. In overseas investigation, the researchers visited local plants to grasp problems and the needs by enterprises and organizations on water-pollution, waste treatment and the like, with the purpose of reflecting the investigation result in the website. In addition, the researchers visited APEC VC coordinators and/or contact points to exchange opinions with the view of expanding the network. (NEDO)

  16. Achievement report for fiscal 1998. Development of Assessment Technology of Life Cycle Environment Impacts of Products; 1998 nendo seika hokokusho. Seihinnado lilfecycle kankyo eikyo hyoka gijutsu kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    An inventory data collecting format is formulated, data collecting activities are launched through 23 industry associations and several investigatory agencies, and almost all the primary data are collected. All the inventory items are being rearranged into a convenient order, and efforts are under way to designate the association to be in charge and the method to be used for data collecting (the accumulation method, process model method). Problems about techniques in the veinous department are extracted. The flow of matters relating to various metals and glass after their use and the magnitude of their environmental impacts at the ultimate sites of treatment are understood though roughly. Investigations are conducted into typical formats overseas, a data arranging format is constructed, specifications are defined for a data inputting software program, and a request is placed with a dedicated dealer for the compilation of the said program. The architecture and specifications of an LCA (life cycle assessment) database system are determined, and its functions are undergoing an intermediate check by a research team for improvement. Endeavors are exerted at quantifying global warming, ozone layer depletion, biotoxicity, and photochemical oxidants for use as the basic data for damage evaluation. (NEDO)

  17. Fiscal 2000 report on result of project for promoting exchange of international environmental technology information; 2000 nendo kankyo gijutsu kokusai joho koryu sokushin jigyo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    With the purpose of sharing environmental technology information of the APEC countries, the homepage structuring was commenced linking and systematizing the home pages owned by governments, institutions, enterprises, etc., as the APEC Virtual Center (APEC-VC) project, with the fiscal 2000 results reported. In creating the homepage contents, in order to disseminate more useful information for the developing countries, 'Environmental Technology Cooperation for Developing Countries' as the original contents was prepared. In building a search engine, for the purpose of improving convenience for website users of the Virtual Center, APEC VC Japan created a retrieval system on the site. In overseas investigation, the researchers visited local plants to grasp problems and the needs by enterprises and organizations on water-pollution, waste treatment and the like, with the purpose of reflecting the investigation result in the website. In addition, the researchers visited APEC VC coordinators and/or contact points to exchange opinions with the view of expanding the network. (NEDO)

  18. Fiscal 2000 report on results of R and D of welfare techno-system in Kochi Prefecture; 2000 nendo walfare techno system kenkyu kaihatsu (Kochi) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    With the purpose of preventing increase in the number of bedridden elderly people, R and D was conducted on equipment for preventing degeneration of walking ability of long bedridden people and a safety device for walking exercise machines, for which the fiscal 2000 results were reported. In the development of the preventive equipment for the degeneration of walking ability, a chain type foot-operated exerciser was experimentally manufactured this year, with test and improvement carried out for the operating characteristics. The test result showed that this exerciser proved to be the equipment as originally intended in the prevention of lumbago, muscle/joint degeneration, etc.. The machine was also found effective for peripheral blood circulation. In the development of the safety device for walking exercise machines, clinical trial tests were conducted on falling and collapsing simulations. The result elucidated that, when a walking exercise machine stopped, a force imparted to the handle by a patient was intensified if the patient had paralysis of one side of the body and that, however, a preventive device installed adjustably to the patient's height was effective against falling. Further, as to collapsing, it was confirmed that, by setting the machine to stop by receiving a load of 20% or more of the body weight, the machine stopped concurrently with the collapsing of the patient. (NEDO)

  19. Report on achievements in fiscal 1999 on research and development of the Welfare Techno-system (Chofu); 1999 nendo Welfare Techno system kenkyu kaihatsu (Chofu) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    Research and development has been performed on a variable type living environment system for elderly people and a system to assist medical welfare and life as a whole for elderly people at the Chofu Welfare Techno-house. This paper summarizes the achievements in fiscal 1999. In the research and development of the variable type living environment system for elderly people, fabrication was performed on the trial basis for a unit to facilitate transfer from a bed to a toilet and taking shower at the toilet seat position. The unit was installed at a hospital in the city of Chiba after discussions and improvements have been made. In the survey and research on welfare devices, for the purpose of serving for selecting welfare devices to be incorporated in variable type welfare houses, surveys were carried out on commercially available welfare devices capable of dealing with daily life actions. Welfare mini-town cases in overseas countries were investigated, taking up the Netherlands, Denmark and the U.S.A. as the object. In the research and development of the system to assist medical welfare and life as a whole for elderly people, design and preparation were carried out on the house terminal information systems and the town management systems. Operation of each information system was verified on a simulated network. (NEDO)

  20. Report on achievements in fiscal 1999 on research and development of the Welfare Techno-system (Kochi); 1999 nendo Welfare Techno system kenkyu kaihatsu (Kochi) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    With an objective to prevent increase of bedridden elderly people, research and development has been performed on a device to prevent retrogression of walking strength in long-term bedridden people, and on the safety device for a walking training machine. This paper summarizes the achievements in fiscal 1999. In developing the device to prevent retrogression of walking strength, a stepping exercising device was fabricated on a trial basis for two types, a hydraulic type and a timing belt type. Operation experiments were carried out. The hydraulic type device has flexibility when making stepping motions, gives good feeling, and operates smoothly. However, it is difficult to achieve the target values for the weight of 70N and the height of 600 mm. The timing belt type device allows reduction in size and weight, but would not operate smoothly if the brake is applied, requiring improvements in various points. In the research and development of the safety device for a walking training machine, discussions were given on a sensing method for the two typical patterns of a patient falling or tumbling down. As a result, a method was discovered, which has a possibility of identifying to some extent how the falling or tumbling is occurring. The existing walking training machines were modified by adding computers and sensors. (NEDO)

  1. Report on achievements in fiscal 1999. System technology to create human life compatible living environment; 1999 nendo ningen kodo tekigogata seikatsu kankyo soshutsu system gijutsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The present research and development is intended to develop the following technology: a system technology to measure, understand and accumulate human activities, analyze objectively the compatibility of human being with products and environments, and support to have the products and working environments comply with activity characteristics of individual persons (a system technology to create human life compatible living environment). Human activities are developed in various scenes, and it is not easy to structure technologies to measure, understand and support the activities common to all of the scenes. Therefore, development will be made on the technologies for measuring, understanding and supporting the activities in the human activity scenes. Development of the manipulative activity complying technology deals with human activities in the scenes to operate devices by which the activities are changed by situation identification and skills in addition to activity characteristics of individual persons. Furthermore, as a scene in which attention to the activity characteristics of individual persons, skills, and external situation is a problem, the automobile driving activities are taken up for discussion, as well as the object building work activities as a scene in which difference in skills of individuals is a problem. (NEDO)

  2. FY 1996 report meeting on the achievement of sending Japanese RITE researchers overseas; 1996 nendo RITE kokunai kenkyusha kaigai haken seika hokokukai

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    In the report meeting, papers on the following were made public: 'Study of catalytic reaction removal technology and reaction mechanism of global warming substances such as N2O' given by Mr. A. Kushiyama sent to Swiss Federal Institute of Technology Zurich, Switzerland, and 'Study of proteins which are concerned with transport of biological membrane' given by Mr. M. Hara sent to Uppsala University, Sweden. In the former, examined were decomposition/oxidation reaction of tert-butyl compounds on various kinds of catalysts using a fixed bed normal pressure flow reactor equipped with FTIR, and selective reduction reaction of N{sub 2}O using these as reducing agent. As a result, it was found that under SCR reaction conditions, t-CNO is easily decomposed to tert-butyl amine through the isomerization to the correspondent tert-butyl isocyanate and further to isobutene and NH3 and also that isocyanato group of t-NCO and N2O easily react. In the latter, as to membrane proteins which play an important role in biological energy conversion system, especially proteins having transport activity such as electron, proton and amino acid, studied was appearance of the functions by solubilizing and separating the proteins, and restructuring them into liposome. (NEDO)

  3. FY 1995 report on the results of the R and D of biodegradable plastics; 1995 nendo seibunkaisei plastic kenkyu kaihatsu seika hokokusho. Ippan kokaiyo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    For the development of biodegradable plastics, the paper made studies on the following items: 1) development of biodegradable plastics through the cultivation of plastic-like polymer producing micro-organisms; 2) development of biodegradable plastics using polysaccharides; 3) development of biodegradable plastics using molecular design/precise polymerization technology. In 1), P of 4HB fraction 10% was biosynthesized in 5L scale and in one stage by giving to fungus body the {gamma}-butyrolactone which was heated/hydrolyzed. In the study of PHB production by gene recombination of algae, the promoter is improved, and it was confirmed that PHB synthetic genes were surely introduced. PHB could be produced 25% by cultivation of acetic acid. In 2), using alkali protease as enzyme catalyst, sugar ester monomer was synthesized from glucose, sucrose and maltose. In 3), effects were grasped of polymerization conditions of succinic acid/1,4-butane diol/carbonate on the molecular weight and reaction velocity. A test on degradability was conducted by the enzyme method to study the structure of olygomer, in particular. Biodegradation of polyurethane was assessed by soil suspension. (NEDO)

  4. FY 1997 research and development of fusion domains. Part 2. Studies on bionic design; 1997 nendo seika hokokusho (yugo ryoiki kenkyu kaihatsu). 1. Bionic design no kenkyu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    Studies were conducted on actuator function in bio materials, cells, structures, and living organisms, and on structuring a biological molecule machine. In the study on soft biological structures, biological compatibility of artificial glass bodies using ultra-polymeric PVA was found very high, raising expectation on feasibility of their practical use. Three-dimensional structure of glass bodies was made clear for the first time in the world. As a result of separating and purifying cells from a liver for the first time in the world, it was indicated that excellent proliferation performance and differentiation into cells are shown. With regard to hydroxyapatite in hard biological structure such as bones and teeth, single crystals were synthesized, and growth rate on the surface C was measured successfully. For molecular motors, studies are being performed on functions of twin-head structure in biological protein enzyme. In molecule structuring, studies were conducted on preparation of a hydrogenase LB membrane as an electric-hydrogen energy conversion element, and structuring of protein molecular structure using gene recombination. 69 refs., 37 figs., 8 tabs.

  5. FY 1998 report on achievements of the verification survey on a new method for load leveling; Fuka heijunka shinshuho jissho chosa 1998 nendo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    An electrically double-layered capacitor is drawing attention as a new power storage technology that can contribute to power load leveling. The issue is to make the capacitor more compact by enhancing energy density. Discussions to improve the energy density are being given on a method by which internal resistance combined with that in electronic circuits may be allowed to some extent. In addition, in order to verify feasibility of its practical use, investigations are made on the optimal operation pattern of the system, possible quantity of introduction, effect of the introduction, and future possibility to reduce the cost. As demonstration of the element technology used in capacitor modules, fiscal 1997 fabricated 35 single cells each with a volume of one liter, and investigated the positioning at practical application, case studies, and operation patterns. Based on the achievements in fiscal 1997, fiscal 1998 performed fabrication and performance test on a capacitor module in which multiple number of cells are connected, and trial fabrication of a next generation type high-energy density capacitor. In addition, as a study on a total system, discussions were given on design and cost estimation of a hybrid type capacitor which combines the capacitor with a NAS battery. (NEDO)

  6. Fiscal 1997 report on the results of the verification survey of a new load leveling method; Fuka heijunka shinshuho jissho chosa (1997 nendo seika hokokusho)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    A study was conducted of a practical applicability of the electric double layer capacitor as a new electric power storage technique. In the study, a comparison was made between the capacitor system and the NAS battery which is most commercialized as one for power storage of all the secondary batteries. The capacitor system is excellent in cycle life, system efficiency, and safety/environment, but in energy density it is approximately a tenth of that of the NAS battery so far. The capacitor system, however, is high in filling rate in modules and enables compact design. As to the 35 fabricated electric double layer capacitor cells, the following tests were carried out: charge and discharge, internal resistance measurement, energy density measurement, characteristics of charge/discharge efficiency, self-discharge characteristics, and characteristics of circumferential temperature. As a result of the tests, the cell with volume energy density of 16.4-16.8 Wh/L was fixed to the module with a filling rate of about 93% and achieved an energy density of 15 Wh/L. 26 refs., 175 figs., 75 tabs.

  7. Fiscal 2000 report on result of the full-length cDNA structure analysis; 2000 nendo kanzen cho cDNA kozo kaiseki seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    This paper explains the results of research on full-length cDNA structure analysis for the period from April, 2000 to March, 2001. The outline of human genome sequence was published in June, 2000. In Japan, human gene analysis was such that, as the basic technology of the bio industry, a millennium project was decided in the budget of fiscal 2000. The full-length cDNA structure analysis is the core of the project. The libraries of cDNA were prepared using full-length and more than 4-5kbp-long cDNAs by oligo-capping method. It began from determining partial sequence data at end cDNA, and then, with new clones selected therefrom, full-length human cDNA sequence data were determined. The partial sequence data determined by fiscal 2000 were 1,035,000 clones while the full-length sequence data were 12,144 clones. The sequence data obtained were analyzed by homology search and translated into amino acid coding sequences, with predictions conducted on protein functions. A clustering method was examined that selects new clones from partial sequences. Database was constructed on gene expression profiles and disease-related gene sequence data. (NEDO)

  8. Achievement report for fiscal 1998. Development of next-generation chemical process technologies; 1998 nendo jisedai kagaku process gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Researches are conducted on the development of a technology of catalytic cracking of naphtha, technology relative to selective oxidation reaction of saturated hydrocarbons, process technology utilizing solid-phase reaction field, and a process technology utilizing novel reaction mechanism. Also, a survey is conducted on chemical processes of the next generation. Concerning the catalytic cracking of naphtha, reaction systems are roughly divided into two groups by whether or not they proceed in the presence of oxygen. As for rare earth oxide catalyst systems and zeolitic catalyst systems, their performance is confirmed and their reaction mechanisms are estimated. Concerning the selective oxidation reaction of hydrocarbons, studies are made to enhance the performance of catalytic systems that have been selected in researches conducted in the past. Concerning the process of solid phase reaction field utilization, the project is summarized and a concept is constructed of 'solid phase catalyst.' Concerning novel reaction mechanism utilizing process technologies, development is discussed of a novel process using membrane reactor, a highly functional hydrogen permeable membrane, a low-temperature dehydrogenation catalyst, etc., and a dehydrogenation membrane reactor is experimentally built. (NEDO)

  9. Achievement report for fiscal 1998 on Welfare Technosystem Ube research and development; 1998 nendo Walfare technosystem kenkyu kaihatsu (Chiba) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Research is conducted into burdens to be imposed on the nurse and the attended person during nursing activities and into measures to lighten such burdens, and basic data are collected about physical strains to be produced when raising a patient on the bed, pushing a wheelchair, and about stool shapes appropriate for the aged. In a study about escape from a disaster, many shortcomings are discovered requiring remedy, such as difference in height and doors failing to open in case of power outage. For communication in case of emergency, it is concluded that the most promising method will be a combination of a mobile computer and handyphone system. A photoelectric pulse wave monitoring system and an acceleration sensor-equipped water bed, on which the patient lies unrestrained for the measurement of heartbeats and respiration waveforms, are developed. A concept wheelchair is under development which will be a 2-motor 4-wheel design, to be equipped with a steering wheel and a vertically movable seat which will facilitate boarding and alighting. Many projects are in store for fiscal 2001, which include the development of a system to ensure sitting position stability and an automatic pressure belt for the prevention of orthostatic hypotension. A multiple function bed is under development for domestic use, which will be provided with a discharge system (automatic toilet) whose mechanism is quite sophisticated. (NEDO)

  10. Reports on 1979 result of Sunshine Project. Research on solar energy system (meteorological investigation); 1979 nendo taiyo energy system no kenkyu seika hokokusho. Kisho chosa

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-03-31

    The following were implemented with the purpose of collecting, measuring and putting in order the meteorological data required for the R and D on solar energy technology. (1) Observation of direct solar radiation (Nagoya/Sendai), (2) Meteorological observation for the pilot plant site of 1,000kW solar thermal power generation, (3) Studies on estimation of quantity of direct solar radiation, and (4) Studies on characteristics of quantity of direct solar radiation. In (1), the summary and the results were explained on the continuous observation of the quantity of the direct solar radiation conducted in Nagoya and Sendai using a self-recording actinometer. In (2), meteorological observation was conducted for building lots reclaimed from a salt pan at Nio-cho, Mitoyo county, Kagawa prefecture, a scheduled site for the pilot plant. The items were the quantity of global solar radiation, quantity of sky solar radiation, quantity of direct solar radiation, temperature, wet-bulb temperature, wind direction and wind velocity. In (3), A method was developed for estimating the monthly average quantity of the global solar radiation, normal direct solar radiation, horizontal sky solar radiation at an arbitrary spot. In (4), the characteristics of direct/specified direct solar radiation flux curves were elucidated as the basic data for the technological development of solar energy utilization using a sun follower type heat collecting device, with research done on a method for estimating these curves from other meteorological factors. (NEDO)

  11. Fiscal 2000 report on results of R and D of welfare techno-system in Shiga Prefecture; 2000 nendo walfare techno system kenkyu kaihatsu (Shiga) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    R and D was conducted on systems and technology for realizing desirable at-home nursing care in the coming super aging society, with the fiscal 2000 results reported. In the development of a muscle using type walking frame, a device was developed using mechanism of the functional element. As a result, it was found that the device was operable through a normal movement pattern, and that the torque generating by the human body side was uniformly reducible, enabling the load to be alleviated physiologically. In the development of a lower extremity orthosis for self-sustained movement, a rising motion from a seated position was observed, with a transfer motion analyzed, leading to the examination of the supporting method and the design/manufacturing of an orthosis for transfer movement. In the development of a monitor system for a long-term behavior and physical condition, an uninvasive unrestrictive earring type pulse wave sensor system was experimentally manufactured as a monitor for heart activity, particularly, for heartbeat fluctuation. This monitor was integrated with the physical activity monitoring device developed in the previous year, with a simultaneous measuring experiment performed for elderly people in their daily life. (NEDO)

  12. Achievement report for fiscal 1998 on Welfare Technosystem Kobe-Chuo-Ku research and development; 1998 nendo Walfare technosystem kenkyu kaihatsu (Kobeshi Chuo-ku) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Research on the transmission and management of information on those who necessitate nursing care will lead to the development of computer-aided nursing and welfare supporting systems and this in turn will help businesses who provide aged people with service they require for the enhancement of nursing care at home and at facilities for aged people to enjoy independent, unaided living. It is important to prepare liaising methods and coordinate with physicians in case of physical condition suddenly turning worse. Exchange of data at a visited place is important for a visiting nurse, and handling of information on such an occasion has to be easy and rapid to ensure high efficiency. When transmitting or receiving data on patients via PHS (personal handyphone system) or handyphone system, transmission of large-capacity data such as pictures should be avoided. In case a picture has to be transmitted, it should be compressed. ISDN (integrated services digital network) is preferred in all cases. The IEEE1394 interface is deemed to be the best for automatically transmitting as digital data the pictures etc. collected from other measuring instruments on nursing welfare and nursing assisting systems. It is necessary, however, to watch the development of digital interfaces in the future. (NEDO)

  13. Fiscal 1981 Sunshine Project research report. Research on underground reinjection mechanism of hot water; 1981 nendo nessui no chika kangen mechanism no chosa kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-03-01

    This report summarizes the fiscal 1981 research result on the behavior and flow mechanism of underground reinjected hot water, and the effect of reinjected hot water on the ground. In the tracer survey in Takinoue area, Iwate prefecture, the re-upwelling rate and mixing rate of reinjected hot water were lower than those in previous surveys, showing the smaller effect of hot water on productivity. In Nigori-Gawa area, Hokkaido, natural conditions prior to industrial production and reinjection were observed by tracer survey. In the simulation research, it was confirmed that the hydraulic structural model and analysis technique established by previous researches are effective for new production and reinjection systems different from previous ones enough. On observation of minute earthquakes, study was made on the effect of reinjected hot water on the ground in Takinoue area. In Nigori-Gawa area, the data were collected under natural conditions prior to industrial production and reinjection through minute earthquake observations. (NEDO)

  14. Fiscal 1998 'Plant Biotechnology in the 21st Century' workshop report; '21 seiki no shokubutsu biotechnology' workshop 1998 nendo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The workshop was opened with the opening remarks by Yamada (President of Nara Institute of Science and Technology (NIST)), the overview of plant biotechnology in the 21st century from academia by Shinmyo (Professor of NIST), and the overview of such technology from Ministry of International Trade and Industry by Katao (Chief of Chemical Industry Division). Lectures and discussions of various topics were conducted for 2 days as follows. The effectiveness of a genomic DNA array method for obtaining the genes for switching genes according to daytime, nighttime, drying, salt, high temperature and low temperature for every plant. Current transfer technology of large DNA fragments into plant cell nuclei and chloroplast. Biological evaluation of the physiological functions and complex stress tolerance capacity transformed by transferring complex stress tolerance genes and useful genes for productivity improvement and value addition. Discussion was also held on the importance of a basic research for biotechnology in the 21st century. (NEDO)

  15. Collection of summaries of Sunshine Program achievement reports for fiscal 1982. Hydrogen energy; 1982 nendo sunshine keikaku seika hokokusho gaiyoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-04-01

    The collection includes achievements of research relating to hydrogen energy. In the research on hydrogen production by electrolysis, electrolysis of water using an acid-type solid polymer electrolyte and electrolysis of water using an alkali-type solid polymer electrolyte are taken up. In the research on hydrogen production by thermochemical methods, studies are conducted on the iodine-based cycle, the bromine-based cycle, materials for devices for the iodine-based cycle, and the mixed cycle. Hydrogen production using high-temperature direct thermolysis and solar radiation is also studied. In the research on hydrogen transportation and storage, use of metallic hydrides in these processes are taken up. In the research on the application of hydrogen, techniques of hydrogen combustion and hydrogen-fueled engines are discussed. In the research on hydrogen safety measures, technologies for the prevention of hydrogen explosions and of hydrogen embrittlement of materials in use with hydrogen are studied. In addition, a study is conducted of a hydrogen energy total system, and research and development is carried out for a plant that produces hydrogen by high-temperature high-pressure electrolysis of water. (NEDO)

  16. 1998 Annual Study Report. Standardization of methods for measuring fuel economy of hybrid electric vehicles; 1998 nendo seika hokokusho. Hybrid denki jidosha no nenpi sokutei hoho no hyojunka

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The hybrid electric vehicle (HEV) has been attracting attention as a clean energy vehicle, because it will potentially show higher fuel economy and release smaller quantities of exhaust emissions than the conventional internal combustion engine, and also will be potentially advantageous over the electric vehicle in that it needs no charging infrastructures and less cost. However, there are many types of hybrid vehicle systems, and, for them to be commercialized on a large scale, it is urgently necessary to establish the fuel economy measurement method. The 1998 R and D efforts were directed to analysis of the effects of the hybrid-characteristic factors (SOC of the propulsion battery and regenerative braking) on fuel economy and exhaust emissions. As a result, it is found that changed SOC before and after the tests must be corrected to determine fuel economy and that it is possible. The method for measuring the effects of regenerative braking should be further developed, because the data collected while the vehicle is running on road and on a two-wheel chassis dynamometer are not clearly distinguished from each other. The exhaust emissions are also sensitive to the changed SOC, correction for which, however, is not as easy as that for fuel economy. (NEDO)

  17. 1998 Annual Study Report. Standardization of image processing for digital home equipment; 1998 nendo seika hokokusho. Kateiyo digital denshi kiki ni okeru digital gazo shori no hyojunka

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The electronic industry should invariably correspond to MPEG-4, when considering the essential conditions for home information equipment of the next generation to be used massively. This project is aimed at formulation of the standard platform for MPEG-4, and identification of the necessary examples and corresponding the necessary tools/functions thereto, to give an impetus for the future development, and to positively provide the additional aids to the tools which strengthen MPEG-4 in the arena of promoting the international standardization. The efforts in this year began with investigations on the assumption of the concrete application examples, considered from the standards' structures, and were concentrated on investigations on characteristic problems involved in each of the system, server and client blocks which constitute the system, and then on identification of the products application, based on the analysis of the MPEG-4 profiles and levels. These have led to selection of an MPEG-4 receiver as the case study item for extracting problems possibly involved in assembling works. (NEDO)

  18. Achievement report on commissioned research of R and D in fiscal 2000 on micromachine technologies. Development of microfactory technology; 2000 nendo kenkyu seika hokokusho. Maikuro fakutori gijutsu kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-04-01

    In order to achieve energy saving by miniaturizing the manufacturing process of small industrial products, R and D has been carried out on a micromachine system that puts together and assemble such devices as for processing, assembling, transportation and inspection used in the manufacturing process. This paper summarizes the achievements in fiscal 2000. In the research of a prototype micro-processing and assembling system, the secondary prototype system was fabricated, and verification was performed on its operation in processing and assembling works of a very small gear train. In the research of a micro liquid manipulating technology, high function liquid delivering device and holding device were developed, whereas the achievement of the targeted specifications was identified. In the research of a micro assembling technology, processing accuracy was improved on micro encoder disks. Furthermore, two second prototype micro arms were assembled into a microfactory to have performed verification on continuous operation to assemble trains of gears with a diameter of 10 mm. Other researches included the micro beam driving technology, micro electric power driving technology, micro transporting technology, and micro inspection technology. (NEDO)

  19. FY1998 research report on the R and D on recycling technology. Part 1; 1998 nendo recycle nado kankyo gijutsu kekyu kaihatsu seika hokokusho. 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    This project aims to develop recycling technology for reduction of environmental burden caused by waste, and promotion of recycling of wastes. As for advanced recycling technology for PET bottles, the facility was improved for improvement of a facility operability and product quality. Study was made on the effect of a raw bale quality and recycled flake colors on a product quality, the forming test with PS or PET labels, and the concentration and effect of washing liquid circulated in flake washing process. As for recycling technology of hard-to-dispose waste plastics, facility improvement and demonstration test were made for continuous operation of dry-distillation/gasification of shredder dusts and separation of nonferrous metals and glass. Study was also made on pulverizing and recycling technologies of FRP bath tubs, and such pulverization costs were estimated. As for production technology of chemical feed and fuel from wastes, study was made on removal technology of non-flammable substances, development of alkaline additives, reacting condition, development of reactors, and use technology as chemical feed. (NEDO)

  20. Fiscal 1998 achievement report. Research and development of advanced clean energy vehicles; 1998 nendo kokoritsu clean energy jidosha no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The efforts aim to develop advanced clean energy vehicles (ACEVs) which drive on substitutes of oil low in pollution, consuming 1/2 or less energy and emitting 1/2 or less CO2 than the existing vehicles. Studies conducted in fiscal 1998 covered high-efficiency hybrid power systems and ACEVs. Efforts to develop ACEVs involved a reformed methanol fuel cell hybrid passenger car of Nissan Motor Co., Ltd. (improvement on element technologies, study of methanol concentration); CNG (compressed natural gas) engine hybrid passenger car of Honda Research and Development Co., Ltd. (improvement on flywheels, studies of ANG (adsorbent natural gas) adsorbent and ANG tank); CNG ceramics engine hybrid cargo truck of Isuzu Ceramics Research Institute Co., Ltd. (fabrication of ceramics single-cylinder engine, design and fabrication of vehicle control system, fabrication of prototype); CNG lean burn engine hybrid cargo truck of Mitsubishi Motors Co., Ltd. (studies, designing, and fabrication of engine element parts); LNG engine hybrid bus of Nissan Diesel Motor Co., Ltd. (development of engine and power storage); and DME (dimethylether) engine hybrid bus of Hino Motors, Ltd. (development of DME fuel injection system and high-efficiency power storage). (NEDO)

  1. 1998 Annual Study Report. Standardization of manufacturing process systems; 1998 nendo seika hokokusho. Seisan process system no hyojunka (STEP kiban kikaku no kaihatsu)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The standards for exchanging and sharing product model data are being internationalized, mainly by ISO-10303 (STEP). The current specifications are not fully developed to include all of the functions needed by the industrial circles, e.g., the functions capable of expressing dynamic product models useful for design alterations and manufacturing processes. In order to solve these problems, and, in particular, to propose the specifications which meet the functions required by the domestic industries, the necessary conditions which the STEP basic specifications should satisfy are investigate to propose the Japan-developed international specifications. One of the major results of the efforts in this year is development of the functional model (I-AAM) which allows to analyze the functions to be proposed for the specifications for the mechanical production processes in the Japanese industries. The necessary data model candidates can be selected by the aid of the model. The efforts will be further continued in and after the next year, based on the results obtained in this year, to eventually develop the specifications which can be registered by NWI. (NEDO)

  2. FY 1999 research and development results. Technological development of superconducting power storage systems; Chodendo denryoku chozo system gijutsu kaihatsu 1999 nendo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The research and development project is implemented for technological surveys on the superconducting power storage system (SMES) for cost reduction and high-temperature SMES, and the FY 1999 results are reported. The SMES cost analysis/evaluation program establishes the (basic flow for cost analysis/evaluation) for cost evaluation. The program for the SMES systems for system stabilization sets the specifications of 100MW as output and 15kWh as storage capacity at the generator end and intermediate switching station. The program for SMES systems for load fluctuation compensation and frequency control sets the specifications of 100MW as output and 500kWh as storage capacity at the installation site as the load end, and the investigation of high-temperature SMES technology is conducted on the conceptual designs of the SMES for system stabilization application (100MW, 15kWh) of toroidal coil type. The optimization designs are made for these systems. The investigation of the technology for high-temperature superconducting wires involves fabrication on a trial basis and evaluation for the characteristic evaluation coils, and characteristic measurement and applicability investigation for the large-current short conductor. (NEDO)

  3. Achievement report for fiscal 1990 on research and development of highly crystalline polymeric materials; 1990 nendo kokesshosei kobunshi zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-03-01

    Activities were performed to seek polymeric materials having mechanical strength comparable to metallic materials as a result of giving contrivance on the composition and processing method, and bending strength of 100 GPa or more. The activities were taken in the following five fields: (1) a one-dimensional system material, (2) special melting and forming of a multi-dimensional system, (3) compound forming of multi-dimensional molecules, (4) hybrid cross-linking of cross-linking systems, and (5) high-density cross linking of cross-linking systems. In Item (1), researches were made on optimization of the structures, and elongation and fluid processing of thermotropic liquid crystal polyacrylate, wherein the objective was achieved. In Item (2), the objective was achieved on poly (imide-benzobisthiazole) by monoaxial drawing and lamination thereof. Discussions were given on the liquid crystal polymer as to its correlation between the structure and the magnetic field orientation. In Item (3) discussions were given on the composition and processing method for molecule compounded materials reinforced by aromatic polyamide matrix-polyphenylenebenzothiazole. In Item (4), ionomers were discussed. In Item (5), discussions were given on multi-functional diacetylene system and diacetylene group containing polyimide. (NEDO)

  4. Report on the coal energy achievements in the Sunshine Project in fiscal 1988; 1989 nendo sunshine keikaku seika hokokusho. Sekitan energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-01

    This paper describes the achievements in the Sunshine Project in fiscal 1988 in studies on coal liquefaction. The liquefaction mechanisms may be conceived to work in the following three manners: radicals produced by spontaneous bond and cleavage of coal molecules draw out hydrogen from the donor and stabilize it; bond, cleavage and stabilization due to hydrogenation from the donor to coal aromatic nucleus; and cleavage and stabilization due to work of active hydrogen discharged from the donor. How these mechanisms contribute to composition of the products depends on coals, liquefying conditions, and reactivity of the donor. Selection of the donor solvent requires design by which high liquefaction yield can be obtained with small amount of solvent. The oil plus asphaltene yield could have been approached to the ideal value through the moving liquefaction of gaseous phase hydrogen and catalyst-free hydrogen, with the 4HFL to coal ratio at 1.5 to 1. The gaseous phase hydrogen was found effective in reducing 4HFL. Liquefaction residual oil manufactured from Morwell brown coal subjected to BCL was hydrogenated in single stage or two stages to compare and discuss the solvent sorting constituents, reactivity of CLVR, and how the catalytic activity deteriorates. The cause for the catalyst deterioration was elucidated, and considerations were given on catalysts and reaction conditions for lightening and refining of CLVR. (NEDO)

  5. Fiscal 1976 Sunshine Project result report. Research on solar energy utilization systems (solar heat power generation); 1976 nendo taiyo energy riyo system chosa kenkyu seika hokokusho. Taiyonetsu hatsuden

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-03-01

    Research was made on solar heat power generation following last fiscal year, as a part of solar energy utilization technologies. In this fiscal year, in particular, research was made on the following: selection of suitable sites for solar heat power plants in Japan, estimation of expected power supply, positioning of a solar heat power system among future power systems, operation policy of solar heat power systems, survey on suitable sites for the 1,000kW pilot power plant, operation characteristics of the small test plant, design of the 1,000kW pilot power plant, test methods and facilities for every element equipment of solar heat power systems, an environmental test method for mostly solar collectors, and the profitability of solar heat power systems. Optimum operation temperature levels were nearly 350 degrees C for distributed systems and nearly 400 degrees C for centralized ones. The distributed system is profitable in a unit capacity range less than 5-10MWe, while the centralized system is profitable in a range over 10MWe. Under some assumptions, the power cost of solar heat power systems was estimated to be 20-30yen/kWH. (NEDO)

  6. Fiscal 1998 R and D report on environment-friendly hydrogen production technology; Kankyo chowagata suiso seizo gijutsu kenkyu kaihatsu 1998 nendo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    For efficient oil-free environment-friendly production of hydrogen necessary for oil refining process and effective use of CO{sub 2}, this project develops the efficient hydrogen production techniques by using a capacity of microorganisms. On the R and D on improvement of screening and breeding for photosynthetic microorganisms, introduction of different hydrogenases, acquisition of hydrogen uptake negative strains, control of photosynthetic pigment expression, breeding of PHB synthesis negative strains were carried out continuously, and some problems were arranged confirming the contribution to increasing a hydrogen production capacity. On the R and D on large-scale cultivation techniques, engineering data were collected by using a module continuously. Based on the engineering data collected by the module test, the feasibility study was made on a possibility as industrial technology from the viewpoint of a profitability and environmental harmony. Screening of bacterial strains suitable for 4 kinds of wastewater and capable of producing hydrogen under extreme conditions, and basic studies on photoreactor and cultivation technique were conducted by outside research organizations. (NEDO)

  7. Achievement report for fiscal 1990 on research and development of electrically conductive polymeric materials; 1990 nendo dodensei kobunshi zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-03-01

    It is intended to realize new electrically conductive materials characterized by light weight, corrosion resistance and easy-to-process performance, and electrical and electronic materials having functions different from those of metallic conduction mechanism. Therefore, activities were performed to seek technologies for polymeric materials having conductivity greater than 10{sup 5} S/cm and being stable and easy to process. Activities were taken in the following six fields: (1) new hydrocarbon conjugate polymers, (2) excipient conjugate conductive materials, (3) technologies to form thin films of graphite synthesized at low temperatures, (4) conductive polymers of hetero aromatic system, (5) research and development of conductive materials of the hetero containing system and the {pi} conjugate system, and (6) comprehensive investigative research. In (1), thin films of polyacetylene and polyacene systems were formed, in (2), excipient hydrocarbon conjugate polymers and excipient graphite materials were developed, in (3), a high-accuracy process controlled graphite thin film forming technology was developed, in (4), the conductivity was enhanced by using high-order structural control and molecular design, and stability of the conductive polymers of complex annular conjugate system was enhanced, and in (5), conductive polymers of the hetero containing system and the {pi} conjugate system, and flexible graphite fibers were developed. (NEDO)

  8. Achievement report for fiscal 1998. Development of next-generation chemical process technologies; 1998 nendo jisedai kagaku process gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Researches are conducted on the development of a technology of catalytic cracking of naphtha, technology relative to selective oxidation reaction of saturated hydrocarbons, process technology utilizing solid-phase reaction field, and a process technology utilizing novel reaction mechanism. Also, a survey is conducted on chemical processes of the next generation. Concerning the catalytic cracking of naphtha, reaction systems are roughly divided into two groups by whether or not they proceed in the presence of oxygen. As for rare earth oxide catalyst systems and zeolitic catalyst systems, their performance is confirmed and their reaction mechanisms are estimated. Concerning the selective oxidation reaction of hydrocarbons, studies are made to enhance the performance of catalytic systems that have been selected in researches conducted in the past. Concerning the process of solid phase reaction field utilization, the project is summarized and a concept is constructed of 'solid phase catalyst.' Concerning novel reaction mechanism utilizing process technologies, development is discussed of a novel process using membrane reactor, a highly functional hydrogen permeable membrane, a low-temperature dehydrogenation catalyst, etc., and a dehydrogenation membrane reactor is experimentally built. (NEDO)

  9. Report on the research achievements in the Sunshine Project in fiscal 1992. Studies on a direct gasification catalyst; 1992 nendo chokusetsu ekika shokubai ni kansuru kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-10-01

    This paper describes the research achievements in the Sunshine Project in fiscal 1992 in studies on a direct gasification catalyst. The paper summarizes the points where the catalyst research has reached to date. The catalyst surface effective for hydrogenation is the metal surface that can dissociate hydrogen. However, metals having large adsorption heat against hydrogen do not show the activity greatly because these metals are difficult of desorbing hydrogen having high dissociating activity. The coal liquefaction system has the surface oxidized by water content, wherein hydrogen dissociation cannot be expected, and sulfides are suitable. When a sulfide catalyst contacts hydrogen, the catalyst itself is desulfurized, producing H{sub 2}S and becomes a low-order sulfide. When atmospheric H{sub 2}S contacts this sulfide, it dissociates into HS and H, and this H behaves as active hydrogen. However, the liquefaction activity can be recognized even in a sulfuric acid type catalyst containing no sulfide whatsoever, wherein the H{sub 2}S partial pressure in the reaction system becomes extremely low. This fact means that the active hydrogen is not necessarily generated by the dissociation of H{sub 2}S. There is no other way but to think that hydrogen is dissociated directly without going through H{sub 2}S. If this is true, it provides a new guideline in developing and designing the future catalysts. (NEDO)

  10. Fiscal 1974 Sunshine Project result report. Research on solar energy utilization systems (total system); 1974 nendo taiyo energy riyo system chosa kenkyu seika hokokusho. Total system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-03-01

    The current most important solar energy utilization fields are solar energy power generation (solar heat and photovoltaic power generation), and solar heat cooling and heating. A solar heat power system collects or stores solar thermal energy as energy source of power systems, and converts it to electric power through heat exchange systems. To establish such system, not only R and D on a collector, absorption capsule, storage unit and heat transfer unit, but also complete study on an optimum system configuration and environmental impact are necessary. A photovoltaic power system converts solar energy to electric power directly by photoelectric conversion device such solar cell. Except specific local uses, drastic cost reduction and improvement of a conversion efficiency (at present 12-15%) and life (several years) are necessary for solar cells. Although a lot of solar heat cooling and heating systems is in practical use in Japan, for its further diffusion an important research task is development of heat collector excellent in efficiency, cost, life and maintainability. (NEDO)

  11. Japan`s New Sunshine Project. 1994 annual summary of solar energy R and D program; 1994 nendo new sunshine keikaku. Seika hokokusho gaiyoshu (taiyo energy)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    The paper reported the results of fiscal 1994 studies on solar energy in the New Sunshine Project. Relating to the technical development for the practical use of photovoltaic power systems, the development of manufacturing technologies for low-cost substrates and the development of element technology for manufacturing low-cost polycrystalline cells/modules were reported as the development of technology for thin substrate polycrystalline solar cells for practical use. As to the research on fabrication technology for thin film solar cells for practical use, reports were made on the research on low-cost fabrication technology for large-area modules and the technological development for qualitative improvement, etc. In respect to the technological development for super-high efficiency solar cells, reported were the technological development for super-high efficiency single crystalline silicon solar cells and the technological development for crystalline compound solar cells, etc. Concerning the research and development of photovoltaic power systems, reports were on the characterization and control of surface/interface recombination velocity of crystalline silicon thin films and the research on surface passivation for high-efficiency silicon solar cells, etc. In regard to the utilization technology of solar thermal energy, the energy conversion technology using chemical reactions and the development of chemical refrigeration and cold storage systems using solar heat were reported as the research and development of utilization technology of solar thermal systems for industrial use.

  12. Fiscal 1998 research achievement report. Research and development for acceleration of biological resource information infrastructure construction; 1998 nendo seibutsu shigen joho kiban seibi kasokuka kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    To fulfill the above-mentioned purpose, research and development of technologies were carried out involving genetic information measurement, genetic information analysis and utilization, analysis and utilization of information on proteins, and the measurement of biomolecular interaction. In a chapter 'Research and development of genetic information analysis using next-generation genome chip,' gene amplification is effected using RNA-DNA molecules and a method for efficiently building UPD (unilateral protruding DNA) was developed. In a chapter 'Development of international standard DNA chip and analyzing system for analysis of massive gene expression,' a relational database program for activating a system for gene preservation, purification, multiple injection, and management was completed. In a chapter '3D-1D modelling of all the proteins coded on genomes,' this fiscal year, analyses were conducted using Escherichia coli and Bacillus subtilis as model microbes. In a chapter 'Analysis of gene expression clustering,' a software program was developed for measuring and analyzing the budding yeast gene expression profile. (NEDO)

  13. Report on achievements in fiscal 1999 on research and development of the Welfare Techno-system (Shizuoka); 1999 nendo Welfare Techno system kenkyu kaihatsu (Shizuoka) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    Research and development has been performed at the Shizuoka Welfare Techno-house to assist entry into the welfare industry field of the local industries in the prefecture, such as for wood products, furniture and music instruments, and to provide products which take into consideration the society with more elderly people and less children. This paper summarizes the achievements in fiscal 1999. In developing barrier-free kitchens capable of handling change in bodily functions, a prototype kitchen was used to evaluate work load variation as a result of existence of a foot space under the kitchen table. In addition, a human simulation software was used to evaluate compatibility of humans with products. By utilizing these technical data, a system was arranged by which barrier-free kitchens can be commercialized by changing the specifications according to individual requirements. In developing a bed unit to prevent bedsore by using the multi-point pressure and fluctuation mechanism, the unit weight was reduced, and addition was made to such functions as controlling finger-pressing cycle and positions by electronic control. Development was made on a music instrument for rehabilitation by which anyone can play music by repetitively giving stimulation to human eyes and ears. (NEDO)

  14. Report on achievements in fiscal 1998. Development of a technology to measure biological molecular interactions; 1998 nendo seitai bunshi sogo sayo no keisoku gijutsu no kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    It has been indicated possible in principle in recent years to measure biological molecular interactions with the molecules in the living state by combining the technologies called the co-focussing optical system and the fluorescence correlation spectroscopy (FCS). The FCS method is a method capable of analyzing concentrations, sizes, and inter-molecule interactions through detection of fluorescence fluctuation in single molecules in submicron zones. In spite of the FCS method being a very effective method to measure interactions in biological molecules, the technology has not reached a level that allows easy utilization under the present condition. The present research and development is intended to solve the technological problems in the FCS method in the co-focussing optical system, and perform as many research and development works as possible in a short time to establish a technological foundation that can be provided to bio-industrial and medical sites. Particularly, in order to make the utilization thereof possible in measuring biological molecular interactions in cells, a measuring technology using the bi-photon excited fluorescence correlation spectroscopy was established with an objective to reduce damages to cells and their internal micro organs, and minimize effects of interference signals from the own fluorescence. (NEDO)

  15. Achievement report for fiscal 2000 on development of technology to recycle disintegrated waste gypsum boards; 1999 nendo kaitai haisekko board no saishigenka gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Investigations and researches have been made on disintegrated waste gypsum boards generated in building demolishing sites, with a target of recycling them as a raw material for boards. In the investigations, the actual status of discarding the disintegrated gypsum boards was identified, whereas the harmful substance contents such as of heavy metals were verified to be below the environmental criteria. As a method to remove impurities and foreign materials from the disintegrated waste gypsum boards, the hydration crushing method was established, in which volumetric change when hemihydrate gypsum returns to gypsum dehydrate is utilized, and bond of gypsum particles with each other and with impurities is destructed to separate them into simple substances. Furthermore, discussions were given on the reforming conditions to reform in an energy saving manner the disintegrated waste gypsum boards into high-quality large-size hemihydrate gypsum by using the wet-type process that utilizes the reversible reaction between hemihydrate gypsum and gypsum dehydrate in the disintegrated waste gypsum boards. A manufacturing process to put the recycled gypsum into practical use was also discussed. Prototype board fabrication and tests were performed by using the reformed gypsum board materials, wherein good results were obtained from all of the practical, chemical, and physical tests. (NEDO)

  16. Report on the surveys in fiscal 1999. Surveys on practical application of the research achievements; 1999 nendo kenkyu seika no jitsuyoka ni kansuru chosa hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    A number of technological hurdles exist in the process of practically applying the fundamental researches, wherein risks for private business entities to promote the technological development are not at all small. The present surveys are intended to elucidate the actual status as to how a practical application process for technologies is positioned in the series of research and technological development activity floats by private corporations, and what kinds of problems are present, to serve for discussing the way the future supportive environment improvement should be. The 'practical application processes' in private corporations were put into order and analyzed, using as the base the existing study results relative to technological innovation mechanisms. Investigations ere performed on the existing Japanese research and technological development supporting institutions for the practical application processes employed by the private corporations. The result was used for reference of discussing the problems therein. Furthermore, it is indicated that, in the R and D strategies in the U.S.A., profitability is placed as the largest target by means of strengthening the linkage between research and commercialization. This has resulted in decline in the fundamental researches, for which discussions are developed currently. This paper reports investigations on the actual status of business enterprises in the practical application processes. (NEDO)

  17. Achievement report for fiscal 1988 on fundamental technologies for next generation industries. Research and development on composite materials; 1988 nendo fukugo zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-03-01

    With an objective to realize structural materials with light weight, high strength and high rigidity, research has been performed on composite materials. This paper reports the achievements in fiscal 1988. In the development on resin-based composite materials, the results of the evaluation tests on forming plates for epoxy-based resins were analyzed and summarized. On the polyimide-based resins, attempts were made on enhancement of formability of the terminal type and main chain type high heat resistant resins. Evaluations were executed on the resin characteristics by using the impact test, and heat deformation and heat reaction analyzing tests. Furthermore, experimental discussions were given on the heat transfer forming process, prefabrication forming process, microwave forming process, and hybrid forming process. In developing the metallic composite materials, the characteristics evaluation tests and manufacturing technologies were summarized on intermediate materials of the carbon fiber system and silicon carbide system. In addition, researches were performed on trial fabrication and formation of wire preforms. In the forming processes, discussions were given on the press forming process, roll forming process, HIP forming process, and thin wall thickness forming process. (NEDO)

  18. Fiscal 1999 achievement report. Development of ultralow-loss power device technology; 1999 nendo choteisonshitsu denryoku soshi gijutsu kaihtsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The aim is to establish basic technologies for upgrading wide-gap semiconductor devices, fabricated mainly of SiC, in terms of their low-loss, high-speed, and high-power features. In the research and development of ultralow-loss power device technology, progress of the effort is reviewed, problems in the process of research and development are extracted, and technological trends are surveyed. In the development of basic technologies, an SiC crystal growing device is experimentally built and the process of crystal growth is assessed and analyzed, and tasks to discharge for higher quality and larger diameter are extracted. Basic technologies are developed relative to the epitaxial growth, interface control, and conductivity control of SiC etc. In the development of technologies for developing SiC into devices, technological development is carried out for the junction-type FET (field effect transistor), which involves termination structure optimization, high-voltage capability enhancement, and gate-off gain improvement. As for MOSFET (metal oxide semiconductor FET), MOS channel formation technology is developed and device-constructing technology is also developed. As for MESFET (metal-semiconductor FET), micro-processing is established for a success in experimentally building a 0.5{mu}m-long gate. (NEDO)

  19. Fiscal 1982 Sunshine Project research report. Development of bore hole measurement technology; 1982 nendo koseinai sokutei gijutsu no kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-03-01

    This report summarizes the fiscal 1982 research result on development of measuring instruments for information collection in geothermal bore holes under high-temperature high-pressure conditions. In development of high-temperature well logging cable, the new TFE Teflon insulated well logging cable (3,300m) applicable up to 320 degreesC was prepared. In development of digital well logging system, the data analyzer for edition and analysis of recorded digital logging data, the depth panel with an automatic depth correction mechanism, and the fiber optics controller were prepared. Preparation of the whole digital well logging system was thus completed. Field test was made at 3 wells in 2 geothermal areas. At the test well in Nigori-Gawa area, Hokkaido, performance test was made on the digital well logging system, TFE Teflon well logging cable, and improved winch completed in this fiscal year. At the same time, the radioactive well logging test using radioactive isotope showed the satisfactory result except neutron well logging. (NEDO)

  20. Summary of the research achievements in fiscal 1990 in developing coal liquefying technologies; Sekitan ekika gijutsu kaihatsu 1990 nendo kenkyu seika no gaiyo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-03-01

    This paper describes the summary of the research achievements in fiscal 1990 in developing coal liquefying technologies. The bituminous coal liquefaction project is scheduled to have a 150-t/d pilot plant start operation from the latter half of fiscal 1994. Research problems were reviewed based on the basic and detailed designs. Construction processes were also reviewed by each facility. Detailed design was performed on the main four facilities for pretreatment, liquefying reaction, liquefied oil distillation, and solvent hydrogenation. Support researches were carried out on the pilot plant in addition to 1-t/d PSU and small testing devices. In the research of a brown coal liquefying technology, operation of the pilot plant (50 t/d) was resumed after completion of the long-term operation (Run 7) having been executed in fiscal 1989, and after the extraordinary repair. The planned operation has been completed as scheduled. Modification and repair works were also carried out. Researches were made on upgrading of brown coal liquefied oil, and a petroleum mixing technology. The paper also describes the support researches. In developing the common basic technologies, studies were performed on development of plant devices, investigation on coal type selection, applications of coal liquefied products, and a refining technology. An environment preserving technology was also developed. The development made it possible to identify the whole image relative to the relevant laws and regulations on the comprehensive operation oil in the whole fraction and by fractions. Comprehensive management of the research and development was also implemented. (NEDO)

  1. Japan's New Sunshine Project. 1998 annual summary of hydrogen energy R and D; New sunshine keikaku 1998 nendo seika hokokusho gaiyoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-04-01

    Summarized herein are the reports on R and D efforts on hydrogen energy, as part of the FY 1998 New Sunshine Project. For production of hydrogen, characteristics related to transport number were investigated for steam electrolysis at high temperature, in which a sintered ceramic powder was used as the electrolyte and the cell was equipped with platinum electrodes. For utilization of hydrogen, energy conversion techniques were investigated using hydrogen occluding alloys for testing methods for alloy microstructures and hydrogenation characteristics, and preparation of and performance testing methods for the cathodes charged with the aid of hydrogen gas. For analysis/assessment for development of hydrogen-related techniques, the investigated items included water electrolysis with solid polymer electrolytes, hydrogen transport techniques using metal hydrides, hydrogen storing techniques using metal hydrides, hydrogen engines, and techniques for preventing hydrogen embrittlement. Analysis/assessment for development of hydrogen turbines was also investigated as one of the 12 R and D themes reported herein. (NEDO)

  2. Report on achievements in fiscal 1975 in Sunshine Project. Studies on a technology to measure inside of wells; 1975 nendo koseinai sokutei gijutsu ni kansuru kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-03-01

    In order to identify the actual status of geothermal reservoirs, development is made on a technology to detect cracks in a geothermal reservoir. This fiscal year has launched development of a PS sonic logging device of well wall compression type, which is considered most effective in crack detection. This device has a number of new development elements such as a mechanism to have a transmitter and a receiver compressed on a geologic stratum to send sonic energy directly into the stratum, simultaneous use of S-wave having excellent characteristics in evaluating crack faces quantitatively and calculating porosities, and a cooling mechanism for electronics installed in the wells. Combining this with a micro seismogram log scheduled to be fabricated in fiscal 1976 will form the mainstream of crack face detection. A continual flow meter measures behavior of steam and hot water to identify flow-out or flow-in patterns and depths of fluid in wells under flowing condition. Adding this meter to temperature and pressure elements scheduled to be developed in fiscal 1976 will provide data to give an important guideline in underground heat production. This meter was attempted with enhancement in heat and pressure resistant characteristics and stabilization of operation for design and fabrication, which were carried out using the spinner flow meter as the base. (NEDO)

  3. Fiscal 1976 Sunshine Project result report. Research on solar energy utilization systems (solar furnace); 1976 nendo taiyo energy riyo system chosa kenkyu seika hokokusho. Taiyoro

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-03-01

    For solar furnace, study was made on analysis of its use purpose, analysis of the profitability of large furnaces, safety, maintenance, solar radiation and construction site conditions. On production of fused refractories by solar furnace, in particular, giving attention on zircon sand and mullite, their fusion property was clarified, and their fine structure was obtained by rapid heating/cooling. On production of Si by solar furnace, in this fiscal year, in particular, study was made on the 1st step (production of coarse Si from silica rock) and 4th step (deposition of Si by decomposition of SiHCl{sub 3}). On study on high-temperature processing followed by chemical reaction, study was made on production of carborundum by solar furnace, its application to high-temperature gas reaction, and its application to heat storage by high-temperature chemical reaction. In addition, for large solar furnace, study was made on its maintenance, safety, pollution problem, and construction site condition based on estimation of direct solar radiation profile maps. Inlands of Tokai, Kii-Hanto and Seto-Naikai districts were confirmed to be suitable for solar furnaces. (NEDO)

  4. Fiscal 1980 Sunshine Project research report. Development of slurry applicable to geothermal environment; 1980 nendo chinetsu kankyoka de shiyo kanona deisui no kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-03-01

    This report summarizes the fiscal 1980 research result on development of slurry applicable to geothermal environment. Study was made on the hydrothermal alteration and rheology of the clay suspension slurry system composed of base mud of sepiolite (thermogel), dehydrator of sodium polyacrylate (SPA), and dispersant GT-8. The study result clarified roughly the action mechanism of such slurry under geothermal environment. Such slurry thus achieved an expected target experimentally through various tests on slurry characteristics at higher temperature, slurry curing and slurry conditioning. Test was made on the lubricity of air system drilling fluid. Simulated field test was made on a preventive effect from lost circulation by using combination of various materials. The preventive effect increased with the kind of additional preventive agents. As for waste sludge treatment technology, the agitating capacity of a mixing tank for polymer flocculant was improved. Study was made on possible continuous treatment of sludge by using the above equipment and a continuous sludge caking equipment, resulting in achievement of an expected target. (NEDO)

  5. Fiscal 1998 research achievement report. Project for promoting development of super-advanced electronic technology; 1998 nendo chosentan denshi gijutsu kaihatsu sokushin jigyo seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-01

    For the purpose of establishing super-advanced technologies two generations ahead in the field of electronics and information, research and development was carried out involving ultrafine machining process technology, technologies of ultimate measuring, analysis, and control, and technologies of electronic materials equipped with novel functions. In the study of writing systems in which writing is performed directly by an electron beam, writing technologies using electron beams under single-column and multi-column systems were taken up. In the study of ultrashort wavelength electromagnetic wave patterning systems, studies were made about equimultiple ultrashort wavelength and reduced ultrashort wavelength electromagnetic wave patterning. In the study of ultrahigh precision shielding systems, studies involved high precision in situ measurement and control of writing distortion, and ultrahigh precision and high current density electronic optical technologies. Also carried out were research and development of technologies of super-advanced plasma measurement, analysis, and control, technology of cleaning by ultrafine particle control, technology of ultrahigh sensitivity medium, and technologies of new functional elements and film fabrication. In the overall research and survey, surveys were conducted of the trends of development of technology of semiconductor related lithography. (NEDO)

  6. Report of overseas dispatch of Japanese researchers by RITE in fiscal 1995; 1995 nendo RITE kokunai kenkyusha kaigai haken seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    This is a report of overseas dispatch of domestic researchers by the Research Institute of Innovative Technology for the Earth (RITE). When the CO2 reduction effect in the air is evaluated by the chemical fixation of CO2, not only the reduction but also the total reduction of CO2 emission by introducing the countermeasure technology should be investigated. Measures for reduction were evaluated by the LCA technique in Austria, and related information was collected in Europe. The promotion of international cooperation for the CO2 storage in the ocean, and the economy and environmental harmony of the whole system including separation, recovery, transportation of CO2, and its supply into the ocean were investigated in Massachusetts Institute of Technology. Based on the biological synthesis and decomposition of chitin and chitosan (chitin matter circulation) which are components of shell of insects and shellfish, the fixation of CO2 and development of new materials in the hydrosphere were investigated in Norway. To clarify the reaction mechanism and critical factors of the yield of the rhenium carbonyl complex, a CO2 photoreduction catalyst, a relationship between the change of electronic state of complex due to chemical modification and the infrared absorption was analyzed in the United Kingdom. 26 refs., 40 figs., 12 tabs.

  7. Report on achievements in fiscal 1999 on research and development of the Welfare Techno-system (Niihama); 1999 nendo Welfare Techno system kenkyu kaihatsu (Niihama) seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    Research and development has been performed on a welfare techno-system that takes into account the interface between houses themselves and welfare devices and between the welfare devices to perform without troubles the life actions in houses such as movement, excretion and bathing. This paper summarizes the achievements in fiscal 1999. In developing a bath tub that promotes autonomous life for handicapped elderly people, data were collected on bath tubs having been fabricated on the trial basis in the previous fiscal year, problems were extracted, and a shape of a corner-installed type bath tub for home use was decided. In developing a reclining transfer-assisting wheelchair, the wheelchair developed in the previous fiscal year was added with the function by which a wheelchair can be reclined to an optional angle by using person's own force. In developing a horizontally transferring wheelchair, improvement was made on the mechanism to transfer a person from a wheelchair to a bed, resulting in a good result that it can be operated by one helper. In developing a wheelchair accommodating lifter, a lifter was developed that allows a wheelchair to be accommodated easily into the trunk of a passenger car even by one female helper. Research and development was also performed on a portable letter reading device for sight handicapped persons. (NEDO)

  8. Collection of summaries of Sunshine Program achievement reports for fiscal 1981. Hydrogen energy; 1981 nendo sunshine keikaku seika hokokusho gaiyoshu. Suuiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-04-01

    The collection includes research on hydrogen production through the electrolysis of water using an acid-type solid polymer electrolyte, electrolysis of water using an alkali-type solid polymer electrolyte, thermochemical method using an iodine-based cycle, thermochemical method using a bromine-based cycle, thermochemical method using a mixed cycle, high-temperature direct thermolysis, and the utilization of solar radiation. Furthermore, it includes a study of materials to build a iodine-based cycle apparatus. In a research on the transportation and storage of hydrogen, technologies of hydrogen transportation and storage using metallic hydrides are taken up. In a research on the application of hydrogen, technologies of hydrogen combustion and hydrogen-fueled engines are discussed. In a research on hydrogen safety measures, technologies for the prevention of hydrogen explosion disasters and of hydrogen embrittlement of materials in use with hydrogen are studied. In addition, a study is conducted of a hydrogen energy total system, and research and development is carried out of a plant that produces hydrogen by means of the high-temperature high-pressure electrolysis of water. (NEDO)

  9. Fiscal 2000 achievement report. Research on machine tool not necessitating hydraulic system; 2000 nendo yuatsu resu kosaku kikai no kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    From the viewpoint that the manufacturing process, expendable items, and recycling should all be taken into consideration when machine tool energy consumption is the matter to discuss, it is concluded that the most important policy to follow in the effort to enhance energy conservation is to enable the tool to operate without hydraulic systems. For the realization of a general-purpose machine tool (lathe) to operate free of hydraulic systems, efforts are exerted to develop element technologies, tool rests, tail stocks, and chuck drives usable for the construction of a practical hydraulic system-free machine tool. In fiscal 2000, comprehensive evaluation of experimental machine tools continued, problems to solve for practical application were put together for the fabrication of improved units, and the improved units and an improved control method were integrated into a prototype of practical machine tools. The prototype was exhibited at Japan International Machine Tool Fair (JIMTOF) as a hydraulic system-free NC (numerically controlled) lathe Type LB300, and won a high valuation. The prototype was then tested for basic performance and for possibility of improvement, and problems to be solved before commercialization were isolated. (NEDO)

  10. FY 1974 report on the results of the Sunshine Project. Technology assessment of hydrogen energy technology; 1974 nendo suiso energy gijutsu no technology assessment seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1975-04-30

    This is aimed at studying the relation between the technology development of hydrogen energy and the society. In Chapter 1, a meaning of technology assessment was examined. When applying it to the hydrogen energy technology, the paper presented what content it has. In Chapter 2, the needs for hydrogen energy in society were made clear in comparison with the energy supply/demand structure in Japan and characteristics of hydrogen energy. In Chapter 3, the paper showed what kinds of technology are being developed to meet the needs in this society and arranged viewpoints for evaluating the effectiveness of the technology. In Chapter 4, the paper studied the positioning of hydrogen energy technology in the future society, and presented as examples more than one hydrogen energy/system plans which become the base to describe the impact of the technology on the society. If taking technology assessment as a part of the communication activities between the technology development and the society as did in this study, these system plans are something like the ring for people in each field to talk with. In Chapter 5, the study made from each aspect was arranged. (NEDO)

  11. Fiscal 1980 Sunshine Project research report. Removal technology of H{sub 2}S; 1980 nendo ryuka suiso jokyo gijutsu no kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1981-03-01

    This report summarizes the fiscal 1980 research result on removal process and equipment of H{sub 2}S from condensate and waste gas of turbine inlet steam and turbine outlet condensers of geothermal power plants. In the research on continuous measurement method of H{sub 2}S in geothermal steam, the continuous measurement equipment was completed by improving the heat conduction type steam qualitative dilution equipment developed in last year. The test result of this equipment in Onikobe geothermal power plant gave interesting data showing cyclic fluctuation of H{sub 2}S concentration. In the research on treatment of turbine inlet steam, both physical and chemical treatments were unpractical because of their very expensive costs. In the research on treatment of turbine outlet fluid by selecting RET method for waste gas and diffusion method for condensate, the field test result by using real fluid in geothermal power plants made it possible to select the optimum process according to conditions of turbine outlet fluid, and to estimate removal costs of H{sub 2}S precisely. (NEDO)

  12. FY1998 report on the research on support for practical recycling technologies. Part 1; 1998 nendo recyle gijutsu nado jitsuyoka shien kenkyu seika hokokusho. 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    This project aims at development, demonstration and utilization of waste recycling technologies. This report summarizes the fiscal 1998 results. The test/demonstration plant for separation and removal of foreign materials was constructed for effective use of waste building wood, and its optimum operation condition was studied. Although some foreign materials exists, 90% of waste building wood chips were separated and recovered through some improvements for the plant. An advanced separation technology is expected. As for fibering technology, fibers with target compression strength were obtained from cedar chips through a disintegration experiment using a newly developed refiner plate. Although the compression strength of fibers obtained from waste building wood chips was slightly poor, it is attained by increasing the target specific gravity of light- weight wooden materials by nearly 10% from 0.1. As for fiber orientation technology, as the tension of a forming belt was adjusted to achieve sufficient width compression, nearly 90% of the target compression strength was attained. A width compression method remains to be solved. (NEDO)

  13. FY 1999 report on the results of the technology development of next-generation chemical process; 1999 nendo jisedai kagaku process gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The R and D were conducted on the naphtha catalytic cracking, selective oxidation reaction of saturated hydrocarbon, new reaction mechanism utilization process, etc., as next-generation chemical process technology in FY 1999, and the results were summarized. As to the technology of naphtha catalytic cracking, developed was La203/p/ZMS-5 zeolite catalyst which is high in cracking activity and high in light-olefin selectivity. By the FS, it was confirmed that this is more excellent in case of the fixed bed reactor than in the present process. Concerning the technology of selective oxidation reaction of saturated hydrocarbon, the basic information/knowledge were obtained about the construction of catalytic principle toward the high selective catalytic partial oxidation, elucidation of a reaction mechanism in alkane oxidation and design of high functional catalysts, elucidation of a mechanism in butan oxidation, synthesis of alkane selective oxidation catalysts, etc. In relation to the technology of new reaction mechanism utilization process, the following were carried out: study of ethyl benzene dehydrogenation using the membrane reactor trially fabricated in the previous fiscal year, development of high efficiency hydrogen penetration membranes and low temperature high activity catalysts, study of the new process by membrane reactor. (NEDO)

  14. Achievement report for fiscal 1990 on research and development of high-efficiency molecule separating membrane materials; 1990 nendo kokoritsu kobunshi bunrimaku zairyo no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-03-01

    In order to achieve high efficiency and energy conservation in the separation processes in the chemical industry, activities were performed to seek high-efficiency liquid separation films, gas separation films, and the related technologies that make possible separation, condensation, and refinement of substances that have consumed large amount of energy in the conventional separation processes (for example, water-alcohol, and rare gases), and substances difficult of separation and refinement because of resemblance in physical and chemical properties (for example, isomer mixed substances). For the gas separation films, research and development has been made on (1) high-order molecule recognizing films, (2) high-density metal complex fixing thin films, (3) high-functional complex films, and (4) re-activating oxygen condensation films. In (1), attempt was made on oxygen condensation by impregnating the carrier film with aqueous cobalt complex solution with regard to oxygen, for example. Research has been made on alcohol condensation film in the liquid selecting and separating films. Research and development has been made on fluororesin films for water/polar organics separation, (3) high-order structure control of water selective and permeating films, (4) water/acetic acid separating films, and (5) particle separation process utilizing liquid films. (NEDO)

  15. FY 1990 achievement report on the survey of possibility of introducing solar energy into buildings; 1990 nendo taiyo energy no kenchikubutsu eno donyu kanosei chosa seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-03-01

    This paper describes the achievements in fiscal 1990 on survey on possibility of introducing solar energy into buildings. Capacity of photovoltaic power generation facilities installed on an area of 1600 km{sup 2}, such as roofs of residential houses, schools and building may be calculated on a trial bases as 100 million kW at maximum. The capacity can replace 16% of the total demand and corresponds to 26.30 million kiloliters (9%) as converted to crude oil. If photovoltaic power generation is utilized on buildings of users, diversified technological criteria are required from the viewpoint of legislation covering wide range of architectural, electrical and disaster aspects. However, no direct and clear standards are available now, except for the electric power business law. What are urgently required are solar cell standardization, incentive subsidies, aging safety, institutions for electric power sale and purchase, and establishment of technological criteria. An utilization example survey revealed problems in array installation and size. Increased demand, mass production and cost reduction will create a favorable cycle. Introduction, proliferation, and acceleration under policies at public facilities which are expected of enlightenment and development into other areas will be the effective means for the purpose. (NEDO)

  16. FY 1998 report of the results of the R and D of human media; 1998 nendo human media no kenkyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    In the light of the trial design/manufacture made in the previous fiscal year, the following were conducted in this R and D: design/manufacture of a system to support the combinedly complete design of designer, contemplation of a system to instantly search the necessary images without keyword input, joint design of urban environment after completion of urban redevelopment by virtual reality technology, design/manufacture of a system by which many people can feel reality, and manufacture of a system to enable evaluation of disaster prevention by a model of urban planning design. Further, carried out were exchanges of technology information and survey on the trend of domestic/overseas technology. In the R and D of the Kansei agent and human media database, pre-prototyping of the integrated system was conducted. By this, an image was materialized for realization of an industrial design support system including sensible information and multimedia contents using database. In the R and D of urban environment human media, the following were conducted: design/evaluation support for design including buildings and the whole urban environment; primary development of individual technology by which many people can virtually experience simultaneously landscape, wind environment, refuge behavior at the time of disaster, etc. (NEDO)

  17. Summary of the research achievements in fiscal 1988. Development of coal liquefaction technologies; Sekitan ekika gijutsu kaihatsu. 1988 nendo kenkyu seika no gaiyo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-03-01

    This paper reports the summary of the research and development works in fiscal 1988. The following researches were carried out: as development of a bituminous coal liquefaction technology, studies by using a pilot plant, studies on support of the pilot plant (studies by using an experimental plant (studies by using a 1-t/d PSU, development of an optimal pretreatment technology for coals to be used for liquefaction, studies on improvement in fraction oil distribution in the NEDOL process, and studies by using a 1-t/d plant)), and (studies by using a small device (studies on coal liquefying conditions, and studies on solvent hydrogenation catalysts)). Studies were carried out on operation of the pilot plant, and on support of the pilot plant operation. Materials for auxiliary machinery were developed (including in-plant test of new materials), and so were the devices (including development of a let-down valve) as trial fabrication and development of the plant devices and materials. As coal type selection and survey, coal types were surveyed, and liquefaction performance of Chinese coals was tested. In order to develop applications of coal liquefied products and a refining technology, developments were carried out on up-grading of the coal liquefied oil, a petroleum mixing technology, and a technology to separate hetero compounds in coal liquefied oil, and applications of the compounds. (NEDO)

  18. Achievement report for fiscal 1999. FS surveys to excavate international joint research seeds; 1999 nendo kokusai kyodo kenky seeds hakkutsu no tame no FS chosa seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    The FS surveys to excavate international joint research seeds are intended to promote international joint researches, whereas surveys have been carried out in fiscal 1999 on eight themes covering as wide scope as new energies, resource conservation, energy conservation, environment preservation, functional materials, information communication technologies, and bio-technologies. The eight themes are: researches on energy conservation in petroleum and petrochemical industries by using advanced distillation processes (to develop an internal heat exchange type distillation column, and realize energy conservation exceeding the minimum reflux status being the limitation of conventional energy saving means), researches on treatment of hard-to-decompose chemical substances by utilizing surface reformation by means of discharge, a new process monitoring technology (process tomography), establishment of human immortalization cells due to co-manifestation of mortalin and telomerase and elucidation of their structure, a remote maintenance technology using integrated type sensors, application of new heat resistant plastics to photo and electronic materials, preparation processes of petroleum catalysts utilizing in situ XAFS, elucidation and design of the structure of the ultra-micro metal activation point in the reaction process, and surveys on necessity of developing a continuous and massive separation system of high-level energy and resource saving type using liquid-liquid distribution. (NEDO)

  19. Collection of summaries of polymer electrolyte fuel cell research and development reports presented at fiscal 2000 meeting; 2000 nendo kotai kobunshigata nenryo denchi kenkyu kaihatsu seika hokokukai yoshishu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-08

    Contained in this book are the summaries of 26 essays presented at an achievement reporting conference on polymer electrolyte fuel cell (PEFC) research and development held in Tokyo on March 8, 2000. In the development of high-efficiency energy systems for transportation and residential/commercial sectors, 6 essays are summarized, involving ion exchange membranes, normal pressure operation type several kW class power source systems for home use, and so forth. For the practical application of high-efficiency fuel cell systems, 12 essays are summarized, involving technologies of PEFC low cost electrodes, PEFC module manufacturing, hydrogen separation type reforming, PEFC system manufacturing, and so forth. In relation to the establishment of technologies for a fuel cell popularization infrastructure and development of key technologies for high-efficiency fuel cells, 2 essays are summarized, involving the construction of a popularization infrastructure and development of evaluation test equipment, and the like, for automotive fuel cells. In relation to the development of key technologies and verification thereof for the practical application of fuel cells, 6 essays are summarized, covering the research and development of hydrogen producing liquid fuels and hydrogen absorbing alloys. (NEDO)

  20. Aerial radiation monitoring around the Fukushima Dai-ichi Nuclear Power Plant using an unmanned helicopter.

    Science.gov (United States)

    Sanada, Yukihisa; Torii, Tatsuo

    2015-01-01

    The Great East Japan Earthquake on March 11, 2011 generated a series of large tsunami that seriously damaged the Fukushima Dai-ichi Nuclear Power Plant (FDNPP), which resulted in the release of radioactive materials into the environment. To provide further details regarding the distribution of air dose rate and the distribution of radioactive cesium ((134)Cs and (137)Cs) deposition on the ground within a radius of approximately 5 km from the nuclear power plant, we carried out measurements using an unmanned helicopter equipped with a radiation detection system. The distribution of the air dose rate at a height of 1 m above the ground and the radioactive cesium deposition on the ground was calculated. Accordingly, the footprint of radioactive plumes that extended from the FDNPP was illustrated. Copyright © 2014 Elsevier Ltd. All rights reserved.

  1. The Fukushima Dai-ichi Accident and its implications for the safety of nuclear power

    Science.gov (United States)

    Barletta, William

    2016-05-01

    Five years ago the dramatic events in Fukushima that followed the massive earthquake and subsequent tsunami that struck Japan on March 11, 2011 sharpened the focus of scientists, engineers and general public on the broad range of technical, environmental and societal issues involved in assuring the safety of the world's nuclear power complex. They also called into question the potential of nuclear power to provide a growing, sustainable resource of CO2-free energy. The issues raised by Fukushima Dai-ichi have provoked urgent concern, not only because of the potential harm that could result from severe accidents or from intentional damage to nuclear reactors or to facilities involved in the nuclear fuel cycle, but also because of the extensive economic impact of those accidents and of the measures taken to avoid them.

  2. The Fukushima Daiichi nuclear site. Airborne releases during works on unit 3 in August 2013

    International Nuclear Information System (INIS)

    2014-07-01

    After having briefly recalled the consequences of the earthquake and tsunami on the Fukushima-Daiichi nuclear power station, this document briefly describes what happened to the building of the reactor number 3, and works to be done to dismantle this installation: removal of damaged structures, of debris in the pool, and then removal of fuel from this pool, removal of the core degraded fuel. The removal of structures and debris has been achieved in October 2013, but leaded to radioactive airborne releases. Simulations of atmospheric dispersion have been performed by the IRSN. Radioactive measurements have been also performed, and the evolution of crop contamination between 2011 and 2013 is discussed, notably in the case of rice. Lessons learned can be useful for the dismantling of other units

  3. Fukushima Daiichi-Derived Radionuclides in the Ocean: Transport, Fate, and Impacts.

    Science.gov (United States)

    Buesseler, Ken; Dai, Minhan; Aoyama, Michio; Benitez-Nelson, Claudia; Charmasson, Sabine; Higley, Kathryn; Maderich, Vladimir; Masqué, Pere; Morris, Paul J; Oughton, Deborah; Smith, John N

    2017-01-03

    The events that followed the Tohoku earthquake and tsunami on March 11, 2011, included the loss of power and overheating at the Fukushima Daiichi nuclear power plants, which led to extensive releases of radioactive gases, volatiles, and liquids, particularly to the coastal ocean. The fate of these radionuclides depends in large part on their oceanic geochemistry, physical processes, and biological uptake. Whereas radioactivity on land can be resampled and its distribution mapped, releases to the marine environment are harder to characterize owing to variability in ocean currents and the general challenges of sampling at sea. Five years later, it is appropriate to review what happened in terms of the sources, transport, and fate of these radionuclides in the ocean. In addition to the oceanic behavior of these contaminants, this review considers the potential health effects and societal impacts.

  4. Fukushima-Daiichi accident. News bulletin no. 2 from April 8

    International Nuclear Information System (INIS)

    2011-01-01

    This news bulletin has been prepared by the French institute of radiation protection and nuclear safety (IRSN) for the information of French residents in Japan. It presents, first, the situation at the date of the bulletin of the reactors at the power plant site, the accident management actions in progress, the radioactive contamination around the site, the evolution of radioactivity in the air of Tokyo since March 15, the meteorological forecasts, and the impact of the April 7 earthquake. Then, it gives some general recommendations to residents concerning food consumption and dwelling hygiene. Finally, some scientific information about radionuclides migration, radioactive pollution and their environmental impact are given. The geographic distribution of radioactive fallouts around the Fukushima-Daiichi site is shown. (J.S.)

  5. Analysis of core melt accident in Fukushima Daiichi-Unit 1 nuclear reactor

    International Nuclear Information System (INIS)

    Tanabe, Fumiya

    2011-01-01

    In order to obtain a profound understanding of the serious situation in Unit 1 and Unit 2/3 reactors of Fukushima Daiichi Nuclear Power Station (hereafter abbreviated as 1F1 and 1F2/3, respectively), which was directly caused by tsunami due to a huge earthquake on 11 March 2011, analyses of severe core damage are performed. In the present report, the analysis method and 1F1 analysis are described. The analysis is essentially based on the total energy balance in the core. In the analysis, the total energy vs. temperature curve is developed for each reactor, which is based on the estimated core materials inventory and material property data. Temperature and melt fraction are estimated by comparing the total energy curve with the total stored energy in the core material. The heat source is the decay heat of fission products and actinides together with reaction heat from the zirconium steam reaction. (author)

  6. Philosophy of safety assurance after the Fukushima Daiichi accident. From views of experts

    International Nuclear Information System (INIS)

    Hisada, Tsukasa

    2014-01-01

    Knowledge incorporating meetings were held to exchange views of experts in order to learn respective safety concept and philosophy of safety assurance except nuclear area, how should be prepared for beyond expectation and what was needed to build social credibility, and how to upgrade safety measures of nuclear power station after the Fukushima Daiichi accident. Meeting had been held twice a year since FY2012 and two lecturers were invited at each meeting to give a lecture on the specified theme such as safety assurance in aviation area and chemical plants, and 'safety target of engineering system'. Common or different views on safety assurance between nuclear and other areas were identified, and risk concept and sincere attitude of explaining engineer were mentioned quite important for preparation for beyond expectation and building social credibility. (T. Tanaka)

  7. An update on radioactive release and exposures after the Fukushima Dai-ichi nuclear disaster.

    LENUS (Irish Health Repository)

    McLaughlin, P D

    2012-09-01

    On 11 March 2011, the Richter scale 0.9-magnitude Tokohu earthquake and tsunami struck the northeast coast of Japan, resulting in widespread injury and loss of life. Compounding this tragic loss of life, a series of equipment and structural failures at the Fukushima Dai-ichi nuclear power plant (FDNP) resulted in the release of many volatile radioisotopes into the atmosphere. In this update, we detail currently available evidence about the nature of immediate radioactive exposure to FDNP workers and the general population. We contrast the nature of the radioactive exposure at FDNP with that which occurred at the Chernobyl power plant 25 years previously. Prediction of the exact health effects related to the FDNP release is difficult at present and this disaster provides the scientific community with a challenge to help those involved and to continue research that will improve our understanding of the potential complications of radionuclide fallout.

  8. Japan's compensation system for nuclear damage - As related to the TEPCO Fukushima Daiichi nuclear accidents

    International Nuclear Information System (INIS)

    Nomura, Toyohiro; Matsuura, Shigekazu; Takahashi, Yasufumi; Takenaka, Chihiro; Hokugo, Taro; Kamada, Toshihiko; Kamai, Hiroyuki

    2012-01-01

    Following the TEPCO Fukushima Daiichi nuclear power plant accident, extraordinary efforts were undertaken in Japan to implement a compensation scheme for the proper and efficient indemnification of the affected victims. This publication provides English translations of key Japanese legislative and administrative texts and other implementing guidance, as well as several commentaries by Japanese experts in the field of third party nuclear liability. The OECD Nuclear Energy Agency (NEA) has prepared this publication in co-operation with the government of Japan to share Japan's recent experience in implementing its nuclear liability and compensation regime. The material presented in the publication should provide valuable insights for those wishing to better understand the regime applied to compensate the victims of the accident and for those working on potential improvements in national regimes and the international framework for third party nuclear liability

  9. Birth Outcomes after the Fukushima Daiichi Nuclear Power Plant Disaster: A Long-Term Retrospective Study.

    Science.gov (United States)

    Leppold, Claire; Nomura, Shuhei; Sawano, Toyoaki; Ozaki, Akihiko; Tsubokura, Masaharu; Hill, Sarah; Kanazawa, Yukio; Anbe, Hiroshi

    2017-05-19

    Changes in population birth outcomes, including increases in low birthweight or preterm births, have been documented after natural and manmade disasters. However, information is limited following the 2011 Fukushima Daiichi Nuclear Power Plant Disaster. In this study, we assessed whether there were long-term changes in birth outcomes post-disaster, compared to pre-disaster data, and whether residential area and food purchasing patterns, as proxy measurements of evacuation and radiation-related anxiety, were associated with post-disaster birth outcomes. Maternal and perinatal data were retrospectively collected for all live singleton births at a public hospital, located 23 km from the power plant, from 2008 to 2015. Proportions of low birthweight (effects on maternal and perinatal health.

  10. Accident at the Fukushima Dai-ichi nuclear power stations of TEPCO. Outline and lessons learned

    International Nuclear Information System (INIS)

    Tanaka, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others. (author)

  11. Results of stress tests of European nuclear power plants after the Fukushima-Daiichi accident

    International Nuclear Information System (INIS)

    Kovacs, Zoltan; Novakova, Helena

    2012-01-01

    In response to the Fukushima-Daiichi accident, the European Council laid down the requirement that a transparent and comprehensive risk assessment exercise ('stress tests') be carried out at each European nuclear power plant. The stress tests concentrated on the nuclear power plants' safety margins in the light of the lessons learned from the accident. The reviews focused on natural external events including earthquake, tsunami and extreme weather, loss of safety functions, and severe accident management. The stress test procedure comprised 3 steps: (i) The nuclear facility operators performed the stress tests and prepared proposals for safety improvements. (ii) The national regulators performed independent reviews of the stress tests and prepared national reports. (iii) The reports submitted by the national regulators were subjected to review at a European level. The article describes the scope of the stress tests and their results, verified at the European level. (orig.)

  12. Accumulation of radioactive cesium released from Fukushima Daiichi Nuclear Power Plant in terrestrial cyanobacteria Nostoc commune.

    Science.gov (United States)

    Sasaki, Hideaki; Shirato, Susumu; Tahara, Tomoya; Sato, Kenji; Takenaka, Hiroyuki

    2013-01-01

    The Fukushima Daiichi Nuclear Power Plant accident released large amounts of radioactive substances into the environment and contaminated the soil of Tohoku and Kanto districts in Japan. Removal of radioactive material from the environment is an urgent problem, and soil purification using plants is being considered. In this study, we investigated the ability of 12 seed plant species and a cyanobacterium to accumulate radioactive material. The plants did not accumulate radioactive material at high levels, but high accumulation was observed in the terrestrial cyanobacterium Nostoc commune. In Nihonmatsu City, Fukushima Prefecture, N. commune accumulated 415,000 Bq/kg dry weight (134)Cs and 607,000 Bq kg(-1) dry weight (137)Cs. The concentration of cesium in N. commune tended to be high in areas where soil radioactivity was high. A cultivation experiment confirmed that N. commune absorbed radioactive cesium from polluted soil. These data demonstrated that radiological absorption using N. commune might be suitable for decontaminating polluted soil.

  13. Analysis on Isolation Condenser Operation by Fukushima Daiichi Unit 1 Operators

    International Nuclear Information System (INIS)

    Kim, Man Cheol

    2014-01-01

    Fukushima Daiichi nuclear accident resulted in the core damage in three reactors and the release of considerable amount of radioactive material to the environment, not to mention significant social impact and anti-nuclear atmosphere all around the world. This paper provides a review of the findings related to shift operators' operation of the isolation condenser in Unit 1 to examine shift operators' response to the situation. Based on the review of the findings, a situation assessment model was developed to analyze shift operators' understanding on whether core cooling was successfully performed in Unit 1 through the operation of isolation condenser. It was found that lack of information could be one of the main causes for the failure in core cooling by the IC in Unit 1. It is also recommended that the differences in the mathematical model for the situation assessment and that of the real operator need to be further investigated

  14. Analysis on Isolation Condenser Operation by Fukushima Daiichi Unit 1 Operators

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Man Cheol [Chungang University, Seoul (Korea, Republic of)

    2014-08-15

    Fukushima Daiichi nuclear accident resulted in the core damage in three reactors and the release of considerable amount of radioactive material to the environment, not to mention significant social impact and anti-nuclear atmosphere all around the world. This paper provides a review of the findings related to shift operators' operation of the isolation condenser in Unit 1 to examine shift operators' response to the situation. Based on the review of the findings, a situation assessment model was developed to analyze shift operators' understanding on whether core cooling was successfully performed in Unit 1 through the operation of isolation condenser. It was found that lack of information could be one of the main causes for the failure in core cooling by the IC in Unit 1. It is also recommended that the differences in the mathematical model for the situation assessment and that of the real operator need to be further investigated.

  15. Implementation of Defence in Depth at Nuclear Power Plants. Lessons Learnt from the Fukushima Daiichi Accident

    International Nuclear Information System (INIS)

    Lachaume, Jean-Luc; Miller, Douglass; Rzentkowski, Greg; Lahtinen, Nina; Valtonen, Keijo; Foucher, Laurent; Harikumar, Shri S.; Yamada, Tomoho; Sharafutdinov, Rashet; Kuznetsov, Mark; Carlsson, Lennart; Hanberg, Jan; Theiss, Klaus; Holahan, Gary; Williams, Donna; Nuenighoff, Kay; Wattelle, Emmanuel; Lazo, Edward; White, Andrew; Reig, Javier; Salgado, Nancy; Weightman, Mike

    2016-01-01

    Defence in depth (DiD) is a concept that has been used for many years alongside tools to optimise nuclear safety in reactor design, assessment and regulation. The 2011 Fukushima Daiichi nuclear power plant accident raised many questions and gave unique insight into nuclear safety issues, including DiD. In June 2013, the NEA held a Joint Workshop on Challenges and Enhancements to DiD in Light of the Fukushima Daiichi Accident (NEA, 2014), organised by the NEA Committee on the Safety of Nuclear Installations (CSNI) and the NEA Committee on Nuclear Regulatory Activities (CNRA). It was noted at the time that further work would be beneficial to enhance nuclear safety worldwide, especially with regard to the implementation of DiD. Accordingly, a senior-level task group (STG) was set up to produce a regulatory guidance booklet that would assist member countries in the use of DiD, taking into account lessons learnt from the 2011 accident. This regulatory guidance booklet builds on the work of this NEA workshop, of the International Atomic Energy Agency (IAEA), the Western European Nuclear Regulators Association (WENRA) and of other members of the STG. It uses as its basis the International Nuclear Safety Advisory Group's Defence in Depth in Nuclear Safety study (INSAG-10) (IAEA, 1996). The booklet provides insights into the implementation of DiD by regulators and emergency management authorities after the Fukushima Daiichi accident, aiming to enhance global harmonisation by providing guidance on: - the background to the DiD concept; - the need for independent effectiveness among the safety provisions for the various DiD levels, to the extent practicable; - the need for greater attention to reinforce prevention and mitigation at the various levels; - the vital importance of ensuring that common cause and common mode failures, especially external events acting in combination, do not lead to breaches of safety provisions at several DiD levels, taking note of the

  16. Japan Reports New Water Leak at Fukushima Daiichi; IAEA Sees No Danger to Public

    International Nuclear Information System (INIS)

    2014-01-01

    Full text: Japanese authorities have informed the IAEA that a leak from an overflowing water storage tank at TEPCO's Fukushima Daiichi Nuclear Power Station was detected in the late evening of 19 February 2014. About 100 cubic metres of radioactive water leaked to the ground adjacent to the tank storage area before the leak was stopped about six hours later. Based on the information provided, IAEA experts consider that the leak poses no danger to the public. IAEA experts also consider actions taken by Japan's Nuclear Regulatory Authority (NRA) following the leak to be appropriate. These include an NRA recommendation that TEPCO remove soil contaminated by the leaked water, which will reduce the risk that contaminated water will be spread further through rain and groundwater. Japan has not asked the IAEA for any assistance in connection with the leak from the tank. The IAEA will continue monitoring developments. (IAEA)

  17. Radioactivity around Fukushima Daiichi Nuclear Power Plant 9 months after the disaster

    International Nuclear Information System (INIS)

    Shozugawa, Katsumi

    2012-01-01

    We have measured radioactivities around Fukushima Daiichi Nuclear Power Plant in December, 2011, 9 months after the disaster, to compare with measurements in April, 2011. The radioactivity originated by radioactive iodine should have disappeared before December due to its comparatively short lifetime. At the point 1.5km apart from the Plant, the dose rate 1m above the earth was 78 μ Sv/h in April whereas it was 56 μ Sv/h in December, which was higher than anticipation. The measured radioactivities of the soil of fields and forests around the Plant in December were even four times higher than those in April. These phenomena may be resulted with the movement of soil particles attached with radioactive cesium by rainwater or wind. (author)

  18. Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt

    International Nuclear Information System (INIS)

    Magwood, William D. IV; Niel, Jean-Christophe; Fuketa, Toyoshi; Sheron, Brian; Boyd, Michael; McGarry, Ann; Dussart-Desart, Roland; Reig, Javier; Hah, Yeonhee; Nieh, Ho; Vasquez-Maignan, Ximena; Salgado, Nancy; White, Andrew; Lazo, Edward; Creswell, Len; Leeds, Eric; Gannon-Picot, Cynthia; Griffiths, Janice

    2016-01-01

    Countries around the world continue to implement safety improvements and corrective actions based on lessons learnt from the 11 March 2011 accident at the Fukushima Daiichi nuclear power plant. This report provides a high-level summary and update on these activities, and outlines further lessons learnt and challenges identified for future consideration. It focuses on actions taken by NEA committees and NEA member countries, and as such is complementary to reports produced by other international organisations. It is in a spirit of openness and transparency that NEA member countries share this information to illustrate that appropriate actions are being taken to maintain and enhance the level of safety at their nuclear facilities. Nuclear power plants are safer today because of these actions. High-priority follow-on items identified by NEA committees are provided to assist countries in continuously benchmarking and improving their nuclear safety practices. (authors)

  19. Radiation protection management in Fukushima Daiichi NPS and post-accident measures

    International Nuclear Information System (INIS)

    Takahira, Shiro

    2014-01-01

    Fukushima Daiichi Nuclear Power Station was hit by the big earthquake and tsunami, which caused the station black out and subsequent loss of cooling functions for reactor and spent fuel pools (SFPs). Consequently the fuels were damaged, hydrogen explosion blew off top of the reactor buildings and radioactive materials were released to the atmosphere and the ocean. Tsunami and power loss caused many difficulties of monitoring, dose management, and radiation protection of workers. For example, the radiation management system was down and about 5,000 Alarm Pocket Dosimeters (APDs) and their battery chargers could not be used. Due to the insufficient number of APDs, one representative of each working team had a dosimeter under the limited conditions. Through the accident, we got following lessons learned; (1) Reinforcing monitoring posts, (2) Preparing more radiation protection equipment, (3) Establishing emergency access control centre, and (4) Education and training in radiation protection. (author)

  20. Study of treatment scenarios for fuel debris removed from Fukushima Daiichi NPS

    International Nuclear Information System (INIS)

    Washiya, Tadahiro; Yano, Kimihiko; Kaji, Naoya; Yamada, Seiya; Kamiya, Masayoshi

    2015-01-01

    On March 11, 2011, a severe nuclear accident occurred at Tokyo Electric Power Company (TEPCO)’s Fukushima Daiichi Nuclear Power Plant (hereinafter called as F1). After the accident, the Council for the Decommissioning was established, mainly by the government and TEPCO, and a road map for the F1 decommissioning was drawn up. In the road map, the fuel debris removal from the reactors is scheduled to launch around 2020. In this study, the characteristics and technological issues of each potential treatment scenario were extracted, and the scenarios were prioritized in advance of formal evaluations in the future. The preliminary evaluation results show that long term storage and direct disposal have more positive aspects in terms of economic efficiency and radioactive waste generation. On the other hand, stabilizing processing, aqueous processing, and pyrochemical processing have been estimated to have more disadvantages in such aspects. (author)

  1. Visualization of information spreading among 'influencers' on Twitter after Fukushima Daiichi nuclear disaster

    International Nuclear Information System (INIS)

    Kobayashi, Saori; Onoue, Yosuke; Koyamada, Koji; Tsubokura, Masaharu; Torii, Hiroyuki A.; Uno, Kazuko

    2017-01-01

    In the aftermath of the Fukushima Daiichi nuclear disaster, there was confusion due to a flood of contradictory opinions about the effects of radiation. In this report data was collected of tweets relating to radiation in 2011. Our aim is to prevent such confusion in the future by considering improvements that should be made in communicating relevant information during times of large-scale disasters. Influencers, the individuals who had an impact on the spread of relevant information, are categorized in three groups based on the contents of their tweets. Our analysis showed that the influencers whose tweets were retweeted the most changed as time passed. We speculated that it was partially caused by the higher number of mutual mentions among the influencers in the group, and verified the hypothesis using network analysis. Results indicated that the density of connection among the influencers is relevant to the ease with which information spreads. (author)

  2. Fukushima Daiichi unit 1 uncertainty analysis--Preliminary selection of uncertain parameters and analysis methodology

    Energy Technology Data Exchange (ETDEWEB)

    Cardoni, Jeffrey N.; Kalinich, Donald A.

    2014-02-01

    Sandia National Laboratories (SNL) plans to conduct uncertainty analyses (UA) on the Fukushima Daiichi unit (1F1) plant with the MELCOR code. The model to be used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). However, that study only examined a handful of various model inputs and boundary conditions, and the predictions yielded only fair agreement with plant data and current release estimates. The goal of this uncertainty study is to perform a focused evaluation of uncertainty in core melt progression behavior and its effect on key figures-of-merit (e.g., hydrogen production, vessel lower head failure, etc.). In preparation for the SNL Fukushima UA work, a scoping study has been completed to identify important core melt progression parameters for the uncertainty analysis. The study also lays out a preliminary UA methodology.

  3. NIRS external dose estimation system for Fukushima residents after the Fukushima Dai-ichi NPP accident

    Science.gov (United States)

    Akahane, Keiichi; Yonai, Shunsuke; Fukuda, Shigekazu; Miyahara, Nobuyuki; Yasuda, Hiroshi; Iwaoka, Kazuki; Matsumoto, Masaki; Fukumura, Akifumi; Akashi, Makoto

    2013-04-01

    The great east Japan earthquake and subsequent tsunamis caused Fukushima Dai-ichi Nuclear Power Plant (NPP) accident. National Institute of Radiological Sciences (NIRS) developed the external dose estimation system for Fukushima residents. The system is being used in the Fukushima health management survey. The doses can be obtained by superimposing the behavior data of the residents on the dose rate maps. For grasping the doses, 18 evacuation patterns of the residents were assumed by considering the actual evacuation information before using the survey data. The doses of the residents from the deliberate evacuation area were relatively higher than those from the area within 20 km radius. The estimated doses varied from around 1 to 6 mSv for the residents evacuated from the representative places in the deliberate evacuation area. The maximum dose in 18 evacuation patterns was estimated to be 19 mSv.

  4. Tracking of Airborne Radionuclides from the Damaged Fukushima Dai-Ichi Nuclear Reactors by European Networks

    DEFF Research Database (Denmark)

    Masson, O.; Baeza, A.; Bieringer, J.

    2011-01-01

    Radioactive emissions into the atmosphere from the damaged reactors of the Fukushima Dai-ichi nuclear power plant (NPP) started on March 12th, 2011. Among the various radionuclides released, iodine-131 (131I) and cesium isotopes (137Cs and 134Cs) were transported across the Pacific toward the North...... period and spatial variations across more than 150 sampling locations in Europe made it possible to characterize the contaminated air masses. After the Chernobyl accident, only a few measurements of the gaseous 131I fraction were conducted compared to the number of measurements for the particulate...... reactors have provided a significant amount of new data on the ratio of the gaseous 131I fraction to total 131I, both on a spatial scale and its temporal variation. It can be pointed out that during the Fukushima event, the 134Cs to 137Cs ratio proved to be different from that observed after the Chernobyl...

  5. Nuclear accidents at the Fukushima Dai-ichi power plant. History, events and consequences

    International Nuclear Information System (INIS)

    Berniolles, Jean Marc

    2011-01-01

    Written few weeks after the accident, this article first recalls the circumstances (earthquake and tsunami), and then describes the accidental process within the primary vessels of the Fukushima Dai-ichi number 1, 2 and 3 reactors. The author then describes the interventions which aimed at cooling these three reactors, the problem faced for the storage of used fuels, and then the sequence of accidents: loss of cooling means leading to an explosion, problems faced in the different storage pools. He describes the various steps of recovery (primary cooling, electricity supply), discusses the consequences in terms of radioactivity releases in the plant environment with a comparison with Chernobyl, and also in terms of nature and quantity of radioactive elements. He comments radioactivity controls and measurements, evacuation measures, measurements performed by the IAEA, measurements of sea radioactivity, and the establishment of maps of ground radioactivity around the plant. He discusses the perspectives associated with these measurements for the surroundings of the Fukushima site

  6. The effects of the nuclear disaster at Fukushima Daiichi Nuclear Power Station on local governments

    International Nuclear Information System (INIS)

    Nakamura, Makoto; Dake, Kinji

    2012-01-01

    All Japan council of local governments with atomic power stations consisted of 24 reactor site and 6 neighboring local governments to solve reactor site related problems. Nuclear disaster at Fukushima Daiichi Nuclear Power Station affected member local governments to be forced in severe conditions such as 'removal of administrative function' or 'refuge over a wide district beyond local government area', not imagined before. The council set up working group for thirteen local governments themselves to investigate this disaster and find safety and prevention of disaster measures to be deployed in nuclear administration, which published report in March 2012. This article described outline of investigation and derived problems and direction of their solution. Main items were related with communication, resident evacuation, prevention of disaster system, and management of refuge site. (T. Tanaka)

  7. Report on achievements in fiscal 1998. Development of foaming eco-material using magazine waste papers. (The first fiscal year); 1998 nendo zasshi koshi wo mochiita happo seikei eko material no kaihatsu seika hokokusho (dai 1 nendo)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Such foaming materials as styro-foam, urethane and polyethylene greatly increase load on the environment when discarded, and are a problem as harmful rubbish. On the other hand, magazine waste papers have limitation as regenerated paper because their pulp fibers are cut off and deteriorated during use and regeneration. They are left unused without a prospect of re-use even if recovered. Under such a background, the present research and development is intended to develop magazine waste papers as a reusable cushioning material, commercialize the cushioning material as a low environment load type material, and promote reutilization of magazine waste papers. Specifically, development is performed on a manufacturing technology and a manufacturing equipment for a cushioning material having excellent biodegradation performance manufactured by mixing magazine waste papers with gelatin as a binder, and further by foaming and forming. The research and development items include: (1) development of a manufacturing technology for a foaming eco-material using magazine waste papers, (2) development of manufacturing equipment for the foaming eco-material, and (3) the market research thereon. This paper reports the achievements in the research and development of each item in fiscal 1998. (NEDO)

  8. Achievement report for fiscal 1998. Research and development of nano-structural materials for ceramic bearing application (the second year); 1998 nendo seika hokokusho. Ceramic bearing yo nano seigyo zairyo no kenkyu kaihatsu (dai 2 nendo)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Development is made on ceramic bearing using high-performance and low-cost nano-structural materials, and its application is performed to high-quality bearings suitable for energy conservation in automobiles and industrial machines, and bearings for office automation devices, electronics, and aeronautic and maritime development. To achieve these goals, raw material synthesizing technologies, forming technologies, structural control technologies, processing technologies and mass production technologies shall be established. Fiscal 1998 had the following achievements: establishment of nano-structure controlled ceramic material powder synthesizing technology (nano-lamination type composite powder made by using the beads mill co-precipitation method, nano-lamination type composite powder made by using the New Mymill co-precipitation method, nano-lamination type composite powder made by using the controlled liquid phase method, composite nano-structured gel, and nano-powder synthesis); near net forming technology for spherical ceramics; high-speed processing technology for ultra smooth surface; evaluation of rolling fatigue properties of ceramic bearings; and analysis and evaluation of nano-structured materials. Since this alumina-based ceramic bearing can be produced at reduced cost with performance comparable to silicon nitride based bearing, investigations and discussions are being given on the application thereof. (NEDO)

  9. Achievement report for fiscal 1998. Research and development of a multi-plant maintenance system (the first year); 1998 nendo seika hokokusho. Odanteki maintenance gijutsu no kenkyu kaihatsu (dai 1 nendo)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    This research and development is intended to structure a network centering around a center having systematized high-level maintenance technology, by utilizing the technological infrastructure having been built in local areas, together with element technologies possessed by national and private research institutes, universities and colleges. It is also purposed to establish a new industrial system for maintenance to realize high reliability, high operation rate and low cost in plants in certain areas. The present fiscal year had the following achievements: research and development of a maintenance system, a maintenance model, a maintenance vehicle, damage estimating technology for stationary parts such as piping, an anomaly diagnostic system using acoustic emission, an anomaly diagnostic system using wear particles in lubricant, an anti-wear material using surface modification, a lubrication control system, and an anomaly diagnostic system using ultrasonic waves. The research and development executing organization was divided into four groups for the maintenance system, maintenance model, maintenance vehicle, and maintenance tool. All groups have achieved the initial plans satisfactorily. (NEDO)

  10. Light Water Reactor Sustainability Program, U.S. Efforts in Support of Examinations at Fukushima Daiichi-2017 Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, Mitchell T. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-08-01

    Although the accident signatures from each unit at the Fukushima Daiichi Nuclear Power Station (NPS) [Daiichi] differ, much is not known about the end-state of core materials within these units. Some of this uncertainty can be attributed to a lack of information related to cooling system operation and cooling water injection. There is also uncertainty in our understanding of phenomena affecting: a) in-vessel core damage progression during severe accidents in boiling water reactors (BWRs), and b) accident progression after vessel failure (ex-vessel progression) for BWRs and Pressurized Water Reactors (PWRs). These uncertainties arise due to limited full scale prototypic data. Similar to what occurred after the accident at Three Mile Island Unit 2, these Daiichi units offer the international community a means to reduce such uncertainties by obtaining prototypic data from multiple full-scale BWR severe accidents. Information obtained from Daiichi is required to inform Decontamination and Decommissioning activities, improving the ability of the Tokyo Electric Power Company Holdings, Incorporated (TEPCO Holdings) to characterize potential hazards and to ensure the safety of workers involved with cleanup activities. This document, which has been updated to include FY2017 information, summarizes results from U.S. efforts to use information obtained by TEPCO Holdings to enhance the safety of existing and future nuclear power plant designs. This effort, which was initiated in 2014 by the Reactor Safety Technologies Pathway of the Department of Energy Office of Nuclear Energy Light Water Reactor (LWR) Sustainability Program, consists of a group of U.S. experts in LWR safety and plant operations that have identified examination needs and are evaluating TEPCO Holdings information from Daiichi that address these needs. Each year, annual reports include examples demonstrating that significant safety insights are being obtained in the areas of component performance, fission

  11. Review of Cytogenetic analysis of restoration workers for Fukushima Daiichi nuclear power station accident

    International Nuclear Information System (INIS)

    Suto, Yumiko

    2016-01-01

    Japan faced with the nuclear accident of the Fukushima Daiichi Nuclear Power Station (NPS) caused by the combined disaster of the Great East Japan Earthquake and the subsequent tsunamis on 11 March 2011. National Institute of Radiological Sciences received all nuclear workers who were engaged in emergency response tasks at the NPS and suspected of being overexposed to acute radiation. Biological dosimetry by dicentric chromosome assay was helpful for medical triage and management of the workers. When an unplanned radiation exposure occurs, biological dosimetry based on cytogenetic assays has been used to estimate the absorbed dose in the exposed individual to get useful information for the medical management of radiological casualties with suspected acute radiation syndrome (ARS). Nowadays, more cytogenetic assays to measure chromosomal aberrations, such as micronuclei in bi-nucleated cells, prematurely condensed chromosomes (PCCs) and inter-chromosomal exchanges detected by fluorescence in situ hybridization (FISH) techniques, are available. However, the dicentric chromosome assay (DCA) using peripheral blood lymphocytes is still considered to be the 'gold standard' of biological dosimetry for the radiation emergency medicine. Experimental protocols of DCA has been standardized and shared among laboratories all over the world. In fact, DCA was useful in previous radiation accidents, e.g. the Chernobyl accident in 1986, the Goiania accident in 1987, the JCO criticality accident in 1999 and the Tokyo electric power company (TEPCO) Fukushima Daiichi Nuclear Power Station (NPS) accident in 2011. The recent development of microscopic image analysis system with automatic metaphase finding and capturing functions was helpful for rapid detection of dicentric chromosomes to perform DCA for the Fukushima NPS restoration workers. (author)

  12. NARAC Modeling During the Response to the Fukushima Dai-ichi Nuclear Power Plant Emergency

    Energy Technology Data Exchange (ETDEWEB)

    Sugiyama, G; Nasstrom, J S; Probanz, B; Foster, K T; Simpson, M; Vogt, P; Aluzzi, F; Dillon, M; Homann, S

    2012-02-14

    This paper summarizes the activities of the National Atmospheric Release Advisory Center (NARAC) during the Fukushima Dai-ichi nuclear power plant crisis. NARAC provided a wide range of products and analyses as part of its support including: (1) Daily Japanese weather forecasts and hypothetical release (generic source term) dispersion predictions to provide situational awareness and inform planning for U.S. measurement data collection and field operations; (2) Estimates of potential dose in Japan for hypothetical scenarios developed by the Nuclear Regulatory Commission (NRC) to inform federal government considerations of possible actions that might be needed to protect U.S. citizens in Japan; (3) Estimates of possible plume arrival times and dose for U.S. locations; and (4) Plume model refinement and source estimation based on meteorological analyses and available field data. The Department of Energy/National Nuclear Security Administration (DOE/NNSA) deployed personnel to Japan and stood up 'home team' assets across the DOE complex to aid in assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. The DOE Nuclear Incident Team (NIT) coordinated response activities, while DOE personnel provided predictive modeling, air and ground monitoring, sample collection, laboratory analysis, and data assessment and interpretation. DOE deployed the Aerial Measuring System (AMS), Radiological Assistance Program (RAP) personnel, and the Consequence Management Response Team (CMRT) to Japan. DOE/NNSA home team assets included the Consequence Management Home Team (CMHT); National Atmospheric Release Advisory Center (NARAC); Radiation Emergency Assistance Center/Training Site (REAC/TS); and Radiological Triage. NARAC was activated by the DOE/NNSA on March 11, shortly after the Tohoku earthquake and tsunami occurred. The center remained on active operations through late May when DOE ended its deployment to Japan. Over 32 NARAC staff

  13. Status of the spent fuel in the reactor buildings of Fukushima Daiichi 1–4

    Energy Technology Data Exchange (ETDEWEB)

    Jäckel, Bernd S., E-mail: bernd.jaeckel@psi.ch

    2015-03-15

    The ratios of the radionuclides Cs-134g and Cs-137 deduced from measurements of liquid samples from the spent fuel pools in Fukushima Daiichi 1–4 are used to interpret the status of the spent fuel assemblies in the pools of the damaged reactor buildings. The different natures of the production of Cs-134g (neutron capture product of Cs-133) and Cs-137 (cumulative fission product from mass chain 137) and the different half-lives (2.06 years and 30.17 years respectively) require a complicated calculation of the mass and activity of the two nuclides. These masses are depending on the local burn up of the fuel, the burn up history and the radioactive decay. Calculation of the neutron capture product Cs-134g is particularly complicated, because the production of Cs-133 (stable cumulative fission product from mass chain 133) has to be taken into account. The neutron capture cross section for Cs-133 for thermal neutrons is well known, but the energy spectrum of the neutrons in a reactor includes higher energies according to the degree of moderation. Therefore the cross section was fitted from a gamma scan of spent fuel rods in a hot cell. The method of the calculation of the nuclide activities and the interpretation of the gamma measurements of the spent fuel pool samples from Fukushima Daiichi 1–4 are described in detail. It could be shown that at most only very minor mechanical damage of some spent fuel elements occurred during the accident and the later phase of the clearing work.

  14. Experimental investigation on molten pool representing corium composition at Fukushima Daiichi nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    An, Sang Mo, E-mail: sangmoan@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yueong-gu, Daejeon, 305-353 (Korea, Republic of); Song, Jin Ho [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yueong-gu, Daejeon, 305-353 (Korea, Republic of); Kim, Jong-Yun [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yueong-gu, Daejeon, 305-353 (Korea, Republic of); Radiochemistry & Nuclear Nonproliferation, University of Science & Technology, Gajeong-ro 217, Yuseong-gu, Daejeon, 34113 (Korea, Republic of); Kim, HwanYeol [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yueong-gu, Daejeon, 305-353 (Korea, Republic of); Naitoh, Masanori [The Institute of Applied Energy, 1-14-2 Nishi-shimbashi, 1-Chome, Minato-ku, Tokyo, 105-0003 (Japan)

    2016-09-15

    A configuration of molten core in the Fukushima Daiichi NPP (nuclear power plant) was investigated by a melting and solidification experiment. About 5 kg of a mixture, whose composition in terms of weight is UO{sub 2} (60%), Zr + ZrO{sub 2} (25%), stainless steel (14%), B{sub 4}C (1%), was melted in a cold crucible using an induction heating technique. It was shown that the solidified melt consists of upper crust and lower solidified ingot. The solidified ingot was separated into two layers. A physical and chemical analysis was performed for the samples taken from the solidified melt to investigate the morphology and chemical characteristics. It was found that the solidified ingot consists of a metal-rich layer on the top and an oxide-rich layer at the bottom. In addition, the oxide layer at the bottom has composition close to the initial charge composition and surrounded by a thin crust layer. It turned out that B{sub 4}C was more concentrated in the upper metal-rich layer. These findings provide important insights for understanding the core melt progression and taking proper post-accident recovery actions for the Fukushima Daiichi NPP. - Highlights: • A configuration of molten core in the Fukushima Daiich NPP unit 1 is investigated. • Corium ingot consists of metallic layer on the top and oxidic layer at the bottom. • Boron carbide was more concentrated in the upper metallic layer. • Two layered configuration would contribute to the post-accident recovery actions.

  15. NARAC Modeling During the Response to the Fukushima Dai-ichi Nuclear Power Plant Emergency

    International Nuclear Information System (INIS)

    Sugiyama, G.; Nasstrom, J.S.; Probanz, B.; Foster, K.T.; Simpson, M.; Vogt, P.; Aluzzi, F.; Dillon, M.; Homann, S.

    2012-01-01

    This paper summarizes the activities of the National Atmospheric Release Advisory Center (NARAC) during the Fukushima Dai-ichi nuclear power plant crisis. NARAC provided a wide range of products and analyses as part of its support including: (1) Daily Japanese weather forecasts and hypothetical release (generic source term) dispersion predictions to provide situational awareness and inform planning for U.S. measurement data collection and field operations; (2) Estimates of potential dose in Japan for hypothetical scenarios developed by the Nuclear Regulatory Commission (NRC) to inform federal government considerations of possible actions that might be needed to protect U.S. citizens in Japan; (3) Estimates of possible plume arrival times and dose for U.S. locations; and (4) Plume model refinement and source estimation based on meteorological analyses and available field data. The Department of Energy/National Nuclear Security Administration (DOE/NNSA) deployed personnel to Japan and stood up 'home team' assets across the DOE complex to aid in assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. The DOE Nuclear Incident Team (NIT) coordinated response activities, while DOE personnel provided predictive modeling, air and ground monitoring, sample collection, laboratory analysis, and data assessment and interpretation. DOE deployed the Aerial Measuring System (AMS), Radiological Assistance Program (RAP) personnel, and the Consequence Management Response Team (CMRT) to Japan. DOE/NNSA home team assets included the Consequence Management Home Team (CMHT); National Atmospheric Release Advisory Center (NARAC); Radiation Emergency Assistance Center/Training Site (REAC/TS); and Radiological Triage. NARAC was activated by the DOE/NNSA on March 11, shortly after the Tohoku earthquake and tsunami occurred. The center remained on active operations through late May when DOE ended its deployment to Japan. Over 32 NARAC staff members

  16. Cooperation in the Implementation of Safeguards at Fukushima Dai-ichi Site

    International Nuclear Information System (INIS)

    Kumekawa, H.; Usui, A.; Sano, K.; Ishii, T.; Ninagawa, J.; Namekawa, M.; Iso, S.; Nakamura, N.; Hirato, Y.; Murajiri, M.; Hori, K.; Oyama, K.; Takagi, A.; Hirabayashi, N.

    2015-01-01

    The accident at Fukushima Dai-ichi Nuclear Power Station caused by the Great East Japan Earthquake and tsunami in March 2011 had a major impact on the safeguards situation at the site. JSGO, NMCC, TEPCO and JAEA are tackling the challenges posed by the accident jointly with the IAEA and in cooperation with the US Department of Energy (DOE). From the day of the earthquake, JSGO and the IAEA have shared information on decommissioning activities and discussed how to deal with this difficult issue. In May 2012, the Fukushima Task Force was established. Its objective is to develop a holistic approach to safeguards implementation measures for the site, to monitor the re-establishment of safeguards, to facilitate discussion of relevant issues, and to consider possible approaches to longer-term safeguards challenges. All the fuels in spent fuel ponds in Units 5 and 6 and Common Spent Fuel Storage have been successfully re-verified. Re-verification of fuels kept in spent fuel pond in Unit 4 is underway. A special arrangement called SNOS (Short Notice Operational Support Activities) has been introduced to confirm non-diversion of declared material at Fukushima Dai-ichi site. Based on extensive information exchange, proactive discussions on safeguards approaches are being held for near-term issues. The damaged core material in Units 1-3 will pose extreme difficulties in longer-term. A special sub-group has been established under the task force to address the issues. Although lessons learned from past nuclear accidents resulting in damage of core material have some relevance, none of them can be directly applicable for Fukushima. Thus a foresighted and creative approach is needed. Close coordination with the IAEA and support from technically competent institutions in Japan and from abroad, such as DOE, are also essential to tackle the issues. (author)

  17. Additional examination on station blackout caused by tsunami in Fukushima Daiichi NPS

    International Nuclear Information System (INIS)

    Yamauchi, Daisuke; Date, Kenji; Mizokami, Masato; Honda, Takeshi; Nozaki, Kenichiro; Mizokami, Shinya; Endo, Ryohei

    2017-01-01

    This study is additional examination to verify in a more reliable way the assessment that the emergency AC power supply was lost due to tsunami at Fukushima Daiichi Nuclear Power Station. It confirmed the relationship between the path length of tsunami intrusion reaching each power supply facility and the function loss time. As a result of examination, it was confirmed that as the path length of the tsunami intrusion reaching each power supply facility was longer, the function loss time tended to be later. So, conventional assessment that the function of each power supply facility was lost due to the run-up and flooding of tsunami has become more probable. For facilities, where the overall trend and the loss time of function were divergent, it was found that there were scenarios that could reasonably be explained. Based on the fact that the Fukushima Daiichi Nuclear Power Station lost power due to the tsunami, Kashiwazaki-Kariwa Nuclear Power Station carries out various safety measures. First of all, as the measures to prevent accidents caused by tsunami, the following have been applied: (1) prevention of the inflow of tsunamis into premises, (2) water prevention of the areas installed with important equipment, (3) securement of seawater at the time of backwashing, (4) storage of portable equipment at high ground, (5) installation of tsunami surveillance cameras. To prepare for the loss of power supply, this station implemented power supply facilities such as generator cars and distribution boards, as well as the placement of power supply cars at high ground. (A.O.)

  18. Fukushima Daiichi - delivery of contaminated water into the Pacific ocean and possible consequences for the marine ecosystem

    International Nuclear Information System (INIS)

    Nies, Hartmut

    2015-01-01

    The nuclear power plant Fukushima Daiichi is sited at the coast of the Japanese island Honshu. Most of the cooling water for the three destroyed reactors units 1-3 and the nuclear fuel in the spent fuel pool of unit-4 were uncontrolled delivered into the groundwater and the Pacific Ocean. As a consequence high concentrations of I-131, Cs-134 and Cs-137 in the coastal waters have to be assumed. The contribution analyzed the possible consequences for the marine ecosystem. A drift time of 5 to 7 years toward the coast of North America is expected. The planning of the marine monitoring program MEXT is described. Radiation measurements in the coastal water up to 200 km distance from Daiichi were performed. The highest radionuclide concentrations of Cs-137 and Cs-134 were found in the fine grained sediments. No increased radioactivity in seafood is expected.

  19. Analysis of comparative English media reports about the aftermath of the Fukushima Daiichi Nuclear Power Plant disaster

    International Nuclear Information System (INIS)

    Sakai, Makoto

    2015-01-01

    I performed a comparative analysis of media reports that related to the aftermath of the Fukushima Daiichi nuclear power plant disaster. I researched advanced countries' media reports on the nuclear power technology field, and especially those from the United States, the United Kingdom, Germany, and France. For this research, I gathered news texts on the aftermath of the Fukushima Daiichi nuclear power plant disaster from newspapers and websites. Then I categorized them into four groups, to analyze what the media in the above four counties have reported about Fukushima: 'same context' (typical context), 'a different context from other countries' media', 'a changing context from before', and 'proposals for the decommissioning and reconstruction process in Japan'. (author)

  20. Consumer Perceptions of Seafood Industries in the Wake of the Deepwater Horizon Oil Spill and Fukushima Daiichi Nuclear Disaster

    OpenAIRE

    McKendree, Melissa G.S.; Ortega, David L.; Widmar, Nicole Olynk; Wang, H. Holly

    2013-01-01

    The impact of environmental disasters on consumers’ perceptions and preferences for specific food items has seldom been studied in the applied economics literature. Recent aquatic disasters, namely the Deepwater Horizon Oil Spill and Fukushima Daiichi Nuclear Disaster, have had profound impacts on fisheries serving US consumers and on agribusinesses within the aquaculture industry. This study explores consumer preferences using a nation-wide representative sample, and finds that twenty-nine p...

  1. Accident on the TEPCO reactors of Fukushima-Daiichi. A focus on the situation in January 2013

    International Nuclear Information System (INIS)

    2013-01-01

    After a brief recall of the accident of the Fukushima-Daiichi nuclear power station and a brief description of the general condition of the installations after the accident, this report proposes an overview of actions performed by TEPCO to control the installations, the actions performed to control effluents and releases. It presents the action plan for the control's recovery of installations, and briefly evokes the situation for other electronuclear reactors in Japan

  2. Accident at the Fukushima Dai-ichi Nuclear Power Stations of TEPCO —Outline & lessons learned—

    OpenAIRE

    TANAKA, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety o...

  3. Partisan amplification of risk: American perceptions of nuclear energy risk in the wake of the Fukushima Daiichi disaster

    International Nuclear Information System (INIS)

    Yeo, Sara K.; Cacciatore, Michael A.; Brossard, Dominique; Scheufele, Dietram A.; Runge, Kristin; Su, Leona Y.; Kim, Jiyoun; Xenos, Michael; Corley, Elizabeth A.

    2014-01-01

    Aim: This study examines risk perceptions toward nuclear power before and after the Fukushima Daiichi disaster using nationally representative survey samples of American adults. Scope: On March 11, 2011, a magnitude 8.4 earthquake, the largest in the nation's history, occurred off the coast of Japan. The earthquake produced a devastating tsunami that flooded areas of the Fukushima Daiichi nuclear plant and resulted in a loss of power to the plant's cooling system. In the weeks that followed, the world watched as Japanese and international nuclear power safety experts scrambled to contain the damage and prevent a full meltdown. Although the Fukushima Daiichi disaster was heavily covered in media, there is little empirical research on how this coverage impacted audience risk perceptions. Our analysis goes beyond examining aggregate risk perceptions, instead focusing on how specific sub-populations responded to the disaster. Conclusion: We found that ideological groups responded differently to the events in Japan. In particular, risk perceptions among conservatives decreased following the incident. Moreover, we found that media use exacerbated these effects. We discuss possible explanations for these findings. - Highlights: • We explored American risk perceptions of nuclear energy pre- and post-Fukushima. • Impacts of the disaster endured, likely due to relatively high media coverage. • Conservatives who paid more attention to media perceived less risk post-Fukushima. • Media coverage can serve to polarize opinions instead of mainstreaming them

  4. Effect of evacuation on liver function after the Fukushima Daiichi Nuclear Power Plant accident: The Fukushima Health Management Survey.

    Science.gov (United States)

    Takahashi, Atsushi; Ohira, Tetsuya; Hosoya, Mitsuaki; Yasumura, Seiji; Nagai, Masato; Ohira, Hiromasa; Hashimoto, Shigeatsu; Satoh, Hiroaki; Sakai, Akira; Ohtsuru, Akira; Kawasaki, Yukihiko; Suzuki, Hitoshi; Kobashi, Gen; Ozasa, Kotaro; Yamashita, Shunichi; Kamiya, Kenji; Abe, Masafumi

    2017-04-01

    The Great East Japan Earthquake and subsequent Fukushima Daiichi Nuclear Power Plant accident caused residents to switch from their normal lives to lives focused on evacuation. We evaluated liver function before and after this disaster to elucidate the effects of evacuation on liver function. This study was a longitudinal survey of 26,006 Japanese men and women living near the Fukushima Daiichi Nuclear Power Plant. This study was undertaken using data from annual health checkups conducted for persons aged 40-90 years between 2008 and 2010. Follow-up examinations were conducted from June 2011 to the end of March 2013, with a mean follow up of 1.6 years. Changes in liver function before and after the disaster were compared among evacuees and non-evacuees. We also assessed groups according to alcohol drinking status. The prevalence of liver dysfunction significantly increased in all participants from 16.4% before to 19.2% after the disaster. The incidence of liver dysfunction was significantly higher in evacuees than in non-evacuees. Multivariate logistic regression analysis showed that evacuation was significantly associated with liver dysfunction among residents. This is the first study to show that evacuation due to the Fukushima Daiichi nuclear power plant disaster was associated with an increase in liver dysfunction. Copyright © 2016 The Authors. Production and hosting by Elsevier B.V. All rights reserved.

  5. Spatial distribution of Iodine-129 in surface soil around the Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Miyake, Yasuto; Tagi, Kazuhiro; Matsuzaki, Hiroyuki; Fujiwara, Takeshi; Saito, Takumi; Yamagata, Takeyasu; Tsuchiya, Yoko; Nakano, Chuichiro; Honda, Maki

    2011-01-01

    Due to the accident at the Fukushima Daiichi nuclear power plant, which was caused by the Great East Japan Earthquake, a lot of radioactive materials were released into the environment. Among them, Iodine-131, which has a short half-life of 8 days, is thought to be hardly detected after the accident is concluded. It is very important to research how leaked out Iodine-131 was diffused in order to estimate the health impact of radiation at the time of the accident. On the other hand, Iodine-129, which was leaked out and was thought to act chemically-identically as Iodine-131, has an extremely long half-life of 15.7 million years and we are able to measure it equally after the accident. By following the trail of Iodine-129, it is considered to estimate the distribution of Iodine-131. To do this, at first, it is essential to measure simultaneously Iodine-131 and Iodine-129 in the same sample picked from near-the Fukushima Daiichi nuclear power plant and examine the relation between them (for example, the isotopic ratio of Iodine derived from the nuclear power plant (I-129/I-131)). At this study, we measured Iodine-129 in surface soil within 60 kilometers of the Fukushima Daiichi nuclear power plant, which was picked by research team of Nuclear Engineering Research Laboratory, Faculty of Engineering, the University of Tokyo. We discuss Iodine-129 derived from the nuclear power plant by considering the concentration range, the relation of a distance or a direction from the nuclear power plant, and the relation between I-129 and other radioactive nuclides (Cs-134, Cs-137, I-131). Since Iodine-129, which had been leaked out from the nuclear fuel reprocessing plant in Europe, was already transferred to Japan by way of the atmospheric transportation before the accident, it is important to distinguish between Iodine-129 from this accident and from the reprocessing plant. Then, we want to obtain the I-129/I-131 ratio originating in the accident precisely and discuss the

  6. The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt

    International Nuclear Information System (INIS)

    2013-01-01

    Following the March 2011 accident at the Fukushima Daiichi nuclear power plant, all NEA member countries took early action to ensure and confirm the continued safety of their nuclear power plants and the protection of the public. After these preliminary safety reviews, all countries with nuclear facilities carried out comprehensive safety reviews, often referred to as 'stress tests', which reassessed safety margins of nuclear facilities with a primary focus on challenges related to conditions experienced at the Fukushima Daiichi nuclear power plant, for example extreme external events and the loss of safety functions, or capabilities to cope with severe accidents. As appropriate, improvements are being made to safety and emergency response systems to ensure that nuclear power plants are capable of withstanding events that lead to loss of electrical power and/or cooling capability. In the weeks following the accident, the NEA immediately began establishing expert groups in the nuclear safety and radiological protection areas, as well as contributing to information exchange with the Japanese authorities and other international organisations. It promptly provided a forum for high-level decision makers and regulators within the G8-G20 frameworks. The NEA actions taken at the international level in response to the accident have been carried out primarily by the three NEA standing technical committees concerned with nuclear and radiation safety issues - the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Radiation Protection and Public Health (CRPPH) - under the leadership of the CNRA. More than two years following the accident, the NEA continues to assist the Japanese authorities in dealing with their nuclear safety and recovery efforts as well as to facilitate international co-operation on nuclear safety and radiological protection matters. It is strongly supporting the establishment of

  7. Analytics of Radioactive Materials Released in the Fukushima Daiichi Nuclear Accident

    Energy Technology Data Exchange (ETDEWEB)

    Egarievwe, Stephen U. [Nuclear Engineering and Radiological Science Center, Alabama A and M University, Huntsville, AL (United States); Nuclear Engineering Department, University of Tennessee, Knoxville, TN (United States); Coble, Jamie B.; Miller, Laurence F. [Nuclear Engineering Department, University of Tennessee, Knoxville, TN (United States)

    2015-07-01

    The 2011 Fukushima Daiichi nuclear accident in Japan resulted in the release of radioactive materials into the atmosphere, the nearby sea, and the surrounding land. Following the accident, several meteorological models were used to predict the transport of the radioactive materials to other continents such as North America and Europe. Also of high importance is the dispersion of radioactive materials locally and within Japan. Based on the International Atomic Energy Agency (IAEA) Convention on Early Notification of a nuclear accident, several radiological data sets were collected on the accident by the Japanese authorities. Among the radioactive materials monitored, are I-131 and Cs-137 which form the major contributions to the contamination of drinking water. The radiation dose in the atmosphere was also measured. It is impractical to measure contamination and radiation dose in every place of interest. Therefore, modeling helps to predict contamination and radiation dose. Some modeling studies that have been reported in the literature include the simulation of transport and deposition of I-131 and Cs-137 from the accident, Cs-137 deposition and contamination of Japanese soils, and preliminary estimates of I-131 and Cs-137 discharged from the plant into the atmosphere. In this paper, we present statistical analytics of I-131 and Cs-137 with the goal of predicting gamma dose from the Fukushima Daiichi nuclear accident. The data sets used in our study were collected from the IAEA Fukushima Monitoring Database. As part of this study, we investigated several regression models to find the best algorithm for modeling the gamma dose. The modeling techniques used in our study include linear regression, principal component regression (PCR), partial least square (PLS) regression, and ridge regression. Our preliminary results on the first set of data showed that the linear regression model with one variable was the best with a root mean square error of 0.0133 μSv/h, compared

  8. Evaluation of short- and long-term fission product sources at the Fukushima Daiichi NPP

    International Nuclear Information System (INIS)

    Uchida, Shunsuke; Naitoh, Masanori; Suzuki, Hiroaki; Okada, Hidetoshi; Pellegrini, Marco; Achilli, Andrea; Hanamoto, Yukio; Sasaki, Hiroaki

    2014-01-01

    Research on fission product (FP) behaviors used to be one of the most important subjects in water chemistry but it is not done nowadays as a consequence of the increased integrity of nuclear fuels and the minimization of FP release into the environment. Evaluation of FP release into the environment is still one of the key issues for severe accident analysis, though. Although there have been a long quiet period in nuclear safety research, how to detect initiation of severe accidents, how to prevent them and how to mitigate them are still important subjects for nuclear engineering, and how to control the severe accidents after their occurrence, especially how to control FP release into the environment, has seldom been discussed in the water chemistry group recently. The paper is intended to address the issue of fewer activities for FP studies. FP sources are divided into two categories, short- and long-term FP sources. Short-term FP source can be evaluated based on the measured data obtained from monitoring posts (MPs), which give us clear evidence on the importance of radioactive iodine and cesium releases into the environment. It used to be considered that during primary containment vessel (PCV) venting, release of each element, e.g., iodine and cesium, was determined by the suppression pool scrubbing efficiency and most of the cesium would likely be removed in the pool due to its large scrubbing efficiency. But as a result of analyzing the MP data at early stage of the Fukushima Daiichi nuclear power plant (NPP) accident, it was confirmed that the releases of both elements were in proportion to their inventories in the reactors and their scrubbing efficiencies were almost the same. The scrubbing efficiency which increased with the pool water temperature became almost the same for iodine and cesium around the pool water boiling temperature. As a result of the mass balance analysis for FPs in the contaminated water accumulated in the Fukushima Daiichi plant site, it

  9. Analytics of Radioactive Materials Released in the Fukushima Daiichi Nuclear Accident

    International Nuclear Information System (INIS)

    Egarievwe, Stephen U.; Coble, Jamie B.; Miller, Laurence F.

    2015-01-01

    The 2011 Fukushima Daiichi nuclear accident in Japan resulted in the release of radioactive materials into the atmosphere, the nearby sea, and the surrounding land. Following the accident, several meteorological models were used to predict the transport of the radioactive materials to other continents such as North America and Europe. Also of high importance is the dispersion of radioactive materials locally and within Japan. Based on the International Atomic Energy Agency (IAEA) Convention on Early Notification of a nuclear accident, several radiological data sets were collected on the accident by the Japanese authorities. Among the radioactive materials monitored, are I-131 and Cs-137 which form the major contributions to the contamination of drinking water. The radiation dose in the atmosphere was also measured. It is impractical to measure contamination and radiation dose in every place of interest. Therefore, modeling helps to predict contamination and radiation dose. Some modeling studies that have been reported in the literature include the simulation of transport and deposition of I-131 and Cs-137 from the accident, Cs-137 deposition and contamination of Japanese soils, and preliminary estimates of I-131 and Cs-137 discharged from the plant into the atmosphere. In this paper, we present statistical analytics of I-131 and Cs-137 with the goal of predicting gamma dose from the Fukushima Daiichi nuclear accident. The data sets used in our study were collected from the IAEA Fukushima Monitoring Database. As part of this study, we investigated several regression models to find the best algorithm for modeling the gamma dose. The modeling techniques used in our study include linear regression, principal component regression (PCR), partial least square (PLS) regression, and ridge regression. Our preliminary results on the first set of data showed that the linear regression model with one variable was the best with a root mean square error of 0.0133 μSv/h, compared

  10. Fukushima Daiichi Nuclear Accident; based on the Final Report of Atomic Energy Society of Japan

    Science.gov (United States)

    Sekimura, Naoto

    2014-09-01

    The Atomic Energy Society of Japan (AESJ) published the Final Report of the AESJ Investigation Committee on Fukushima Daiichi NPS Accident in March 2014. The AESJ is responsible to identify the underlying root causes of the accident through technical surveys and analyses, and to offer solutions for nuclear safety. At the Fukushima Daiichi, Units 1 to 3, which were under operation, were automatically shut down at 14:46 on March 11, 2011 by the Tohoku District-off the Pacific Ocean Earthquake. About 50 minutes later, the tsunami flooded and destroyed the emergency diesel generators, the seawater cooling pumps, the electric wiring system and the DC power for Units 1, 2 and 4, resulting in loss of all power except for an air-cooled emergency diesel generator at Unit 6. Unit 3 lost all AC power, and later lost DC before dawn of March 13. Cooling the reactors and monitoring the results were heavily dependent on electricity for high-pressure water injection, depressurizing the reactor, low pressure water injection, and following continuous cooling. In Unit 3, for example, recent re-evaluation in August 2014 by TEPCO shows that no cooling water was injected into the reactor core region after 8 PM on March 12, leading to the fuel melting from 5:30 AM on March 13. Even though seawater was injected from fire engines afterwards, the rupture of pressure vessel was caused and the majority of melted fuel dropped into the containment vessel of Unit 3. The estimation of amount of radioactive materials such as Xe-133, I-131, Cs-137 and Cs-134, emitted to the environment from Units 1 to 3 is discussed in the presentation. Direct causes of the accident identified in the AESJ Report were, 1) inadequate tsunami measures, 2) inadequate severe accident management measures and 3) inadequate emergency response, post-accident management/mitigation, and recovery measures. These were caused by the following underlying factors, i.e., a) lack of awareness on the roles and responsibilities by

  11. Introduction of new terms and lessons for radiological protection after Fukushima Dai-Ichi accident

    International Nuclear Information System (INIS)

    Singh, Vishwanath P.; Managanvi, S.S.; Bhat, H.R.

    2012-01-01

    The nuclear accidents in the world are very few among various types of operating facilities. However when an accident happened, we have learnt a lot to improve the philosophy, term, definitions, document preparation, equipment's requirement, supporting systems, awareness program and restriction etc. After Fukushima Dai-ichi we have learnt a lot, in this view this paper has been prepared to discuss for radiological protection aspects. Discussion: The probability of nuclear accidents is negligible but when happens, it opens new doors of lessons for radiological protection practices for occupational workers, emergency workers for damage control to prevent catastrophic situation/rescue to life saving actions and the member of the public. The Chernobyl and Three Mile Island accidents have provided a lot experiences for management of emergency situations, documentation, radiation emergency preparedness, emergency equipment's, concept of defense-in-depth, emergency planning zone (EPZ), accidental dose limits, estimation of source term and public dose, intervention levels, decision supporting system, remedial actions in public domain; decontamination of person, houses/building and land and etc. Recent Fukushima Dai-ichi accident in Japan was managed in appreciable manner but still new definitions and lessons for radiological protection have been emerged out. The present paper discusses difficulties w. r. t. the radiological aspects observed/faced by Japanese during nuclear crises. The accident introduced new terms as Natural Dose Rate Unit (NDRU), voluntary evacuation, deliberate evacuation area, restricted area and difference between evacuation zone and EPZ. The Fukushima accident has enforced worldwide regulators and operators to review the individual dose limit and amendment for raise in the dose limit during accident, availability of efficient/adequate quantities of personal dosimeter in public domain, collection arrangement of bulk amount of radioactive wastes

  12. ABWR1. A Generation III.7 reactor after the Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Sato, Takashi; Matsumoto, Keiji; Kurosaki, Toshikazu; Taguchi, Keisuke

    2015-01-01

    iB1350 stands for an innovative, intelligent and inexpensive BWR 1350. It is the first Generation III.7 reactor after the Fukushima Daiichi accident. It has incorporated lessons learned from the Fukushima Daiichi accident and WENRA safety objectives. It has innovative safety to cope with devastating natural disasters including a giant earthquake, a large tsunami and a monster hurricane. The iB1350 can survive passively such devastation and a very prolonged SBO without any support from the outside of a site up to 7 days even preventing core melt. It, however, is based on the well-established proven ABWR design. The NSSS is exactly the same as that of the current ABWR. As for safety design it has a double cylinder RCCV (Mark W containment) and an in-depth hybrid safety system (IDHS). The Mark W containment has double FP confinement barriers and the in-containment filtered venting system (IFVS) that enable passively no emergency evacuation outside the immediate vicinity of the plant for a SA. It has a large volume to hold hydrogen, a core catcher, a passive flooding system and an innovative passive containment cooling system (iPCCS) establishing passively practical elimination of containment failure even in a long term. The IDHS consists of 4 division active safety systems for a DBA, 2 division active safety systems for a SA and built-in passive safety systems (BiPSS) consisting of an isolation condenser (IC) and the iPCCS for a SA. The IC/PCCS pools have enough capacity for 7 day grace period. The IC/PCCS heat exchangers, core and spent fuel pool are enclosed inside the CV building and protected against a large airplane crash. The iB1350 can survive a large airplane crash only by the CV building and the built-in passive safety systems therein. The dome of the CV building consists of a single wall made of steel and concrete composite. This single dome structure facilitates a short-term construction period and cost saving. The CV diameter is smaller than that of most

  13. Analysis of the accident at Fukushima Daiichi nuclear power plant in an A BWR reactor

    International Nuclear Information System (INIS)

    Escorcia O, D.; Salazar S, E.

    2016-09-01

    The present work aims to recreate the accident occurred at the Fukushima Daiichi nuclear power plant in Japan on March 11, 2011, making use of an academic simulator of forced circulation of the A BWR reactor provided by the IAEA to know the scope of this simulator. The simulator was developed and distributed by the IAEA for academic purposes and contains the characteristics and general elements of this reactor to be able to simulate transients and failures of different types, allowing also to observe the general behavior of the reactor, as well as several phenomena and present systems in the same. Is an educational tool of great value, but it does not have a scope that allows the training of plant operators. To recreate the conditions of the Fukushima accident in the simulator, we first have to know what events led to this accident, as well as the actions taken by operators and managers to reduce the consequences of this accident; and the sequence of events that occurred during the course of the accident. Differences in the nuclear power plant behavior are observed and interpreted throughout the simulation, since the Fukushima plant technology and the simulator technology are not the same, although they have several elements in common. The Fukushima plant had an event that by far exceeded the design basis, which triggered in an accident that occurred in the first place by a total loss of power supply, followed by the loss of cooling systems, causing a level too high in temperature, melting the core and damaging the containment accordingly, allowing the escape of hydrogen and radioactive material. As a result of the simulation, was determined that the scope of the IAEA academic simulator reaches the entrance of the emergency equipment, so is able to simulate almost all the events occurred at the time of the earthquake and the arrival of the tsunami in the nuclear power plant of Fukushima Daiichi. However, due to its characteristics, is not able to simulate later

  14. Mental health problems after the 2011 Fukushima Dai-ichi nuclear power plant accident

    International Nuclear Information System (INIS)

    Niwa, Shin-ichi

    2012-01-01

    The name of Fukushima has now become well-known worldwide after Hiroshima and Nagasaki as the third place exposed to radiation in Japan. This radiation pollution has severely damaged the chief industries of Fukushima Prefecture, namely agriculture, fishery, and tourist industry. It has also stimulated strong anxious feelings among parents with young children. The accident has caused a critical situation in the psychiatric and mental health services in Fukushima as well. Five hospitals with psychiatric beds within 30 km from the Fukushima Dai-ichi Nuclear Power Plant were ordered to transfer their inpatients to other hospitals outside the designated 30 km-areas and to close down the hospitals immediately after the nuclear plant accident. In total, more than 800 psychiatric beds disappeared in an instant, and 1,228 persons including psychiatric inpatients and residents of elderly people nursing homes were transferred to other facilities far away. Rational explanation that low-level radiation in Fukushima will not do harm to people did not necessarily relieve existing anxiety among people. The terms 'safety' and 'relief' are usually used in combination; however, 'relief' was separated from 'safety' this time in Fukushima. People gradually began to feel 'relieved', when they themselves got involved in the cleaning work of radiation although its effect remained ambiguous. Now we have the following mental health problems after the 2011 Fukushima Dai-ichi nuclear power plant accident; recovery and maintenance of treatment systems for psychiatric patients in the affected areas, efforts for early detection and intervention of depression, severe stress disorder, adaptation disorder, and alcohol abuse which are expected to occur due to the earthquake and radiation pollution, prevention of suicides, relief from anxiety resulting from radiation pollution, adequate treatment of mental problems among children with long-term evacuation, prevention of fall in physical and mental

  15. Lessons Learned from the Fukushima Daiichi Accident, Actions Taken and Challenges Ahead

    International Nuclear Information System (INIS)

    Shimizu, Y.

    2016-01-01

    On 19 September, 2012, the Nuclear Regulation Authority (NRA) was established in light of lessons learned from the Fukushima Daiichi accident of 11 March 2011, to ensure that such accidents never happen again, to restore public trust in regulator both in Japan and abroad and to rebuild and foster a genuine safety culture by placing the highest priority on public safety. The NRA, an independent administrative commission of the Ministry of the Environment, is organized to separate the regulatory functions from the promotional functions of the use of nuclear energy within the government, and to independently implement its duties from the perspectives of neutrality and fairness based on its expertise. Having learned the lessons from the Fukushima Daiichi accident and with reference to IAEA safety standards, since its establishment, the NRA has endeavored to strengthen the regulatory requirements, in particular, for hazards such as tsunamis and earthquakes which may lead to common cause failures, and countermeasures against severe accidents. Under the new regulatory scheme, a back-fitting system was introduced. Emergency preparedness and response measures for nuclear facilities were also enhanced. As of end of March 2016, five reactors received NRA’s permission for changing their reactor installations based on the new regulatory requirements, and two nuclear power reactors have restarted their operations. In January 2016, at the request of Japan, the IAEA sent the IRRS mission team to Japan to assess the regulatory framework for nuclear and radiation safety. Through the self-assessment prior to the mission, the NRA has developed 22 action plans, including a) improvement of regulatory inspection, b) capacity building, and c) strengthening of safety research capability. The mission team has found that Japan’s nuclear regulator has demonstrated independence and transparency since it was set up in 2012. The team also noted that the NRA needs to improve the inspection

  16. Estimation of marine source-term following Fukushima Dai-ichi accident

    International Nuclear Information System (INIS)

    Bailly du Bois, P.; Laguionie, P.; Boust, D.; Korsakissok, I.; Didier, D.; Fiévet, B.

    2012-01-01

    Contamination of the marine environment following the accident in the Fukushima Dai-ichi nuclear power plant represented the most important artificial radioactive release flux into the sea ever known. The radioactive marine pollution came from atmospheric fallout onto the ocean, direct release of contaminated water from the plant and transport of radioactive pollution from leaching through contaminated soil. In the immediate vicinity of the plant (less than 500 m), the seawater concentrations reached 68 000 Bq.L −1 for 134 Cs and 137 Cs, and exceeded 100 000 Bq.L −1 for 131 I in early April. Due to the accidental context of the releases, it is difficult to estimate the total amount of radionuclides introduced into seawater from data obtained in the plant. An evaluation is proposed here, based on measurements performed in seawater for monitoring purposes. Quantities of 137 Cs in seawater in a 50-km area around the plant were calculated from interpolation of seawater measurements. The environmental halftime of seawater in this area is deduced from the time-evolution of these quantities. This halftime appeared constant at about 7 days for 137 Cs. These data allowed estimation of the amount of principal marine inputs and their evolution in time: a total of 27 PBq (12 PBq–41 PBq) of 137 Cs was estimated up to July 18. Even though this main release may be followed by residual inputs from the plant, river runoff and leakage from deposited sediments, it represents the principal source-term that must be accounted for future studies of the consequences of the accident on marine systems. The 137 Cs from Fukushima will remain detectable for several years throughout the North Pacific, and 137 Cs/ 134 Cs ratio will be a tracer for future studies. Highlights: ► Fukushima Dai-ichi accident is the most important artificial radioactive release flux into the sea. ► Quantities of 137 Cs in seawater are deduced from individual measurements. ► Local concentrations in

  17. MDEP Design-Specific Common Position CP-EPRWG-02. Common position addressing Fukushima Daiichi-related issues

    International Nuclear Information System (INIS)

    2015-10-01

    A severe accident involving several units took place in Japan at Fukushima Daiichi nuclear power plant (NPP) in March 2011. The immediate cause of the accident was an earthquake followed by a tsunami coupled with inadequate provisions against the consequences of such events in the design. Opportunities to improve protection against a realistic design basis tsunami were not taken. As a consequence of the tsunami, safety equipment and the related safety functions were lost at the plant, leading to core damage in three units and subsequently to large radioactive releases (INES 7). Several studies have already been performed to better understand the accident progression and detailed technical studies are still in progress in Japan and elsewhere. In the meantime, on-going studies on the behaviour of NPPs in very severe situations, similar to Fukushima Daiichi, seek to identify potential vulnerabilities in plant design and operation; to suggest reasonably practicable upgrades; or to recommend enhanced regulatory requirements and guidance to address such situations. Likewise, agencies around the world that are responsible for regulating the design, construction and operation of EPR plants are engaged in similar activities. The MDEP EPR Working Group (EPRWG) members consist of members from the United States, the United Kingdom, France, Finland, China, India and Sweden. Because not all of these countries have completed the regulatory review of their EPR applications yet, this paper identifies common preliminary approaches to address potential safety improvements for EPR plants, as well as common general expectations for new nuclear power plants, as related to lessons learned from the Fukushima Daiichi accident or Fukushima Daiichi-related issues. After the safety reviews of the EPR design applications that are currently in review are completed, the regulators will update this paper to reflect their safety conclusions regarding the EPR design and how the design could be

  18. Direction on characterization of fuel debris for defueling process in Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    Yano, Kimihiko; Kitagaki, Toru; Ikeuchi, Hirotomo; Wakui, Ryohei; Higuchi, Hidetoshi; Kaji, Naoya; Koizumi, Kenji; Washiya, Tadahiro

    2013-01-01

    For the decommissioning of Fukushima Daiichi Nuclear Power Station (1F), defueling of the fuel debris in the reactor core of Units 1-3 is planned to start within 10 years. Preferential items in the characterization of the fuel debris were identified for this work, in which the procedure and handling tools were assumed on the basis of information on 1F and experience after the Three Mile Island Unit 2 (TMI-2) accident. The candidates for defueling tools for 1F were selected from among the TMI- 2 defueling tools. It was found that they could be categorized into six groups according to their operating principles. The important properties of the fuel debris for defueling were selected considering the effect of the target materials on the tool performance. The selected properties are shape, size, density, thermal conductivity, heat capacity, melting point, hardness, elastic modulus, and fracture toughness. Of these properties, the mechanical properties (hardness, elastic modulus, fracture toughness) were identified as preferential items, because too few data on these characteristics of fuel debris are available in past severe accident studies. (authors)

  19. Local area distribution of fallout radionuclides from Fukushima Daiichi Nuclear Power Plant determined by autoradiography analysis

    International Nuclear Information System (INIS)

    Sakamoto, Fuminori; Ohnuki, Toshihiko; Kozai, Naofumi; Igarashi, Shosuke; Yamasaki, Shinya; Yoshida, Zenko; Tanaka, Shunichi

    2012-01-01

    The environmental behavior of radioactive Cs in the fallout from the accident of the Fukushima Daiichi Nuclear Power Plant has been studied by measuring its spatial distribution on/in trees, plants, and surface soil beneath the plants using autoradiography analysis. The results of autoradiography analysis showed that radioactive Cs was distributed on the branches and leaves of trees that were present during the accident and that only a small fraction of radioactive Cs was transported to new branches and leaves grown after the accident. Radioactive Cs was present on the grass and rice stubble on the soils, but not in the soils beneath the grass and rice stubble, indicating that the radioactive Cs was deposited on the grass and the rice plant. In addition, the ratio of the radioactive Cs that penetrated into the soil layer by weathering was very small two months after the accident. These results indicate that trees and other plants are the reservoir of the fallout Cs and function to retard the fallout Cs migration with rain water. (author)

  20. IAEA report on the Fukushima-Daiichi accident and safety standards

    International Nuclear Information System (INIS)

    Mizumachi, Wataru

    2011-01-01

    On March 11th, 2011, 4th largest earthquake attacked Fukushima Nuclear Power Plant and around one hour later, the enormous Tsunami attacked it also. After the large earthquake attacked, the automatic shutdown was performed and the emergency diesel generators automatically started and Isolation condenser cooled down the core for unit 1 and RCIC cooled down the cores for unit 2 and 3. However, the large Tsunami damaged all emergency diesel generators and all ECCS pumps. The core melted and the hydrogen gas were generated by the steam and the zircaloy reaction. The hydrogen leaked into the reactor building and then the reactor building blasted by the hydrogen. IAEA has organized the Great East Japan Earthquake Expert Mission on Fukushima-daiichi accident and they reported to the formal meeting in the headquater in Viena. They made 15 conclusions and 16 lessons and learned. IAEA chairman officially summarized 28 recommendations from them. USNRC published 'Recommendations for Enhanuing Reactor Safety in the 21st Century 'where they summarized 12 Recommendations on Fukushima Accident. Here is the summary of these recommendations. (author)

  1. Groundwater flow modeling focused on the Fukushima Daiichi Nuclear Power Plant Site

    International Nuclear Information System (INIS)

    Saegusa, Hiromitsu; Onoe, Hironori; Kohashi, Akio; Watanabe, Masahisa

    2015-01-01

    Fukushima Daiichi nuclear power plant of Tokyo Electric Power Company is facing contaminated water issues in the aftermath of the Great East Japan Earthquake on March 11, 2011. The amount of contaminated water is continuously increasing due to groundwater leakage into the underground part of reactor and turbine buildings. Therefore, it is important to understand the groundwater flow conditions at the site and to predict the impact of countermeasures taken for isolating groundwater from the source of the contamination, i.e. the reactor buildings. Installations, such as of land-side and sea-side impermeable walls have been planned as countermeasures. In this study, groundwater flow modeling has been performed to estimate the response of groundwater flow conditions to the countermeasures. From the modeling, groundwater recharge and discharge areas, major groundwater flow direction, inflow rate into underground part of the buildings, and changes in response to implementation of the countermeasures could be reasonably estimated. The results indicate that the countermeasures will decrease the volume of inflow into the underground part of the buildings. This means that the countermeasures will be effective in reducing the discharge volume of contaminated groundwater to ocean. (author)

  2. Supportive measures toward safety assurance of post-disaster Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Hatazawa, Mamoru

    2012-01-01

    Toshiba group had taken supportive measures toward safety assurance of post-disaster Fukushima Daiichi Nuclear Power Plant, such as active water treatment, upgrade core cooling capability with additional water injection rout of core spray spargers, alternative cooling system of spent fuel pool with air cooler and nitrogen injection into reactor containment vessel from portable air separation system for nitrogen generation. As for a water treatment system for handling the radioactive water that had built up in the basement of the turbine building from injected water for cooling fuel debris, it was implemented at first by water treatment equipment from Areva and Kurion and now by Simplified Active Water Retrieve and Recovery System (SARRY) which Toshiba had newly developed as redundant system. Purified water could be reused for circulating injected water for reactor cooling. Strenuous efforts would be made for installation of cover building for fuel removal from spent fuel pool of unit 3 reactor and technology development for fuel debris removal using remote control robots. Portable gamma camera had been developed for decontamination works of radiation 'hot spot'. With loading SARRY on truck, mobile contaminated water treatment and contaminated soil purification system using oxalic acid solution for cesium extraction had been developed to contribute environmental remedial action in surrounding areas. (T. Tanaka)

  3. Agricultural approaches of remediation in the outside of the Fukushima Daiichi nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Sato, Nobuaki [Tohoku University, 2-1-1 Katahira Aoba-ku, Sendai, Miyagi 980-8577 (Japan); Saso, Michitaka [Toshiba Corporation Power Systems Company: 2-1 Ukishima-cho, Kawasaki-ku, Kawasaki, Kanagawa 210-0862 (Japan); Umeda, Miki [Japan Atomic Energy Agency, 4-29 Muramatsu, Tokai, Ibaraki 319-1184 (Japan); Fujii, Yasuhiko [Tokyo Institute of Technology:2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550 (Japan); Amemiya, Kiyoshi [Hazama Corporation: 2-2-5 Toranomon, Minato-ku, Tokyo 105-8479 (Japan)

    2013-07-01

    This paper outlines agricultural approaches of remediation activity done in contaminated areas around the Fukushima Daiichi Nuclear Power Plant. About the decontamination examination of contaminated areas, we have tried the land scale test of a rice field before and after planting by the use of currently recommended methods. Since farmers would carry out the land preparation by themselves, generation of secondary radioactive waste should be as low as possible through the decontamination works. For the radioactive nuclide migration control of rice by wet rice production, several types of decontamination methods such as zeolite addition and potassium fertilization in the soil have been examined. The results are summarized in the 4 following points. 1) Plowing and water discharge are effective for removing radioactive cesium from rice field. 2) Additional potassium fertilization is effective for reducing cesium radioactivity in the product. 3) No significant difference is observed with or without the zeolite addition. 4) Very low transfer factor of cesium from soil to brown rice has been obtained compared with literature values.

  4. Comparison of direct deposition and root uptake results after the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Tagami, Keiko; Uchida, Shigeo

    2012-01-01

    Field horsetail(Equisetum arvense) is a kind of fern, and the fertile shoots are eaten as vegetables in Japan in the spring. Since fern species tend to concentrate radiocaesium from soil, concentrations and distribution patterns of radiocaesium in the fertile shoots are of interest. In this study, distribution and food processing results were compared using samples collected in 2011(n=1) and 2012(n=3); the sample collected in 2011 received direct deposition from the Fukushima Daiichi Nuclear Power Plant accident while those collected in 2012 included radiocaesium mainly taken up from soil. About 200-300 shoots were collected at each sampling time. The 137 Cs concentration in samples collected in 2012 decreased by 100-200 times compared to that in 2011. The radiocaesium distribution patterns in strobili, leaves and stems of 2012 samples were almost the same as those of 2011; however, the patterns were different from those of potassium. The radiocaesium removal percentage by food processing (washing + boiling for 2.5min) was 70% in 2011, while that for 2012 samples was 32-72%; the effect of direct deposition and root uptake was not clear. (author)

  5. Atmospheric radionuclides from the Fukushima Dai-ichi nuclear reactor accident observed in Vietnam

    International Nuclear Information System (INIS)

    Long, N.Q.; Giap, T.V.; Phan, N.T.; Truong, Y.; Binh, N.T; Sieu, L.N.; Hien, P.D.

    2012-01-01

    Radionuclides from the reactor accident at the Fukushima Dai-ichi Nuclear Power Plant were observed in the surface air at stations in Hanoi, Dalat and Ho Chi Minh City (HCMC) in Vietnam, about 4500 km southwest of Japan, during the period from March 27 to April 22, 2011. The maximum activity concentrations in the air measured at those three sites were 193, 33 and 37 μBq m -3 for 131 I, 134 Cs and 137 Cs, respectively. Peaks of radionuclide concentrations in the air corresponded to arrival of the air mass from Fukushima to Vietnam after traveling for 8 days over the Pacific Ocean. Cesium-134 was detected with the 134 Cs/ 137 Cs activity ratio of about 0.85 in line with observations made elsewhere. The 131 I/ 137 Cs activity ratio was observed to decrease exponentially with time as expected from radioactive decay. The ratio at Dalat, where is 1500 m high, was higher than those at Hanoi and HCMC in low lands, indicating the relative enrichment of the iodine in comparison to cesium at high altitudes. The time-integrated surface air concentrations of the Fukushima-derived radionuclides in the Southeast Asia showed exponential decrease with distance from Fukushima. (author)

  6. National radiological emergency response to the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Dela Rosa, Alumanda M.

    2011-01-01

    The Fukushima nuclear power plant accident occurred on March 11, 2011, when two natural disasters of unprecedented strengths, an earthquake with magnitude 9 followed one hour later by a powerful tsunami struck northeastern Japan and felled the external power supply and the emergency diesel generators of the Fukushima Daiichi nuclear power station, resulting in a loss of coolant accident. There were core meltdowns in three nuclear reactors with the release of radioactivity estimated to be 1/10 of what was released to the environment during the Chernobyl nuclear power plant accident in April 1986. The Fukushima nuclear accident tested the capability of the Philippine Nuclear Research Institute (PNRI) and the National Disaster Risk Reduction and Management Council (NDRRMC) in responding to such radiological emergency as a nuclear power plant accident. The PNRI and NDRRMC activated the RADPLAN for possible radiological emergency. The emergency response was calibrated to the status of the nuclear reactors on site and the environmental monitoring undertaken around the site and off-site, including the marine environment. This orchestrated effort enabled the PNRI and the national agencies concerned to reassure the public that the nuclear accident does not have a significant impact on the Philippines, both on the health and safety of the people and on the safety of the environment. National actions taken during the accident will be presented. The role played by the International Atomic Energy Agency as the central UN agency for nuclear matters will be discussed. (author)

  7. Restoration of water environment contaminated by radioactive cesium released from Fukushima Daiichi NPP

    Energy Technology Data Exchange (ETDEWEB)

    Takeshita, K.; Takahashi, H. [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 157-8550 (Japan); Jinbo, Y. [CDM Cosulting Co.Ltd., 1-13-13 Tsukiji Chuo-ku Tokyo 104-0045 (Japan); Ishido, A. [Radwaste and Decommissioning Center, 1-7-6 Toranomon, Minato-ku, Tokyo 105-0001 (Japan)

    2013-07-01

    In the Fukushima Daiichi NPP Accident, large amounts of volatile radioactive nuclides, such as {sup 131}I, {sup 134}Cs and {sup 137}Cs, were released to the atmosphere and huge areas surrounding the nuclear site were contaminated by the radioactive fallout. In this study, a combined process with a hydrothermal process and a coagulation settling process was proposed for the separation of radioactive Cs from contaminated soil and sewage sludge. The coagulation settling operation uses Prussian Blue (Ferric ferrocyanide) and an inorganic coagulant. The recovery of Cs from sewage sludge sampled at Fukushima city (100.000 Bq/kg) and soil at a nearby village (55.000 Bq/kg), was tested. About 96% of Cs in the sewage sludge was removed successfully by combining simple hydrothermal decomposition and coagulation settling. However, Cs in the soil was not removed sufficiently by the combined process (Cs removal is only 56%). The hydrothermal decomposition with blasting was carried out. The Cs removal from the soil was increased to 85%. When these operations were repeated twice, the Cs recovery was over 90%. The combined process with hydrothermal blasting and coagulation settling is applicable to the removal of Cs from highly contaminated soil.

  8. Risk communication with Fukushima residents affected by the Fukushima Daiichi accident at whole-body counting

    Energy Technology Data Exchange (ETDEWEB)

    Gunji, I.; Furuno, A.; Yonezawa, R.; Sugiyama, K. [Risk Communication Study Office, Japan Atomic Energy Agency 4-33 Muramatsu, Tokai-mura, Ibaraki, 319-1194 (Japan)

    2013-07-01

    After the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi nuclear power plant accident, the Tokai Research and Development Center of the Japan Atomic Energy Agency (JAEA) have had direct dialogue as risk communication with Fukushima residents who underwent whole-body counting examination (WBC). The purpose of the risk communication was to exchange information and opinions about radiation in order to mitigate Fukushima residents' anxiety and stress. Two kinds of opinion surveys were performed: one survey evaluated residents' views of the nuclear accident itself and the second survey evaluated the management of WBC examination as well as the quality of JAEA's communication skills on risks. It appears that most Fukushima residents seem to have reduced their anxiety level after the direct dialogue. The results of the surveys show that Fukushima residents have the deepest anxiety and concern about their long-term health issues and that they harbor anger toward the government and TEPCO. On the other hand, many WBC patients and patients' relatives have expressed gratitude for help in reducing their feelings of anxiety.

  9. Risk Assessment Strategy for Decommissioning of Fukushima Daiichi Nuclear Power Station

    Directory of Open Access Journals (Sweden)

    Akira Yamaguchi

    2017-03-01

    Full Text Available Risk management of the Fukushima Daiichi Nuclear Power Station decommissioning is a great challenge. In the present study, a risk management framework has been developed for the decommissioning work. It is applied to fuel assembly retrieval from Unit 3 spent fuel pool. Whole retrieval work is divided into three phases: preparation, retrieval, and transportation and storage. First of all, the end point has been established and the success path has been developed. Then, possible threats, which are internal/external and technical/societal/management, are identified and selected. “What can go wrong?” is a question about the failure scenario. The likelihoods and consequences for each scenario are roughly estimated. The whole decommissioning project will continue for several decades, i.e., long-term perspective is important. What should be emphasized is that we do not always have enough knowledge and experience of this kind. It is expected that the decommissioning can make steady and good progress in support of the proposed risk management framework. Thus, risk assessment and management are required, and the process needs to be updated in accordance with the most recent information and knowledge on the decommissioning works.

  10. Birth Outcomes after the Fukushima Daiichi Nuclear Power Plant Disaster: A Long-Term Retrospective Study

    Science.gov (United States)

    Leppold, Claire; Nomura, Shuhei; Sawano, Toyoaki; Ozaki, Akihiko; Tsubokura, Masaharu; Hill, Sarah; Kanazawa, Yukio; Anbe, Hiroshi

    2017-01-01

    Changes in population birth outcomes, including increases in low birthweight or preterm births, have been documented after natural and manmade disasters. However, information is limited following the 2011 Fukushima Daiichi Nuclear Power Plant Disaster. In this study, we assessed whether there were long-term changes in birth outcomes post-disaster, compared to pre-disaster data, and whether residential area and food purchasing patterns, as proxy measurements of evacuation and radiation-related anxiety, were associated with post-disaster birth outcomes. Maternal and perinatal data were retrospectively collected for all live singleton births at a public hospital, located 23 km from the power plant, from 2008 to 2015. Proportions of low birthweight (increased proportions of low birthweight or preterm births in any year after the disaster (merged post-disaster risk ratio of low birthweight birth: 0.98, 95% confidence interval (CI): 0.64–1.51; and preterm birth: 0.68, 95% CI: 0.38–1.21). No significant associations between birth outcomes and residential area or food purchasing patterns were identified, after adjustment for covariates. In conclusion, no changes in birth outcomes were found in this institution-based investigation after the Fukushima disaster. Further research is needed on the pathways that may exacerbate or reduce disaster effects on maternal and perinatal health. PMID:28534840

  11. Simultaneous sampling of indoor and outdoor airborne radioactivity after the Fukushima Daiichi nuclear power plant accident.

    Science.gov (United States)

    Ishikawa, Tetsuo; Sorimachi, Atsuyuki; Arae, Hideki; Sahoo, Sarata Kumar; Janik, Miroslaw; Hosoda, Masahiro; Tokonami, Shinji

    2014-02-18

    Several studies have estimated inhalation doses for the public because of the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident. Most of them were based on measurement of radioactivity in outdoor air and included the assumption that people stayed outdoors all day. Although this assumption gives a conservative estimate, it is not realistic. The "air decontamination factor" (ratio of indoor to outdoor air radionuclide concentrations) was estimated from simultaneous sampling of radioactivity in both inside and outside air of one building. The building was a workplace and located at the National Institute of Radiological Sciences (NIRS) in Chiba Prefecture, Japan. Aerosol-associated radioactive materials in air were collected onto filters, and the filters were analyzed by γ spectrometry at NIRS. The filter sampling was started on March 15, 2011 and was continued for more than 1 year. Several radionuclides, such as (131)I, (134)Cs, and (137)Cs were found by measuring the filters with a germanium detector. The air decontamination factor was around 0.64 for particulate (131)I and 0.58 for (137)Cs. These values could give implications for the ratio of indoor to outdoor radionuclide concentrations after the FDNPP accident for a similar type of building.

  12. Plutonium release from Fukushima Daiichi fosters the need for more detailed investigations

    Science.gov (United States)

    Schneider, Stephanie; Walther, Clemens; Bister, Stefan; Schauer, Viktoria; Christl, Marcus; Synal, Hans-Arno; Shozugawa, Katsumi; Steinhauser, Georg

    2013-10-01

    The contamination of Japan after the Fukushima accident has been investigated mainly for volatile fission products, but only sparsely for actinides such as plutonium. Only small releases of actinides were estimated in Fukushima. Plutonium is still omnipresent in the environment from previous atmospheric nuclear weapons tests. We investigated soil and plants sampled at different hot spots in Japan, searching for reactor-borne plutonium using its isotopic ratio 240Pu/239Pu. By using accelerator mass spectrometry, we clearly demonstrated the release of Pu from the Fukushima Daiichi power plant: While most samples contained only the radionuclide signature of fallout plutonium, there is at least one vegetation sample whose isotope ratio (0.381 +/- 0.046) evidences that the Pu originates from a nuclear reactor (239+240Pu activity concentration 0.49 Bq/kg). Plutonium content and isotope ratios differ considerably even for very close sampling locations, e.g. the soil and the plants growing on it. This strong localization indicates a particulate Pu release, which is of high radiological risk if incorporated.

  13. Mobilizing Mothers: The Fukushima Daiichi Nuclear Catastrophe and Environmental Activism in Japan

    Directory of Open Access Journals (Sweden)

    Nicole Freiner

    2014-02-01

    Full Text Available The citizens’ and environmental movements of the 1960s and 70s hadgreat political success in Japan, culminating in the Special Session of the Diet in1970 that enacted 14 anti-pollution laws. These activist groups fought denials ofresponsibility on the part of industry and unresponsiveness on the part of localgovernments. Women were at the forefront of this type of activism during the 1960sand 70s, and led many of the citizens’ environmental movements during this time.More recently, during the environmental catastrophe caused by the meltdown of theFukushima Daiichi nuclear plant, women and mothers have been vocal protesters.Environmental movements have particular political salience because of the successwomen have achieved in this area both in policy change and also roles in formalpolitics. Women have consistently achieved these successes at the same time as theyperformed their roles as mothers and home managers; these roles have been usedstrategically to mobilize women with great effect, and also were central to the valueswith which the citizens’ movements defined themselves politically.

  14. Linear free energy correlations for fission product release from the Fukushima-Daiichi nuclear accident.

    Science.gov (United States)

    Abrecht, David G; Schwantes, Jon M

    2015-03-03

    This paper extends the preliminary linear free energy correlations for radionuclide release performed by Schwantes et al., following the Fukushima-Daiichi Nuclear Power Plant accident. Through evaluations of the molar fractionations of radionuclides deposited in the soil relative to modeled radionuclide inventories, we confirm the initial source of the radionuclides to the environment to be from active reactors rather than the spent fuel pool. Linear correlations of the form In χ = −α ((ΔGrxn°(TC))/(RTC)) + β were obtained between the deposited concentrations, and the reduction potentials of the fission product oxide species using multiple reduction schemes to calculate ΔG°rxn (TC). These models allowed an estimate of the upper bound for the reactor temperatures of TC between 2015 and 2060 K, providing insight into the limiting factors to vaporization and release of fission products during the reactor accident. Estimates of the release of medium-lived fission products 90Sr, 121mSn, 147Pm, 144Ce, 152Eu, 154Eu, 155Eu, and 151Sm through atmospheric venting during the first month following the accident were obtained, indicating that large quantities of 90Sr and radioactive lanthanides were likely to remain in the damaged reactor cores.

  15. Risk assessment strategy for decommissioning of Fukushima Daiichi Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Yamaguchi, Akira; Jang, Sung Hoon [The University of Tokyo, Tokyo (Japan); Hida, Kazuki [Nuclear Damage Compensation and Decommissioning Facilitation Corporation, Tokyo (Japan); Yamanaka, Yasunori [Tokyo Electric Power Company Holdings, Tokyo (Japan); Narumiya, Yoshiyuki [The Kansai Electric Power Co., Inc., Osaka (Japan)

    2017-03-15

    Risk management of the Fukushima Daiichi Nuclear Power Station decommissioning is a great challenge. In the present study, a risk management framework has been developed for the decommissioning work. It is applied to fuel assembly retrieval from Unit 3 spent fuel pool. Whole retrieval work is divided into three phases: preparation, retrieval, and transportation and storage. First of all, the end point has been established and the success path has been developed. Then, possible threats, which are internal/external and technical/societal/management, are identified and selected. “What can go wrong?” is a question about the failure scenario. The likelihoods and consequences for each scenario are roughly estimated. The whole decommissioning project will continue for several decades, i.e., long-term perspective is important. What should be emphasized is that we do not always have enough knowledge and experience of this kind. It is expected that the decommissioning can make steady and good progress in support of the proposed risk management framework. Thus, risk assessment and management are required, and the process needs to be updated in accordance with the most recent information and knowledge on the decommissioning works.

  16. Atmospheric radionuclides from Fukushima Dai-ichi nuclear accident detected in Lanzhou, China

    Institute of Scientific and Technical Information of China (English)

    邬家龙王赟; 孙卫; 罗伟立; 王延俊; 张飙

    2015-01-01

    After the Fukushima Dai-ichi nuclear power plant accident on March 11, 2011, the radioactivity released from the accident was transported around the globe by atmospheric processes. The radioactivity monitoring program on atmospheric particulate in Lanzhou, China was activated by GSCDC to detect the input radionu-clides through atmospheric transport. Several artificial radionuclides were detected and measured in aerosol samples from March 26 to May 2, 2011. The peaked activity concentrations (in mBq/m3) were: 1.194 (131I), 0.231 (137Cs), 0.173 (134Cs) and 0.008 (136Cs), detected on April 6, 2011. The average activity ratio of 131I/137Cs and 134Cs/137Cs in air were 13.5 and 0.78. The significant increase of 137Cs activity concentration, one order of magnitude higher than pre-Fukushima accident levels, in ground level aerosol was observed in 2013, as its re-suspension from soil. The back-trajectory analysis simulated by NOAA-ARL HYSPLIT shows a direct transfer of the air masses released from Fukushima to Lanzhou across the Pacific Ocean, North America and Europe at the height close to 9000 m AGL. The value of effective dose for inhalation is close to one millionth of the annual limit for the general public.

  17. Aftermath of the Fukushima Daiichi nuclear accident in March 2011 - Situation review in March 2016

    International Nuclear Information System (INIS)

    2016-03-01

    The first part of this detailed report addresses the consequences of the accident regarding nuclear safety. It proposes a situation review of site damaged installations, of radioactive water management, and of underground water management. It presents and comments lessons learned from this accident for French nuclear installations, gives an overview of researches performed by the IRSN in the field of nuclear safety. The second part addresses health consequences of the accident. It discusses an assessment of epidemiologic studies performed on inhabitants of the Fukushima Prefecture, and comments the situation of workers involved in operations performed in the Fukushima Daiichi nuclear power plant. The third part addresses environmental consequences. It discusses values of radionuclide concentrations in Japanese air five years after the accident, measurements of caesium activities, assessments of contamination of Japanese food products, decontamination actions and waste management, the status of marine contamination in 2015, the evolution of evacuation areas between 2011 and 2016, the first returns and wills to return of evacuated populations, the update of knowledge related to the dispersion and depositions of atmospheric releases of the accident, and the modelling of atmospheric transport and fallouts of releases emitted during the accident. The last part proposes a comparison between the Chernobyl accident and the Fukushima accident in terms of distribution of radioactive depositions within river basins, of knowledge drawn from ecologic studies on fauna and flora performed on the long term in contaminated areas, and of management of forest environments after a nuclear accident

  18. Problems of probabilistic safety assessment after Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    Sugiyama, Naoki

    2011-01-01

    Probabilistic safety assessment (PSA) methodology to assure nuclear safety is had great expectations of lessons learned from Fukushima Daiichi nuclear power plant (NPP) accident and on the other hand this accident made actualized technical problems of PSA. Effectiveness of current PSA methodology for risk assessment was confirmed by comparing the accident development with accident scenario of PSA and equipment failure rate. From a viewpoint of nuclear safety objective and defense in depth approach of IAEA, technical problems of PSA were (1) extension of PSA for spent fuel pool and waste disposal system as well as level 3PSA for broader environmental contamination and (2) overlapping of accident scenario of plural unit site, balance of high quality plant management and preceding negation, treatment of uncertainty of external events, severe accident measure and human reliability analysis and reflection of disaster prevention capability to level 3PSA. In order to upgrade PSA technology, six proposals were described for nuclear safety and defense in depth, comprehensive evaluation scope and catch-up of latest technology, necessity of strategic preparation of PSA standard, human resources fostering and risk communication. (T. Tanaka)

  19. Risk communication with Fukushima residents affected by the Fukushima Daiichi accident at whole-body counting

    International Nuclear Information System (INIS)

    Gunji, I.; Furuno, A.; Yonezawa, R.; Sugiyama, K.

    2013-01-01

    After the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi nuclear power plant accident, the Tokai Research and Development Center of the Japan Atomic Energy Agency (JAEA) have had direct dialogue as risk communication with Fukushima residents who underwent whole-body counting examination (WBC). The purpose of the risk communication was to exchange information and opinions about radiation in order to mitigate Fukushima residents' anxiety and stress. Two kinds of opinion surveys were performed: one survey evaluated residents' views of the nuclear accident itself and the second survey evaluated the management of WBC examination as well as the quality of JAEA's communication skills on risks. It appears that most Fukushima residents seem to have reduced their anxiety level after the direct dialogue. The results of the surveys show that Fukushima residents have the deepest anxiety and concern about their long-term health issues and that they harbor anger toward the government and TEPCO. On the other hand, many WBC patients and patients' relatives have expressed gratitude for help in reducing their feelings of anxiety

  20. Condensate demineralizer system for Fukushima Daiichi Nuclear Power Station, the Tokyo Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Ariyoshi, Shigeki; Ikeda, Yukio; Kuramoto, Kenji; Omori, Yoshi; Yamamoto, Hiroyoshi

    1975-01-01

    This paper describes the condensate demineralizing equipment recently supplied to the second, third, and fifth power units of the Fukushima Daiichi Nuclear Power Station of the Tokyo Electric Power Company, Inc. The output of this equipment is rated as 4,900 m 3 /h each, which is currently the largest capacity for this type of equipment in Japan. The purpose of this equipment is to remove any ion components and suspended solids contained in condensate to improve its water purity. By doing so, decreasing the corrosion rate of materials used in the plant and, at the same time, decreasing the radioactivity of the condensate, thus easing the whole plant operation can be achieved. The same kind of equipment is also employed at the conventional thermal power stations, but the required functioning and operating mode are quite different. In the case of the nuclear power plant, extremely severe requirements specific with nuclear technology must be met which arise solely from dealing with radioactive substances. Not only the water treatment method, but also layout and arrangement, operation and liquid waste processing methods differ from those for the conventional power plants. The equipment for the sixth unit at Fukushima is now under designing and that for the Tokai No.2 unit of the Japan Atomic Power Company is already under shop fabrication. Both have the rated capacity of 7,300 m 3 /h each, which exceeds far up the capacity of the previously mentioned equipment. (auth.)

  1. Radiocesium contamination in house dust within evacuation areas close to the Fukushima Daiichi nuclear power plant.

    Science.gov (United States)

    Shinohara, Naohide; Yoshida-Ohuchi, Hiroko

    2018-05-01

    Outdoor decontamination efforts have been ongoing since the Fukushima Daiichi nuclear power plant (FDNPP) accident; however, little is known about indoor contamination. Therefore, house dust was sampled based on particle size in 21 wooden buildings (19 residential houses and 2 community centers) within the evacuation area close to the FDNPP, Fukushima Prefecture, Japan. Activities of radiocesium ( 137 Cs) per gram of house dust increased with decreasing particle size (mean: 6.1 × 10 3 , 2.6 × 10 3 , 1.6 × 10 3 , 7.5 × 10 2 , 5.0 × 10 2 , and 4.6 × 10 2  Bq/g for house dust were inversely related to the square of distance from the FDNPP for house dust. It was found that 19%, 33%, and 48% of 137 Cs in house dust were extracted in water, 1 M HCl, and not extracted, respectively. Considering the bioaccessibility and assuming a 20 mg/day daily intake of house dust, the daily doses would be 7.2 Bq/day (mean) and 18 Bq/day (95th percent quantile). These results provide valuable insight into indoor radioactive Cs contamination in the area around the FDNPP and possible oral exposure to indoor radioactive Cs after returning home. Copyright © 2018 The Authors. Published by Elsevier Ltd.. All rights reserved.

  2. Screening survey on thyroid exposure for children after the Fukushima Daiichi Nuclear Power Station accident

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Eunjoo; Kurihara, Osamu; Suzuki, Toshikazu; Matsumoto, Masaki; Fukutsu, Kumiko; Yamada, Yuji; Sugiura, Nobuyuki; Akashi, Makoto [National Institute of Radiological Sciences, Research Center for Radiation Emergency Medicine, Chiba, Chiba (Japan)

    2012-11-15

    In response to a serious accident at the Fukushima Daiichi Nuclear Power Station, National Institute of Radiological Sciences (NIRS) established a protocol for a screening survey of thyroid exposure for children living in areas where thyroid doses were predicted to be high. The aim of the screening survey was to implement measurements for a large number of subjects with conventional NaI(Tl) scintillation survey meters. This protocol was applied to the screening survey of 1,149 children at five locations in three municipalities (Kawamata Town, Iitate Village and Iwaki City). Among 1,080 children (excluding 69 subjects from evaluation), there were no subjects who exceeded a screening level (0.2 {mu}Sv h{sup -1}) corresponding to a thyroid equivalent dose of 100 mSv (for the age group of 1-y-old as of March 24). No significant signals were detected in 55.4% of these subjects and the maximum dose was found to be 43 mSv. This paper presents details on the protocol as well as results of the screening survey. (author)

  3. Abbreviations [Annex to The Fukushima Daiichi Accident, Technical Volume 2/5

    International Nuclear Information System (INIS)

    2015-01-01

    This annex is a list of abbreviations used in the publication The Fukushima Daiichi Accident, Technical Volume 2/5. The list includes the abbreviations for: • Agency for Natural Resources and Energy; • essential service water; • International Nuclear and Radiological Event Scale;• Integrated Regulatory Review Service; • Japan Atomic Energy Agency; • Japan Atomic Energy Commission; • Japan Power Engineering and Inspection Corp; • Japan Nuclear Energy Safety Organization; • low head safety injection; • low level radioactive waste; • Madras Atomic Power Station; • main control room; • Ministry of Economy, Trade and Industry; • Ministry of Education, Culture, Sports, Science and Technology; • Ministry of International Trade and Industry; • Ministry of Foreign Affairs; • Nuclear and Industrial Safety Agency; • Nuclear Power Corporation of India Limited; • nuclear power plant; • Nuclear Safety Commission; • Nuclear Power Engineering Corporation; • Nuclear Safety Technology Centre; • Onahama Port; • pressurized water reactor; • Science and Technology Agency; • Tokyo Electric Power Company

  4. Communication activity for residents to understand radiation after the accident of Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    Itabashi, Kiyoshi; Tagawa, Akihiro; Sugiyama, Kenji; Yamamoto, Tomoyo

    2015-01-01

    'Question-and-Answer Session on Radiation and Health' ('Kotaeru-kai' in Japanese) has started in July 2011 in Fukushima Prefecture, which was influenced by the accident of Fukushima Daiichi Nuclear Power Station following the Great East Japan Earthquake and Tsunami on 11 March 2011. The purpose of the Session is to have mainly parents and teachers (kindergartens, schools etc.) understand correctly about radiation and its influence on health. At the requests of the teachers in Fukushima Prefecture, about 4 staff members made a team, and visited Fukushima. The members of the team were selected from 500 JAEA staffs nominated beforehand. The members explained about radiation and its influence on health by using illustrations and metaphors. After the lecture, they answered the questions asked in advance at schools. Also they answered the questions asked in the Session. In the Session, the members placed much value on the communication with participants. Until the end of December 2014, the Question-and-Answer Sessions on Radiation and Health have been held 241 times for about twenty thousand participants. According to 7,613 participants' questionnaires, which were collected from July 2011 to the end of 2012, it seems that participants were able to understand well about radiation and its influence on health. Besides parents and teachers, some of the junior high schools requested to explain for students. JAEA will continue this communication activity in order to meet these expectations and requirements. (author)

  5. A Study on Pyrochemical Process for Treating Fuel Debris from the Fukushima-Daiichi Reactors

    International Nuclear Information System (INIS)

    Sakamura, Y.; Iizuka, M.; Koyama, T.; Kitawaki, S.; Nakayoshi, A.; Kofuji, H.

    2015-01-01

    After the severe accident at Fukushima-daiichi nuclear power plants, CRIEPI and JAEA started a feasibility study on the pyrochemical treatment of the corium that mainly consists of UO 2 -ZrO 2 solid solution. In this study, reduction behaviours of zirconium oxide compounds were investigated in LiCl-Li 2 O salt bath at 923 K. It was experimentally verified that uranium in the simulated corium could be reduced to the metallic form and a part of zirconium was converted to Li 2 ZrO 3 . At higher Li 2 O concentrations in LiCl, Li 2 ZrO 3 was converted to Li 6 Zr 2 O 7 and Li 8 ZrO 6 . In the subsequent electrorefining, Li 2 ZrO 3 reacts with UCl 3 dissolved in the electrolyte salt to give UO 2 precipitate. Therefore, how to remove the Li 2 ZrO 3 from the reduction product is a key point for the pyrochemical treatment of the corium. (authors)

  6. Tritium in Japanese precipitation following the March 2011 Fukushima Daiichi Nuclear Plant accident.

    Science.gov (United States)

    Matsumoto, Takuya; Maruoka, Teruyuki; Shimoda, Gen; Obata, Hajime; Kagi, Hiroyuki; Suzuki, Katsuhiko; Yamamoto, Koshi; Mitsuguchi, Takehiro; Hagino, Kyoko; Tomioka, Naotaka; Sambandam, Chinmaya; Brummer, Daniela; Klaus, Philipp Martin; Aggarwal, Pradeep

    2013-02-15

    Tritium concentrations in Japanese precipitation samples collected after the March 2011 accident at the Fukushima Dai-ichi Nuclear Power Plant (FNPP1) were measured. Values exceeding the pre-accident background were detected at three out of seven localities (Tsukuba, Kashiwa and Hongo) southwest of the FNPP1 at distances varying between 170 and 220 km from the source. The highest tritium content was found in the first rainfall in Tsukuba after the accident; however concentrations were 500 times less than the regulatory limit for tritium in drinking water. Tritium concentrations decreased steadily and rapidly with time, becoming indistinguishable from the pre-accident values within five weeks. The atmospheric tritium activities in the vicinity of the FNPP1 during the earliest stage of the accident was estimated to be 1.5×10(3) Bq/m(3), which is potentially capable of producing rainwater exceeding the regulatory limit, but only in the immediate vicinity of the source. Copyright © 2012 Elsevier B.V. All rights reserved.

  7. Teaching of severe accident of Fukushima Daiichi Nuclear Power Plants of Tokyo Electric Power

    International Nuclear Information System (INIS)

    Saito, Shinzo

    2011-01-01

    The Great East Japan Earthquake and accompanied tsunami brought about the severe accident at Fukushima Daiichi Nuclear Power Plants of Tokyo Electric Power Co., Inc. For 'No more Fukushima', twelve teaching of the accident was pointed out as follows: 1) natural disasters and external events shall be taken into consideration, 2) severe accident shall be included into safety regulation, 3) all possibility of hydrogen explosion shall be excluded, 4) diversity of safety important component and equipment shall be added with sufficient period of outage, 5) siting of multiple units at the same site shall be avoided at quake-prone country like Japan, 6) accident response environment for operators shall be improved, 7) accident convergence termination system shall be established so as to concentrate technical experience and knowledge, 8) off-site center shall be improved, 9) resident evacuation, consumption limit of food, radiation exposure and soil contamination limit shall be decided openly, 10) nuclear regulation and prevention of disaster shall be conducted by unitary organization to gain public trust, 11) fostering of safety culture among relevant enterprises shall be more encouraged and 12) nuclear industry shall develop reactor such as with no core meltdown or no evacuation and environmental contamination even if reactor core would be meltdown. (T. Tanaka)

  8. Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core Concrete Interaction

    International Nuclear Information System (INIS)

    Robb, Kevin R; Farmer, Mitchell; Francis, Matthew W

    2015-01-01

    Lower head failure and corium concrete interaction were predicted to occur at Fukushima Daiichi Unit 1 (1F1) by several different system-level code analyses, including MELCOR v2.1 and MAAP5. Although these codes capture a wide range of accident phenomena, they do not contain detailed models for ex-vessel core melt behavior. However, specialized codes exist for analysis of ex-vessel melt spreading (e.g., MELTSPREAD) and long-term debris coolability (e.g., CORQUENCH). On this basis, an analysis was carried out to further evaluate ex-vessel behavior for 1F1 using MELTSPREAD and CORQUENCH. Best-estimate melt pour conditions predicted by MELCOR v2.1 and MAAP5 were used as input. MELTSPREAD was then used to predict the spatially dependent melt conditions and extent of spreading during relocation from the vessel. The results of the MELTSPREAD analysis are reported in a companion paper. This information was used as input for the long-term debris coolability analysis with CORQUENCH.

  9. Japan Catastrophic Earthquake and Tsunami in Fukushima Daiichi NPP; Is it Beyond Design Basis Accident or a Design Deficiency and Operator Unawareness?

    International Nuclear Information System (INIS)

    Gaafar, M.A.; Refeat, R.M.; EL-Kady, A.A.

    2012-01-01

    On March 11, 2011 a catastrophic earthquake and tsunami struck the north east coast of Japan. This catastrophe damaged fully or partially the six units of the Fukushima Daiichi Nuclear Power Plant.Questions were raised following the aftermath, whether it is beyond design basis accident caused by severe natural event or a failure by the Japanese authorities to plan to deal with such accident. There are many indications that the Utility of Fukushima Daiichi NPP, Tokyo Electric Power Company (TEPCO), did not pay enough attention to numerous facts about the incompatibility of the site and several design defects in the plant units. In fact there are three other NPP sites nearby Fukushima Daiichi Plant (about 30 to 60 Km far from Fukushima Daiichi NPP), with different site characteristics, which survived the same catastrophic earthquake and tsunami, but they were automatically turned into a safe shutdown state. These plants sites are Fukushima Daini Plant (4 units), Onagawa Plant (3 units) and Tokai Daini (II) Plant (one unit). In this paper, the aftermath Fukushima Daiichi plant integrity is pointed out. Some facts about the site and design concerns which could have implications on the accident are discussed. The response of Japan Authority is outlined and some remarks about their actions are underlined. The impacts of this disaster on the Nuclear Power Program worldwide are also discussed.

  10. Situation of Fukushima Dai-ichi power plant in Japan - June 1, 2011 status; Situation de la centrale nucleaire de Fukushima Dai-ichi au Japon - Point de situation du 1er juin 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on June 1, 2011 by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the cores of reactors 1, 2 and 3 of the Fukushima I site (Dai-ichi) and of the different spent fuel pools is briefly presented as well as the actions in progress for the control of environmental radioactive releases and for the progressive recovery of the facilities control. (J.S.)

  11. Situation of Fukushima Dai-ichi power plant in Japan - May 25, 2011 status; Situation de la centrale nucleaire de Fukushima Dai-ichi au Japon - Point de situation du 25 mai 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on May 25, 2011 by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the cores of reactors 1, 2 and 3 of the Fukushima I site (Dai-ichi) and of the different spent fuel pools is briefly presented as well as the actions in progress for the control of environmental radioactive releases and for the progressive recovery of the facilities control. (J.S.)

  12. Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM

    Directory of Open Access Journals (Sweden)

    C. M. Allison

    2012-01-01

    Full Text Available Immediately after the accident at Fukushima Daiichi, Innovative Systems Software and other members of the international SCDAP Development and Training Program started an assessment of the possible core/vessel damage states of the Fukushima Daiichi Units 1–3. The assessment included a brief review of relevant severe accident experiments and a series of detailed calculations using RELAP/SCDAPSIM. The calculations used a detailed RELAP/SCDAPSIM model of the Laguna Verde BWR vessel and related reactor cooling systems. The Laguna Verde models were provided by the Comision Nacional de Seguridad Nuclear y Salvaguardias, the Mexican nuclear regulatory authority. The initial assessment was originally presented to the International Atomic Energy Agency on March 21 to support their emergency response team and later to our Japanese members to support their Fukushima Daiichi specific analysis and model development.

  13. Safety goals for seismic and tsunami risks: Lessons learned from the Fukushima Daiichi disaster

    International Nuclear Information System (INIS)

    Saji, Genn

    2014-01-01

    Highlights: • Reviewed why the Fukushima disaster was not anticipated among seismologists. • Reviewed Fukushima Daiichi's preparedness against the earthquake and tsunami. • There was a large “cliff edge” in radiological consequences from the design basis tsunami. • By including earthquakes as an “external event” resulted in insufficient “defense in depths”. • Proposes a new probabilistic seismic and tsunami safety goal be developed. - Abstract: This paper first reviews why the potential occurrence of the Tohoku-oki earthquake with momentum magnitude M w of 9.0 earthquake was not anticipated by Japanese seismologists, and to clarify our limitations in predicting rare but severe earthquakes at our current knowledge in the field of geosciences. Although there was a large volume of historical records related to earthquakes and tsunamis, generally this data infer high plate coupling in regions where earthquakes were known to have already occurred, with only partial or even no coupling from the Japan Trench to a point approximately midway between the trench and the coastline—precisely the region where the 2011 Tohoku-Oki earthquake occurred. This phenomenon has been explained as a “silent earthquake” or a fault creep as observed at the San Andreas Faults in the US. Considering the large uncertainties in seismic events, nuclear power plants should be conservatively designed with adequate safety margins. TEPCO's preparedness against seismic and tsunami hazards were reviewed in order to clarify why the established safety margin was not sufficient during the Fukushima Daiichi. It was found that the plant incorporated the necessary safety margins against seismic oscillation however, there was a large “cliff edge” in which the radiological consequences surged by several orders of magnitude from the design basis tsunami. Since the tsunami's height was greater than the ground level of the turbine hall, a large amount of the tsunami

  14. Safety goals for seismic and tsunami risks: Lessons learned from the Fukushima Daiichi disaster

    Energy Technology Data Exchange (ETDEWEB)

    Saji, Genn, E-mail: sajig@bd5.so-net.ne.jp

    2014-12-15

    Highlights: • Reviewed why the Fukushima disaster was not anticipated among seismologists. • Reviewed Fukushima Daiichi's preparedness against the earthquake and tsunami. • There was a large “cliff edge” in radiological consequences from the design basis tsunami. • By including earthquakes as an “external event” resulted in insufficient “defense in depths”. • Proposes a new probabilistic seismic and tsunami safety goal be developed. - Abstract: This paper first reviews why the potential occurrence of the Tohoku-oki earthquake with momentum magnitude M{sub w} of 9.0 earthquake was not anticipated by Japanese seismologists, and to clarify our limitations in predicting rare but severe earthquakes at our current knowledge in the field of geosciences. Although there was a large volume of historical records related to earthquakes and tsunamis, generally this data infer high plate coupling in regions where earthquakes were known to have already occurred, with only partial or even no coupling from the Japan Trench to a point approximately midway between the trench and the coastline—precisely the region where the 2011 Tohoku-Oki earthquake occurred. This phenomenon has been explained as a “silent earthquake” or a fault creep as observed at the San Andreas Faults in the US. Considering the large uncertainties in seismic events, nuclear power plants should be conservatively designed with adequate safety margins. TEPCO's preparedness against seismic and tsunami hazards were reviewed in order to clarify why the established safety margin was not sufficient during the Fukushima Daiichi. It was found that the plant incorporated the necessary safety margins against seismic oscillation however, there was a large “cliff edge” in which the radiological consequences surged by several orders of magnitude from the design basis tsunami. Since the tsunami's height was greater than the ground level of the turbine hall, a large amount of the

  15. The Fukushima Daiichi Accident. Technical Volume 2/5. Safety Assessment

    International Nuclear Information System (INIS)

    2015-08-01

    Technical Volume 1 of this report has described what happened during the accident at the Fukushima Daiichi nuclear power plant (NPP). This volume begins (Section 2.1) with a review of how the design basis of the site for external events was assessed initially and then reassessed over the life of the NPP. The section also describes the physical changes that were made to the units as a result. The remainder of the volume describes the treatment of beyond design basis events in the safety assessment of the site, the accident management provisions, the effectiveness of regulatory programmes, human and organizational factors and the safety culture, and the role of operating experience. Further background information is contained in three annexes included on the CD-ROM of this Technical Volume which describe analytical investigations of the accident along with information on topics such as system performance, defence in depth and severe accident phenomena. Section 2.2 provides an assessment of the systems that failed, resulting in a failure to maintain the fundamental safety functions in Units 1–3, which were in operation at the time of the tsunami and in which the reactor pressure vessels (RPV) and containment vessels failed. The section also describes Units 4-6, which were shut down at the time of the tsunami, and the site’s central spent fuel storage facility. Section 2.3 discusses the probabilistic and deterministic safety assessments of beyond design basis accidents (BDBAs) that had been performed for the plant and the insights from these assessments that had led to changes in the plant’s design. The section pays particular attention to the assessment of extreme natural hazards, such as the one which led to the total loss of AC power supply on the site. The additional loss of DC power supply in Units 1 and 2 played a key role in the progression of the accident because it impeded the diagnosis of plant conditions and made the operators unaware of the status of

  16. The Fukushima Daiichi Accident. Technical Volume 3/5. Emergency Preparedness and Response

    International Nuclear Information System (INIS)

    2015-08-01

    This volume describes the key events and response actions from the onset of the accident at the Fukushima Daiichi nuclear power plant (NPP), operated by the Tokyo Electric Power Company (TEPCO), on 11 March 2011. It also describes the national emergency preparedness and response (EPR) system in place in Japan and the international EPR framework prior to the accident. It is divided into five sections. Section 3.1 describes the initial actions taken by Japan in response to the accident, involving: identification of the accident, notification of off-site authorities and activation of the response; mitigatory actions taken on-site; and initial off-site response. Section 3.2 describes the protective measures taken for personnel in response to the natural disaster, protection of emergency workers, medical management of emergency workers and the voluntary involvement of members of the public in the emergency response. Section 3.3 describes the protective actions and other response actions taken by Japan to protect the public. It addresses urgent and early protective actions; the use of a dose projection model, the System for Prediction of Environmental Emergency Dose Information (SPEEDI), as a basis for decisions on protective actions during the accident; environmental monitoring; provision of information to the public and international community; and issues related to international trade and waste management. Section 3.4 describes the transition from the emergency phase to the recovery phase. It also addresses the national analysis of the accident and the emergency response. Section 3.5 describes the response by the IAEA, other international organizations within the Inter- Agency Committee on Radiological and Nuclear Emergencies (IACRNE), the actions of IAEA Member States with regard to protective actions recommended to their nationals in Japan and the provision of international assistance. A summary, observations and lessons conclude each section. There are three

  17. iB1350 no.1. A generation III.7 reactor after the Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Sato, Takashi; Matsumoto, Keiji; Hosomi, Kenji; Kojima, Yoshihiro; Taguchi, Keisuke

    2017-01-01

    iB1350 stands for an innovative, intelligent and inexpensive BWR 1350. It is the first generation III.7 reactor after the Fukushima Daiichi accident. It has incorporated lessons learned from the Fukushima Daiichi accident and WENRA safety objectives. It has innovative safety to cope with devastating natural disasters including a giant earthquake, a large tsunami and a monster hurricane. The iB1350 can survive passively such devastation and a very prolonged SBO without any support from the outside of a site up to 7 days even preventing core melt. It, however, is based on the well-established proven ABWR design. The NSSS is exactly the same as that of the current ABWR. As for safety design, it has a double cylinder RCCV (Mark W containment) and in-depth hybrid safety systems (IDHS). The Mark W containment has double FP confinement barriers and the in-containment filtered venting system (IFVS) that enable passively no emergency evacuation outside the immediate vicinity of the plant for a SA. It has a large volume to hold hydrogen, an innovative core catcher (iCC), a passive flooding system and an innovative passive containment cooling system (iPCCS) establishing passively practical elimination of containment failure even in a long term. The IDHS consists of 4 division active safety systems for a DBA, 2 division active safety systems for a SA and built-in passive safety systems (BiPSS) consisting of an isolation condenser (IC) and the iPCCS for a SA. While the conventional PCCS can never cool the S/P, the iPCCS can automatically cool the S/P directly even in a DBA LOCA. That makes it possible for the iB1350 to optimize the active safety systems for a DBA. Sato came up with several optimized configurations of the IDHS that are expected to achieve further cost reduction and enhance its reliability resulting from passive feature of the iPCCS. The IC/iPCCS pool has enough capacity for 7 day grace period. The IC/iPCCS heat exchangers, the core and the spent fuel pool are

  18. Fungal levels in houses in the Fukushima Daiichi Nuclear Power Plant evacuation zone after the Great East Japan Earthquake.

    Science.gov (United States)

    Shinohara, Naohide; Tokumura, Masahiro; Hashimoto, Kazuhiro; Asano, Katsuyoshi; Kawakami, Yuji

    2017-10-01

    Residences located within 20 km of the damaged Fukushima Daiichi Nuclear Power Plant were evacuated shortly after the Great East Japan Earthquake. The levels of airborne and surface fungi were measured in six houses in the evacuation zone in August 2012 and February 2013. Airborne fungal levels in all of the houses in the summer were higher than the environmental standard levels for residential houses published in Architectural Institute of Japan (>1000 colony-forming units [CFU]/m 3 ). In two houses whose residents rarely returned to visit, fungal levels were extremely high (>52,000 CFU/m 3 ). Although fungal levels in the winter were much lower than those in the summer, they were still higher than environmental standard levels in several houses. Indoor fungal levels were significantly inversely related to the frequency with which residents returned, but they were not correlated with the air exchange rates, temperature, humidity, or radiation levels. Cladosporium spp. and Penicillium spp. were detected in every house. Aspergillus section Circumdati (Aspergillus ochraceus group) was also detected in several houses. These fungi produced ochratoxin A and ochratoxin B, which have nephrotoxic and carcinogenic potential. The present study suggests that further monitoring of fungal levels is necessary in houses in the Fukushima Daiichi Nuclear Power Plant evacuation zone, and that some houses may require fungal disinfection. The results suggest that residents' health could be at risk owing to the high levels of airborne fungi and toxic fungi Aspergillus section Circumdati. Therefore, monitoring and decontamination/disinfection of fungi are strongly recommended before residents are allowed to return permanently to their homes. In addition, returning to home with a certain frequency and adequate ventilation are necessary during similar situations, e.g., when residents cannot stay in their homes for a long period, because fungal levels in houses in the Fukushima Daiichi

  19. Tritium in Japanese precipitation following the March 2011 Fukushima Daiichi Nuclear Plant accident

    Energy Technology Data Exchange (ETDEWEB)

    Matsumoto, Takuya, E-mail: t.matsumoto@iaea.org [Isotope Hydrology Section, Division of Physical and Chemical Sciences, International Atomic Energy Agency, Vienna International Centre, 1400 Vienna (Austria); Maruoka, Teruyuki [Division of Integrative Environmental Sciences Graduate School of Life and Environmental Sciences, University of Tsukuba, 1-1-1 Tennodai, Tsukuba City, Ibaraki 305-8572 (Japan); Shimoda, Gen [Geological Survey of Japan, National Institute of Advanced Industrial Science and Technology, 1-1-1 Higashi, Tsukuba City, Ibaraki 305-8561 (Japan); Obata, Hajime [Atmosphere and Ocean Research Institute, The University of Tokyo, 5-1-5, Kashiwanoha, Kashiwa-shi, Chiba 277-8564 (Japan); Kagi, Hiroyuki [Geochemical Research Center, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-0033 (Japan); Suzuki, Katsuhiko [Japan Agency for Marin-Earth Science and Technology, 2-15, Natsushima, Yokosuka, Kanagawa 237-0061 (Japan); Yamamoto, Koshi [Graduate School of Environmental Studies, Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8601 (Japan); Mitsuguchi, Takehiro [215 Ooma Akadoji-cho Konan, 483-8226 (Japan); Usa Marine Biological Institute, Kochi University, 194 Inoshiri, Usa, Tosa, Kochi 781-1164 (Japan); Hagino, Kyoko; Tomioka, Naotaka [Institute for Study of the Earth' s Interior, Okayama University at Misasa, 827 Yamada, Misasa, Tottori 682-0193 (Japan); Sambandam, Chinmaya; Brummer, Daniela; Klaus, Philipp Martin; Aggarwal, Pradeep [Isotope Hydrology Section, Division of Physical and Chemical Sciences, International Atomic Energy Agency, Vienna International Centre, 1400 Vienna (Austria)

    2013-02-15

    Tritium concentrations in Japanese precipitation samples collected after the March 2011 accident at the Fukushima Dai-ichi Nuclear Power Plant (FNPP1) were measured. Values exceeding the pre-accident background were detected at three out of seven localities (Tsukuba, Kashiwa and Hongo) southwest of the FNPP1 at distances varying between 170 and 220 km from the source. The highest tritium content was found in the first rainfall in Tsukuba after the accident; however concentrations were 500 times less than the regulatory limit for tritium in drinking water. Tritium concentrations decreased steadily and rapidly with time, becoming indistinguishable from the pre-accident values within five weeks. The atmospheric tritium activities in the vicinity of the FNPP1 during the earliest stage of the accident was estimated to be 1.5 × 10{sup 3} Bq/m{sup 3}, which is potentially capable of producing rainwater exceeding the regulatory limit, but only in the immediate vicinity of the source. - Highlights: ► We measured the {sup 3}H contents of Japanese rain collected after the Fukushima accident. ► {sup 3}H level became 30 times higher than pre-accident level in the first rain at Tsukuba. ► Some locality within 220 km from the source showed elevated {sup 3}H levels. ► These high {sup 3}H signals disappear in a few weeks. ► Atmospheric {sup 3}H level at the source during the earliest stage was estimated to be 1500 Bq/m{sup 3}.

  20. Fukushima Daiichi. Post accident countermeasures and mid-and-long-term action plan

    International Nuclear Information System (INIS)

    Yamashita, Kazuhiko

    2012-01-01

    Since accident at Fukushima Daiichi nuclear power station, TEPCO had made strenuous efforts to maintain stable cooling of reactors and suppress discharge of radioactive materials under the cooperation of the government and others concerned. Various activities towards settlement of the accident had been done according to the roadmap proposed on April 17, 2011. This article described outlines of post accident countermeasures and current activities toward decommissioning based on mid-and-long-term action plan. Step 2 completion in roadmap towards settlement of the accident was confirmed on Dec. 16, 2011; (1) reactors: attainment of a condition equivalent to 'cold shutdown' with temperature of RPV bottom below 100degC, release of radioactive materials from PCV under control and public radiation exposure by additional release being significantly held down (evaluated as maximum 0.2 mSv/y at the site boundary), and mid-term safety of circulating water injection cooling system, (2) spent fuel pools: more stable cooling with circulating cooling system by installation of heat exchanger, (3) radioactive contaminated water: reduction of total amount with full-fledged processing facilities, desalination processing (reuse), storage and mitigation of contamination in the ocean, (4) commence construction of water shielding wall to prevent contamination of the ocean via the underground water, (5) installation of reactor building cover of unit 1 to restrain release of radioactive materials, and others. According to mid-to-long-term roadmap towards the decommissioning of Fukushima Nuclear Power Units 1-4, current activities were to (1) maintain stable reactor cooling and accumulated water processing and improve their credibility, (2) reduce the radiation impact due to additional emissions from the whole site and radioactive waste generated after the accident, (3) commence removal of fuel from the spent fuel pools (unit 4 within 2 years), (4) commence R and D and decontamination the

  1. Radiation control in the core shroud replacement project of Fukushima-Daiichi NPS Unit no.2

    International Nuclear Information System (INIS)

    Kokubun, Yasunori; Haraguchi, Kazuyuki; Yoshizawa, Yuji; Yamada, Yasuo

    2000-01-01

    In Fukushima-Daiichi NPS Unit no.2, the core shroud replacement was made following that of Unit no.3. This project involves replacement of wide-ranging equipment, with the project extending over a long period of time. This was expected to increase the dose equivalent of workers. Accordingly, various measures to lower the dose equivalent were planned and implemented. We outline radiation controls implemented during the project period. The shroud replacement project was a preventive maintenance project which consisted of replacing the core shroud and other internals with those less susceptible to stress corrosion cracking. Problems related to radiation control during the replacement project of Unit no.3 the year before last were summarized. We studied, planned, and implemented measures to be reflected in the project for Unit no.2. This was done to lower the dose equivalent as much as possible while paying due attention to safety and economy. For radiation control during the project for Unit no.2, experiments with Unit no.3 were fully exploited and any effective measures taken at that time were adopted in this project. Problems pointed out after that project with Unit no.3 resulted in new or improved measures being taken with Unit no.2. Measures taken over from the project with Unit no.3; a. Daily analysis of difference between expected and actual dose equivalents b. Dose reduction measures, chemical decontamination, temporary shield, flushing, etc.; New or improved measures; a. Dose reduction measures: Mechanical removal of radiation sources, strengthening of shield, etc.; b. Automatic remote control system; c. Use of new protective devices. With measures implemented as described above, the dose equivalent during shroud replacement of Unit no.2 was reduced by about 30% when compared with that (11.5 persons · Sv) in the case of Unit no.3. Implemented radiation controls will be checked and reviewed in future for reflection in projects with other units. (author)

  2. Environmental behavior of the radionuclides released from the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Yamazaki, Hideo

    2014-01-01

    The environmental behavior of radioactive nuclides released from the Fukushima Daiichi Nuclear Power Station (FDNPS) accident in eastern Japan was investigated. The radioactive pollution of environmental samples, including airborne dust, soil, sediment, fish, and other organisms was described. It was evaluated for environmental behavior and fate of the radioactive material from the spatial and temporal distribution of the radioactive nuclides. In Higashiosaka City about 600 km away from FDNPS, it begins to detect the radioactive nuclides in the airborne dust from 25th March 2011. Radioactive fission products 95 Zr- 95 Nb was detected on 18th April. The concentrations of 131 I, 134 Cs, and 137 Cs in the soil collected from Fukushima City were 126000, 14000, and 14200 Bq/kg on 19th March 2011 and 12800, 13200, and 13700 Bq/kg on 26th March 2011, respectively. The concentrations of 131 I, 134 Cs, and 137 Cs in the soil samples collected from March-June 2011 from study sites in metropolitan area and Kanto region ranged from nd to 91900, 59 to 16100, and 69 to 17600 Bq/kg, respectively. (Concentrations of 131 I were done decay correction to the value of 16th March) Radioactivities in fish samples collected from off FDNPS, Tokyo Bay, and Kejonuma Pond were measured. The radioactive contamination of forest ecosystem was also investigated. Two processes are involved in the radioactive contamination of the environment from the FDNPS accident. One is contamination by radioactive nuclides released from the hydrogen explosion. Leakage of contaminated cooling water to the ocean is in other important environmental pollution. We must continue carefully monitoring of radioactive nuclides in the environment. (author)

  3. The total release of xenon-133 from the Fukushima Dai-ichi nuclear power plant accident

    International Nuclear Information System (INIS)

    Stohl, Andreas; Seibert, Petra; Wotawa, Gerhard

    2012-01-01

    The accident at the Fukushima Dai-ichi nuclear power plant (FD-NPP) on 11 March 2011 released large amounts of radioactivity into the atmosphere. We determine the total emission of the noble gas xenon-133 ( 133 Xe) using global atmospheric concentration measurements. For estimating the emissions, we used three different methods: (i) using a purely observation-based multi-box model, (ii) comparisons of dispersion model results driven with GFS meteorological data with the observation data, and (iii) such comparisons with the dispersion model driven by ECMWF data. From these three methods, we have obtained total 133 Xe releases from FD-NPP of (i) 16.7 ± 1.9 EBq, (ii) 14.2 ± 0.8 EBq, and (iii) 19.0 ± 3.4 EBq, respectively. These values are substantially larger than the entire 133 Xe inventory of FD-NPP of about 12.2 EBq derived from calculations of nuclear fuel burn-up. Complete release of the entire 133 Xe inventory of FD-NPP and additional release of 133 Xe due to the decay of iodine-133 ( 133 I), which can add another 2 EBq to the 133 Xe FD-NPP inventory, is required to explain the atmospheric observations. Two of our three methods indicate even higher emissions, but this may not be a robust finding given the differences between our estimates. - Highlights: ► We determine the total release of xenon-133 from the Fukushima nuclear accident. ► We used global measurements and a box model, as well as dispersion model estimates. ► Total 133 Xe release is about 14.2-19 EBq, more than Fukushima 133 Xe inventory. ► Additional release of iodine-133 and decay into 133 Xe needed to explain results.

  4. Iodine-129 depth profiles in soil within 30 km from Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Honda, M.; Matsuzaki, H.; Tsuchiya, Y.S.; Nakano, C.; Yamagata, T.; Nagai, H.; Matsushi, Y.; Maejima, Y.

    2013-01-01

    Iodine-129 depth profiles of 13 soil cores were analyzed by AMS to evaluate the distribution and the mobility in soil. The cores were sampled from various fields around the Fukushima Daiichi Nuclear Power Plant (FDNPP). Four cores out of the 13 were collected from almost the same position in Kawauchi village crop field 20 km apart from FDNPP at different times between April 2011 and June 2012 to observe the temporal variation of depth profile of "1"2"9I in soil. On the all of 13 soil cores, clear enhancement of the accident origin "1"2"9I was observed. From the crop field soil cores in Kawauchi village, "1"2"9I inventory was estimated as 43.4±2.7 mBq m"-"2 (3.10x10"1"3 atoms m"-"2). There is positive relationship between relaxation length and the elapsed time since the FDNPP accident. The increase rate of the relaxation length is about 1 cm yr"-"1 which should reflect the downward transfer rate of the Fukushima-derived "1"2"9I. Other 9 cores were collected from various fields including crop fields and man-made soils within 30 km from FDNPP on June 2012. Cumulative "1"2"9I inventory fraction [%] from the surface was calculated. The inventory fraction within top 5 cm varied widely, 65-100% with median 82%. Similarly the inventory fraction within top 10 cm varied 82 to 100% with the median 95%. (author)

  5. Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident

    Energy Technology Data Exchange (ETDEWEB)

    Sadeghi, Nahid; Ahangari, Rohollah; Kasesaz, Yaser; Noori-kalkhoran, O. [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of). Reactor Research School

    2017-11-15

    In the case of Fukushima Daiichi nuclear power plant (FNP) accident, the radioactive material was released from reactor units 1-3 and transported to short and long distances due to the atmospheric pathways-motions. Power sources for monitoring posts were lost due to earthquake and tsunami. Based on air dose rates and other data measured by monitoring cars, the amount of radioactive material released to the atmosphere from the power station was obtained. The atmospheric dispersion and the transport model used in the RASCAL code, estimate the radionuclide concentrations downwind, both in the air and on the ground due to deposition. The calculated concentrations are then used to estimate the projected doses for workers in vicinity of the accident area in the first minutes of accident time. For dose modeling, we assumed that each worker was 15 min in vicinity of FNP in accident situation, once without and once with protective clothes or respirator. According to Tokyo Electric Power Company (TEPCO) report six workers had received doses over 250 mSv (309 to 678 mSv) apparently due to inhaling Iodine-131 fume. In this paper the calculated dose results using RASCAL code shows that, if emergency workers who work in early phase of accident had not used protective equipment, for 15 min, inhalation doses from iodine in their thyroid gland up to 12 March afternoon would have been 520 mSv. A comparison between calculation results and TEPCO report shows that dose calculated virtually is nearly equal to TEPCO measurement results.

  6. Birth Outcomes after the Fukushima Daiichi Nuclear Power Plant Disaster: A Long-Term Retrospective Study

    Directory of Open Access Journals (Sweden)

    Claire Leppold

    2017-05-01

    Full Text Available Changes in population birth outcomes, including increases in low birthweight or preterm births, have been documented after natural and manmade disasters. However, information is limited following the 2011 Fukushima Daiichi Nuclear Power Plant Disaster. In this study, we assessed whether there were long-term changes in birth outcomes post-disaster, compared to pre-disaster data, and whether residential area and food purchasing patterns, as proxy measurements of evacuation and radiation-related anxiety, were associated with post-disaster birth outcomes. Maternal and perinatal data were retrospectively collected for all live singleton births at a public hospital, located 23 km from the power plant, from 2008 to 2015. Proportions of low birthweight (<2500 g at birth and preterm births (<37 weeks gestation at birth were compared pre- and post-disaster, and regression models were conducted to assess for associations between these outcomes and evacuation and food avoidance. A total of 1101 live singleton births were included. There were no increased proportions of low birthweight or preterm births in any year after the disaster (merged post-disaster risk ratio of low birthweight birth: 0.98, 95% confidence interval (CI: 0.64–1.51; and preterm birth: 0.68, 95% CI: 0.38–1.21. No significant associations between birth outcomes and residential area or food purchasing patterns were identified, after adjustment for covariates. In conclusion, no changes in birth outcomes were found in this institution-based investigation after the Fukushima disaster. Further research is needed on the pathways that may exacerbate or reduce disaster effects on maternal and perinatal health.

  7. The relationship between media consumption and health-related anxieties after the Fukushima Daiichi nuclear disaster.

    Science.gov (United States)

    Sugimoto, Amina; Nomura, Shuhei; Tsubokura, Masaharu; Matsumura, Tomoko; Muto, Kaori; Sato, Mikiko; Gilmour, Stuart

    2013-01-01

    The Fukushima Daiichi nuclear disaster caused a global panic by a release of harmful radionuclides. In a disaster setting, misusage of contemporary media sources available today can lead to disseminated incorrect information and panic. The study aims to build a scale which examines associations between media and individual anxieties, and to propose effective media usages for future disaster management. The University of Tokyo collaborated with the Fukushima local government to conduct a radiation-health-seminar for a total of 1560 residents, at 12 different locations in Fukushima. A 13 item questionnaire collected once before and after a radiation-seminar was used on factor analysis to develop sub-scales for multiple regression models, to determine relationships between the sub-scales and media type consumed. A paired t-test was used to examine any changes in sub-scale of pre- and post-seminar scores. Three sub-scales were revealed and were associated with different media types: was with rumors, while concern for the future was positively associated with regional-newspapers and negatively with national-newspapers. Anxiety about social-disruption was associated with radio. The seminar had a significant effect on anxiety reduction for all the three sub-scales. Different media types were associated with various heightened concerns, and that a radiation seminar was helpful to reduce anxieties in the post-disaster setting. By tailoring post-disaster messages via specific media types, i.e., radio, it may be possible to effectively convey important information, as well as to calm fears about particular elements of post-disaster recovery and to combat rumors.

  8. The relationship between media consumption and health-related anxieties after the Fukushima Daiichi nuclear disaster.

    Directory of Open Access Journals (Sweden)

    Amina Sugimoto

    Full Text Available BACKGROUND: The Fukushima Daiichi nuclear disaster caused a global panic by a release of harmful radionuclides. In a disaster setting, misusage of contemporary media sources available today can lead to disseminated incorrect information and panic. The study aims to build a scale which examines associations between media and individual anxieties, and to propose effective media usages for future disaster management. METHODS: The University of Tokyo collaborated with the Fukushima local government to conduct a radiation-health-seminar for a total of 1560 residents, at 12 different locations in Fukushima. A 13 item questionnaire collected once before and after a radiation-seminar was used on factor analysis to develop sub-scales for multiple regression models, to determine relationships between the sub-scales and media type consumed. A paired t-test was used to examine any changes in sub-scale of pre- and post-seminar scores. RESULTS: Three sub-scales were revealed and were associated with different media types: was with rumors, while concern for the future was positively associated with regional-newspapers and negatively with national-newspapers. Anxiety about social-disruption was associated with radio. The seminar had a significant effect on anxiety reduction for all the three sub-scales. CONCLUSION: Different media types were associated with various heightened concerns, and that a radiation seminar was helpful to reduce anxieties in the post-disaster setting. By tailoring post-disaster messages via specific media types, i.e., radio, it may be possible to effectively convey important information, as well as to calm fears about particular elements of post-disaster recovery and to combat rumors.

  9. Corrosion resistance of tank material for flock storage in the Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sano, Yuichi; Anbai, Hiromu; Takeuchi, Masayuki; Ogino, Hideki; Koizumi, Kenji

    2014-01-01

    The installation of the storage tank made of SS400 is under planning in the Fukushima Daiichi nuclear power plant for the flock which was generated in the coagulation process for radioactive contaminated water. The flock contains the seawater and has a possibility to make a crevice and local corrosion on the surface of the tank. Air agitation will be applied in the storage tank to prevent the accumulation of the flock and hydrogen generated by radiolysis, which will increase the diffusion of oxygen and the corrosion of SS400. In addition, the effect of radiation from the flock on the corrosion should be considered. In this study, we investigated the corrosion behavior of SS400 in the flock under the aeration-agitation condition with γ-ray irradiation. Based on the flock storage condition announced by Tokyo Electric Power Company (TEPCO), immersion tests were performed with SS400 coupons under several conditions and corrosion rates were estimated by the weight loss of the coupons. After the immersion tests, the surfaces of the coupons were observed by microscopy for evaluating the local corrosion. To evaluate corrosion mechanism in detail, electrochemical tests were also carried out. In all of these tests, the non-radioactive flock as a surrogate and artificial seawater were used. Corrosion rates of SS400 increased significantly with aeration flow rates in the seawater with/without the flock, but this tendency was weaker in the seawater with the flock, especially under the condition where coupons were buried in the flock. The electrochemical tests indicated the suppression of the cathodic reaction, i.e. dissolved oxygen reduction, in the seawater with the flock. The effect of γ-ray irradiation on the corrosion rates was not remarkable under the assumed dose rate. Microscopic analysis of the immersed coupons showed no severe corrosion including local corrosion occurred. The corrosion rate could be decreased effectively by suppressing the dissolved oxygen reduction

  10. Estimation of internal exposure dose from food after the Fukushima Daiichi Nuclear Power Station disaster

    International Nuclear Information System (INIS)

    Takizawa, Mari; Yoshizawa, Nobuaki; Kawai, Masaki; Miyatake, Hirokazu; Hirakawa, Sachiko; Murakami, Kana; Sato, Osamu; Takagi, Shunji; Suzuki, Gen

    2016-01-01

    In order to estimate the internal exposure dose from food due to the Fukushima Daiichi Nuclear Power Station accident, total diet study (TDS) has been carried out. TDS is a method for estimating how much of certain chemicals people intake in the normal diet. A wide range of food products are chosen as targets, and the increase or decrease of chemicals depending on processing or cooking is taken into account. This paper glanced at the transition of TDS survey results, and with a focus on the survey results of the market basket (MB) system, which is one of the TDS techniques, it examined a decrease in the committed effective dose per year of radioactive cesium. Although the values of internal exposure dose from food in Fukushima Prefecture and surrounding prefectures are even now in a relatively high tendency compared with those in the distant regions, the difference has been narrowing. According to the attenuation prediction of internal exposure dose in each region of Fukushima Prefecture, the values after 5 years from the accident will be lower than the measured value on the food in market that has been investigated during 1989 and 2005. In addition, the internal exposure dose that was the survey results based on MB system in September - October 2014 was 0.0007 to 0.0022 mSv/year. These values are very small at 1% or less of the upper limit dose of 1 mSv/year as the setting basis of current reference value in Japan. (A.O.)

  11. Impact of the Fukushima Daiichi nuclear power plant accident on local community and healthcare services

    International Nuclear Information System (INIS)

    Oikawa, Tomoyoshi

    2013-01-01

    The Soso region of Japan, located in the northern part of the Pacific side of Fukushima Prefecture, has suffered tremendously from widespread damage caused by the earthquake, tsunami and the Fukushima Dai-ichi nuclear power plant accident. Immediately after the disaster it even seemed that the restoration of this region itself would not be possible. However after six months, the Indoor Restriction Order and evacuation orders within a 20 to 30 km zone from the plant, such as the Evacuation-Prepared Area in Case of Emergency, were lifted and all of those restrictions for the planned evaluation zone has been eased in line with the actual conditions of each region. A year and a month after the earthquake, the Caution Zone, which was declared to prohibit the entry to the zone within the 20 km radius from the plant, was lifted. Thus people can now enter as close as 10 km from the plant. Minami-Soma city is an administrative district which had the largest population (approximately 71,500 residents) within the 20 to 30 km zone prior to the earthquake. It was, also, the only district where the evacuation was not conducted by the municipality. The city is now called the Genpatsu frontline district as it is the closest city to the plant where people have continued to live. Due to the damage caused by the earthquake and Tsunami, the city has suffered both from destruction by the tsunami and radiation, and people are still facing numerous problems despite the fact that the city appears to have been restored on its surface. It is very unfortunate that much of the medical data from the region was lost in the confusion after the Great East Japan Earthquake. In this paper various facts after the disaster based on the data left in the So-so region, Minamisoma city, and Minamisoma municipal general hospital are reported. (author)

  12. Suppositional analysis for the nuclear accidents at the Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    Yoshida, Yoshitaka

    2012-01-01

    The Great East Japan Earthquake which occurred on March 11, 2011 set off a series of events that have led to a serious nuclear disaster. The Fukushima Daiichi Nuclear Power Station suffered damage due to the huge tsunami waves triggered by the earthquake, which lead to release of large amounts of radioactive materials into the environment. Using the limited information presented by the government and others within several days after the accident, this study examined the amount of radioactive materials released into the atmosphere predicted using the incident progress prediction system (IPPS) and the radioactive release, radiation dose and radiological protection area prediction system (R-Cubic) each developed by INSS, and compared those findings with the amount of radioactive materials evaluated by the government and the Tokyo Electric Power Company. The following points were seen (1) The step-by-step public protection measures taken by the government were consistent with the amount of released radioactive materials by R-Cubic. (2) The IPPS underestimated the amount of released radioactive materials when the irradiation levels in the nuclear reactors were analyzed according to the observed nuclear reactor water levels, although these were well in agreement with the observed parameters. (3) The amounts of released radioactive materials predicted by R-Cubic agreed well with those of the Nuclear Safety Commission and the Nuclear and Industrial Safety Agency. (4) The 0.5MeV equivalent value of noble gases in the amount of radioactive materials released into the atmosphere shown by TEPCO on May 2012 was considered to be an underestimate. (author)

  13. The Recent Situation of Fukushima Daiichi Plants and the Related Water Chemistry Problems

    International Nuclear Information System (INIS)

    Makihira, Atsutoshi; GOTO, Akira; Ishikawa, Keiji

    2012-09-01

    Fukushima Daiichi Nuclear Power Station was hit by the big earthquake and tsunami, which caused the station black out and subsequent loss of cooling functions for reactors and spent fuel pools (SFPs). Consequently the fuels were damaged, hydrogen explosion blew off top of the reactor buildings and radioactive materials were released to the atmosphere and the ocean. In the accident, one of the most important mission is to cool the reactors and SFPs stably with removing radionuclides and impurities in the water. The water injected into the reactors has been leaked off and accumulated in the basement of the reactor and turbine buildings. Hence the water was highly contaminated, we had to purify it and reused for cooling by 'circulating water cooling system'. The system is mainly composed of removal of radioactive materials and desalination. With improving the equipment reliability, sufficient quantity of cooling water is being able to supply for the reactors. We have achieved the inside reactor temperatures of units 1,2,3 approximately below 100 degrees C as of December 2011. The SFPs were firstly cooled by spraying water from the outside at rooftop areas, or seawater was injected through a piping of Fuel Pool Cooling System (FPC). Afterwards, alternative circulating cooling systems were installed that allowed SFPs of unit 1 to 4 for cooling. The water purification system was also introduced for preventing corrosion of SFP lining. By using the system, SFP water quality has been improved and each temperature is stable at approximately 30 degree C as of June 2012. (authors)

  14. Local variance of atmospheric 14C concentrations around Fukushima Dai-ichi Nuclear Power Plant from 2010 to 2012

    DEFF Research Database (Denmark)

    Chen, Biying; Xu, Sheng; Cook, Gordon T.

    2017-01-01

    Radiocarbon (14C) has been measured in single tree ring samples collected from the southwest of the Fukushima Dai-ichi Nuclear Power Plant. Our data indicate south-westwards dispersion of radiocarbon and the highest 14C activity observed so far in the local environment during the 2011 accident....... The abnormally high 14C activity in the late wood of 2011 ring may imply an unknown source of radiocarbon nearby after the accident. The influence of 14C shrank from 30 km during normal reactor operation to 14 km for the accident in the northwest of FDNPP, but remains unclear in the southwest....

  15. Study on filling materials suitable for seawater piping trench closure work at Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Yanai, Shuji; Hibi, Yasuki; Nishikori, Kazumasa; Sato, Keita

    2016-01-01

    Highly contaminated water leaking from the reactor buildings and turbine buildings damaged by the 2011 Great East Japan Earthquake has accumulated in the seawater piping trenches of Fukushima Daiichi Nuclear Power Station Units 2, 3, and 4. In November 2014, work commenced to replace and remove this contaminated water by filling the trenches with filling materials, and this work was completed in December 2015. This paper summarizes the contents of this study on various filling materials, including special fillers with long-distance underwater flowability applied to the horizontal tunnel parts of the trenches. (author)

  16. Removal of Radionuclides from Waste Water at Fukushima Daiichi Nuclear Power Plant: Desalination and Adsorption Methods - 13126

    Energy Technology Data Exchange (ETDEWEB)

    Kani, Yuko; Kamosida, Mamoru; Watanabe, Daisuke [Hitachi Research Laboratory, Hitachi, Ltd., 7-2-1 Omika-cho, Hitachi, Ibaraki, 319-1221 (Japan); Asano, Takashi; Tamata, Shin [Hitachi Works, Hitachi-GE Nuclear Energy, Ltd. (Japan)

    2013-07-01

    Waste water containing high levels of radionuclides due to the Fukushima Daiichi Nuclear Power Plant accident, has been treated by the adsorption removal and reverse-osmosis (RO) desalination to allow water re-use for cooling the reactors. Radionuclides in the waste water are collected in the adsorbent medium and the RO concentrate (RO brine) in the water treatment system currently operated at the Fukushima Daiichi site. In this paper, we have studied the behavior of radionuclides in the presently applied RO desalination system and the removal of radionuclides in possible additional adsorption systems for the Fukushima Daiichi waste water treatment. Regarding the RO desalination system, decontamination factors (DFs) of the elements present in the waste water were obtained by lab-scale testing using an RO unit and simulated waste water with non-radioactive elements. The results of the lab-scale testing using representative elements showed that the DF for each element depended on its hydrated ionic radius: the larger the hydrated ionic radius of the element, the higher its DF is. Thus, the DF of each element in the waste water could be estimated based on its hydrated ionic radius. For the adsorption system to remove radionuclides more effectively, we studied adsorption behavior of typical elements, such as radioactive cesium and strontium, by various kinds of adsorbents using batch and column testing. We used batch testing to measure distribution coefficients (K{sub d}s) for cesium and strontium onto adsorbents under different brine concentrations that simulated waste water conditions at the Fukushima Daiichi site. For cesium adsorbents, K{sub d}s with different dependency on the brine concentration were observed based on the mechanism of cesium adsorption. As for strontium, K{sub d}s decreased as the brine concentration increased for any adsorbents which adsorbed strontium by intercalation and by ion exchange. The adsorbent titanium oxide had higher K{sub d}s and it

  17. Mobility of radioactive cesium in soil originated from the Fukushima Daiichi nuclear disaster. Application of extraction experiments

    International Nuclear Information System (INIS)

    Yoshikazu Kikawada; Takao Oi; Katsumi Hirose; Masaaki Hirose; Atsushi Tsukamoto; Ko Nakamachi; Teruyuki Honda; Hiroaki Takahashi

    2015-01-01

    Extraction experiments on soil radioactively contaminated by the Fukushima Daiichi Nuclear Power Plant accident were conducted by using a variety of extractants to acquire knowledge on the mobility of radioactive cesium in soil. The experimental results revealed that cesium is tightly bound with soil particles and that radioactive cesium newly deposited on soil due to the accident had apparently a higher mobility than stable cesium commonly existing in soil. The results suggested that radioactive cesium deposited on soil hardly migrates via aqueous processes, although chemical and mineralogical conditions of soil affect their mobility. (author)

  18. Measurement of Iodine-129 in surface soil collected near the Fukushima Daiichi nuclear power plant accident site

    International Nuclear Information System (INIS)

    Miyake, Yasuto; Matsuzaki, Hiroyuki; Fujiwara, Takeshi; Saito, Takumi; Yamagata, Takeyasu; Honda, Maki

    2013-01-01

    Iodine-129 in soil around Fukushima Daiichi nuclear power plant were measured by Accelerator Mass Spectrometry and isotopic ratio of radioiodine was estimated. Surface deposition amount of Iodine-129 resulted in 6.7 to 5500 mBq/m"2. The mean isotopic ratio between Iodine-129 and Iodine-131 at the accident was estimated that "1"2"9"I"/"1"3"1I = 26±6 as of March 11 2011. This result was compared to the calculation result of ORIGEN2 code to test the validity of this estimation. (author)

  19. Removal of Radionuclides from Waste Water at Fukushima Daiichi Nuclear Power Plant: Desalination and Adsorption Methods - 13126

    International Nuclear Information System (INIS)

    Kani, Yuko; Kamosida, Mamoru; Watanabe, Daisuke; Asano, Takashi; Tamata, Shin

    2013-01-01

    Waste water containing high levels of radionuclides due to the Fukushima Daiichi Nuclear Power Plant accident, has been treated by the adsorption removal and reverse-osmosis (RO) desalination to allow water re-use for cooling the reactors. Radionuclides in the waste water are collected in the adsorbent medium and the RO concentrate (RO brine) in the water treatment system currently operated at the Fukushima Daiichi site. In this paper, we have studied the behavior of radionuclides in the presently applied RO desalination system and the removal of radionuclides in possible additional adsorption systems for the Fukushima Daiichi waste water treatment. Regarding the RO desalination system, decontamination factors (DFs) of the elements present in the waste water were obtained by lab-scale testing using an RO unit and simulated waste water with non-radioactive elements. The results of the lab-scale testing using representative elements showed that the DF for each element depended on its hydrated ionic radius: the larger the hydrated ionic radius of the element, the higher its DF is. Thus, the DF of each element in the waste water could be estimated based on its hydrated ionic radius. For the adsorption system to remove radionuclides more effectively, we studied adsorption behavior of typical elements, such as radioactive cesium and strontium, by various kinds of adsorbents using batch and column testing. We used batch testing to measure distribution coefficients (K d s) for cesium and strontium onto adsorbents under different brine concentrations that simulated waste water conditions at the Fukushima Daiichi site. For cesium adsorbents, K d s with different dependency on the brine concentration were observed based on the mechanism of cesium adsorption. As for strontium, K d s decreased as the brine concentration increased for any adsorbents which adsorbed strontium by intercalation and by ion exchange. The adsorbent titanium oxide had higher K d s and it was used for

  20. MDEP Design-Specific Common Position CP-APR1400WG-01. Common position addressing Fukushima Daiichi nuclear power plant accident

    International Nuclear Information System (INIS)

    2016-05-01

    The MDEP APR1400 Working Group (APR1400WG) members consist of members from Republic of Korea, United Arab Emirates, and the United States. A main objectives of MDEP is to encourage convergence of code, standard and safety goals with exploring the opportunities for harmonization of regulatory practice and cooperation on safety review of APR-1400 specific designs. This common position addressing is aimed at sharing knowledge, information and experience on safety improvement related to lessons learned from the Fukushima Daiichi NPP Accident or Fukushima Daiichi NPP Accident-related issues amongst APR-1400 WG member states to achieve the MEDP goal. Because not all of these Regulators have completed the regulatory review of their APR1400 applications yet, this paper identifies common preliminary approaches to address potential safety improvements for APR1400 plants, as well as common general expectations for new nuclear power plants, as related to lessons learned from the Fukushima Daiichi NPP Accident or Fukushima Daiichi NPP Accident-related issues. While some asymmetry exists among those of three Regulators in terms of design, regulatory practice and licensing milestone sharing information and common understanding on post-Fukushima Daiichi NPP Accident enhancement would be promote resilient design for countering beyond design extreme external event like Fukushima Daiichi NPP nuclear disaster. This common position paper aims at identifying characteristics of post-Fukushima Daiichi NPP Accident enhancements putting in place by each country and setting common position to achieve balanced and harmonized APR-1400 design. After the safety reviews of the APR1400 design applications that are currently in review are completed, the regulators will update this paper to reflect their safety conclusions regarding the APR1400 design and how the design could be enhanced to address Fukushima Daiichi NPP Accident-related issues. The common preliminary approaches are organised into

  1. Damage of reactor buildings occurred at the Fukushima Daiichi accident. Focusing on sequence leading to hydrogen explosions

    International Nuclear Information System (INIS)

    Naito, Masanori

    2011-01-01

    Fukushima Daiichi accident discharged enormous radioactive materials confined inside into the environment due to hydrogen explosions occurred at reactor buildings and forced many people to live the refugee life. This article described overview of Great East Japan Earthquake, specifications of Fukushima Daiichi nuclear power plants, sequence of plant status after earthquake occurrence and computerized simulation of plant behavior of Unit 1 leading to core melt and hydrogen explosion. Simulation results with estimated and assumed conditions showed water level decreased to bottom of reactor core after 4 hrs and 15 minutes passed, core melt started after 6 hrs and 49 minutes passed, failure of core support plate after 7 hrs and 18 minutes passed and through failure of penetration at bottom of pressure vessel after 7 hrs and 25 minutes passed. Hydrogen concentration at operating floor of reactor building of Unit 1 would be 15% accumulated and the pressure would amount to about 5 bars after hydrogen explosion if reactor building did not rupture with leak-tight structure. Since reactor building was not pressure-proof structure, walls of operating floor would rupture before 5 bars attained. (T. Tanaka)

  2. Monitoring of Radionuclide Contamination in Food Samples in Malaysia due to Daiichi Reactor Accident in Fukushima, Japan

    International Nuclear Information System (INIS)

    Nurrul Assyikeen Mohd Jaffary; Wo, Y.M.; Abdul Kadir Ishak

    2015-01-01

    On March 11, 2011, a serious accident occurred in Daiichi nuclear reactor plant, Fukushima, Japan which caused radioactive materials been released into the atmosphere in the form of aerosols and dust particles. Sea water around the plant was also found contaminated with high radioactivity readings. These radioactive materials could be transported by the winds and ocean current across international borders and cannot be controlled by human. Thus, a continuous monitoring activity of radionuclide content in the air and sea water needs to be conducted by the authorities. In addition to radioactivity monitoring, Malaysia should also control the entry of contaminated food in order to prevent radionuclide ingestion by human. The radionuclide 131 I, 134 Cs and 137 Cs were used as a measure of pollution levels and counted with gamma spectrometry using standard analysis method suggested by AOAC International. In this paper, details description of the role of Radiochemical and Environment Group, Nuclear Malaysia who is responsible in analyzing the radioactivity in the food samples due to Fukushima Daiichi, Japan accident was included. The radioactivity limit adopted and analysis results from this monitoring were discussed. (author)

  3. Monitoring of Radionuclide Contamination in Food Samples in Malaysia due to Daiichi Reactor Accident in Fukushima, Japan

    International Nuclear Information System (INIS)

    Nurrul Assyikeen Mohd Jaffary; Abdul Kadir Ishak; Wo, Y.M.

    2011-01-01

    On March 11, 2011, a serious accident occurred in Daiichi nuclear reactor plant, Fukushima, Japan which caused radioactive materials been released into the atmosphere in the form of aerosols and dust particles. Sea water around the plant was also found contaminated with high radioactivity readings. These radioactive materials could be transported by the winds and ocean current across international borders and cannot be controlled by human. Besides a continuous monitoring activity of radionuclide content in the air and sea water that need to be conducted by the authorities, Malaysia should also control the entry of radionuclide through contaminated food ingestion by human. Radionuclide I-131, Cs-134 and Cs-137 were used as a counter-measure of pollution levels and counted with gamma spectrometry using standard analysis method suggested by AOAC International. In this paper, details description of the role of Radiochemical and Environment Group, Nuclear Malaysia who's responsible in analyzing the radioactivity in the food samples due to Fukushima Daiichi, Japan accident was included. Also discussed are the radioactivity limit adopted and analysis results from this monitoring. (author)

  4. Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors - Volume I.

    Energy Technology Data Exchange (ETDEWEB)

    Gauntt, Randall O. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mattie, Patrick D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    Sandia National Laboratories (SNL) has conducted an uncertainty analysis (UA) on the Fukushima Daiichi unit (1F1) accident progression with the MELCOR code. The model used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). That study focused on reconstructing the accident progressions, as postulated by the limited plant data. This work was focused evaluation of uncertainty in core damage progression behavior and its effect on key figures-of-merit (e.g., hydrogen production, reactor damage state, fraction of intact fuel, vessel lower head failure). The primary intent of this study was to characterize the range of predicted damage states in the 1F1 reactor considering state of knowledge uncertainties associated with MELCOR modeling of core damage progression and to generate information that may be useful in informing the decommissioning activities that will be employed to defuel the damaged reactors at the Fukushima Daiichi Nuclear Power Plant. Additionally, core damage progression variability inherent in MELCOR modeling numerics is investigated.

  5. Review of health issues of workers engaged in operations related to the accident at the Fukushima Daiichi Nuclear Power Plant.

    Science.gov (United States)

    Hiraoka, Koh; Tateishi, Seiichiro; Mori, Koji

    2015-01-01

    The aim of this review was to summarize the lessons learned from the experience in protecting the health of workers engaged in operations following the accident at the Fukushima Daiichi Nuclear Power Plant (NPP). We reviewed all types of scientific papers examining workers' health found in Medline and Web of Sciences as well as some official reports published by the Ministry of Health, Labour and Welfare of Japan and other governmental institutes. The papers and reports were classified into those investigating workers at the Fukushima Daiichi and Daini NPPs, workers engaged in decontamination operations in designated areas, and other workers. Regarding workers at the NPPs, many efforts were made to establish an emergency-care and occupational health system. Risk management efforts were undertaken for radiation exposure, heat stress, psychological stress, outbreak of infectious diseases, and fitness for work. Only a few reports dealt with decontamination workers and others; however, the health management of these workers was clearly weaker than that for workers at the NPPs. Many lessons can be learned from what occurred. That knowledge can be applied to ongoing decommissioning work and to future disasters. In addition, it is necessary to study the long-term health effects of radiation exposure and to accumulate data about the health of workers engaged in decontamination work and other areas.

  6. AESJ 5 years activities and issues to be solved for the TEPCO's Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Uetsuka, Hiroshi; Yamamoto, Akio; Saso, Michitaka

    2016-01-01

    This paper summarizes the measures taken by the Atomic Energy Society of Japan (AESJ) against the Fukushima Daiichi Accident, and its challenges to the task to be addressed in the future. As recommendations by AESJ, the following five items were pointed out in its final report on the survey on the accident: (1) basic matters on nuclear safety, (2) matters on direct causes of accident, (3) organizational matters among background factors, (4) collective matters, and (5) future matters related to environmental remediation. As the commitment to the Fukushima reconstruction, AESJ performed the introduction of decontamination technologies, hosting of interactive forum and symposium session in Fukushima Prefecture, decontamination test of paddy fields, and preparation of an air dose rate map in Fukushima Prefecture. As for the decommissioning of the Fukushima Daiichi Nuclear Power Station, AESJ prepared guidelines by applying probabilistic risk assessment (PRA) to tsunami, and revised seismic PRA standards. Since there was a lack in the implementation of multiple protections as one of the background causes of the Fukushima Accident, it summarized 'concept of the implementation of multiple protections.' In addition, it surveyed and examined the accident from the viewpoint of human factors, discussed the importance of accident investigation from the viewpoint of a party in charge, and issued a report. (A.O.)

  7. Reconstruction of 137Cs activity in the ocean following the Fukushima Daiichi Nuclear Power Plant Accident

    Science.gov (United States)

    Tsumune, Daisuke; Aoyama, Michio; Tsubono, Takaki; Tateda, Yutaka; Misumi, Kazuhiro; Hayami, Hiroshi; Toyoda, Yasuhiro; Maeda, Yoshiaki; Yoshida, Yoshikatsu; Uematsu, Mitsuo

    2014-05-01

    A series of accidents at the Fukushima Dai-ichi Nuclear Power Plant following the earthquake and tsunami of 11 March 2011 resulted in the release of radioactive materials to the ocean by two major pathways, direct release from the accident site and atmospheric deposition. We reconstructed spatiotemporal variability of 137Cs activity in the ocean by the comparison model simulations and observed data. We employed a regional scale and the North Pacific scale oceanic dispersion models, an atmospheric transport model, a sediment transport model, a dynamic biological compartment model for marine biota and river runoff model to investigate the oceanic contamination. Direct releases of 137Cs were estimated for more than 2 years after the accident by comparing simulated results and observed activities very close to the site. The estimated total amounts of directly released 137Cs was 3.6±0.7 PBq. Directly release rate of 137Cs decreased exponentially with time by the end of December 2012 and then, was almost constant. The daily release rate of 137Cs was estimated to be 3.0 x 1010 Bq day-1 by the end of September 2013. The activity of directly released 137Cs was detectable only in the coastal zone after December 2012. Simulated 137Cs activities attributable to direct release were in good agreement with observed activities, a result that implies the estimated direct release rate was reasonable, while simulated 137Cs activities attributable to atmospheric deposition were low compared to measured activities. The rate of atmospheric deposition onto the ocean was underestimated because of a lack of measurements of dose rate and air activity of 137Cs over the ocean when atmospheric deposition rates were being estimated. Observed 137Cs activities attributable to atmospheric deposition in the ocean helped to improve the accuracy of simulated atmospheric deposition rates. Although there is no observed data of 137Cs activity in the ocean from 11 to 21 March 2011, observed data of

  8. Characterization study of cesium concentrated particles in the soils near the Fukushima Daiichi nuclear power plant

    Science.gov (United States)

    Satou, Yukihiko; Sueki, Keisuke; Sasa, Kimikazu; Adachi, Kouji; Igarashi, Yasuhito

    2015-04-01

    Radionuclides from the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident contaminated a vast area. Two types of contamination, spread and spot types, were observed in soils with autoradiography using an imaging plate. Other samples such as dust filters, vegetation, X-ray films, and so on, also indicate the spot type contamination in the early stage of the FDNPP accident. The source of spot type contamination is well known as hot particles at the Chernobyl Nuclear Power Plant (ChNPP) accident in 1986. Hot particles were divided into two groups, fuel hot particles and fission product particles, and they were emitted directly from reactor core with phreatic explosion and fire. In contrast, the official reports of the FDNPP accident did not conforme core explosion. In addition, the emitted total amount of Uranium was very few (Yamamoto et al., 2014). Thus, the spot type contaminations were not identified as the same of hot particles yet. Therefore, the present study aimed to pick up and identify the spot contaminations in soils. Surface soil samples were collected at 20 km northwest from the FDNPP in June 2013. Soils were spread in plastic bags for autoradiography with imaging plate analysis. Then, the soil particles were collected on a sticky carbon tape and analyzed by SEM-EDS to detect radioactive particles. Finally, particles were confirmed to contain photo peaks in the γ-spectrum by a germanium semiconductor detector. Four radioactive particles were isolated from the soil samples in the present study. Detected γ-ray emission radionuclides were only Cs-134 and Cs-137. The X-ray spectra on the SEM-EDS of all particles showed a Cs peak as well as O, Fe, Zn, and Rb peaks, and these elements were distributed uniformly within the particles. In addition, uniform distribution of Si was also shown. Moreover, U was detected from one of the particles, but U concentration was very low and existed locally in the particle. These characters are very similar to previous

  9. Radioactive Cs in the estuary sediments near Fukushima Daiichi Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Yamasaki, Shinya, E-mail: s-yamasaki@ied.tsukuba.ac.jp [Faculty of Pure and Applied Sciences and Center for Research in Isotopes and Environmental Dynamics, University of Tsukuba, 1-1-1 Tennodai, Tsukuba, Ibaraki 305-8577 (Japan); Imoto, Junpei; Furuki, Genki; Ochiai, Asumi [Department of Chemistry, Kyushu University, 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581 (Japan); Ohnuki, Toshihiko [Advanced Science Research Center, Japan Atomic Energy Agency, Shirakata Shirane 2-4, Tokai, Ibaraki 319-1195 (Japan); Sueki, Keisuke [Faculty of Pure and Applied Sciences and Center for Research in Isotopes and Environmental Dynamics, University of Tsukuba, 1-1-1 Tennodai, Tsukuba, Ibaraki 305-8577 (Japan); Nanba, Kenji [Department of Environmental Management, Faculty of Symbiotic System Science, Fukushima University, Kanayagawa 1, Fukushima, 960-1296 (Japan); Ewing, Rodney C. [Department of Geological Sciences and Center for International Security and Cooperation, Stanford University, Stanford, CA 94305-2115 (United States); Utsunomiya, Satoshi [Department of Chemistry, Kyushu University, 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581 (Japan)

    2016-05-01

    The migration and dispersion of radioactive Cs (mainly {sup 134}Cs and {sup 137}Cs) are of critical concern in the area surrounding the Fukushima Daiichi Nuclear Power Plant (FDNPP). Considerable uncertainty remains in understanding the properties and dynamics of radioactive Cs transport by surface water, particularly during rainfall-induced flood events to the ocean. Physical and chemical properties of unique estuary sediments, collected from the Kuma River, 4.0 km south of the FDNPP, were quantified in this study. These were deposited after storm events and now occur as dried platy sediments on beach sand. The platy sediments exhibit median particle sizes ranging from 28 to 32 μm. There is increasing radioactivity towards the bottom of the layers deposited; approximately 28 and 38 Bq g{sup −1} in the upper and lower layers, respectively. The difference in the radioactivity is attributed to a larger number of particles associated with radioactive Cs in the lower part of the section, suggesting that radioactive Cs in the suspended soils transported by surface water has decreased over time. Sequential chemical extractions showed that ~ 90% of {sup 137}Cs was strongly bound to the residual fraction in the estuary samples, whereas 60 ~ 80% of {sup 137}Cs was bound to clays in the six paddy soils. This high concentration in the residual fraction facilitates ease of transport of clay and silt size particles through the river system. Estuary sediments consist of particles < 100 μm. Radioactive Cs desorption experiments using the estuary samples in artificial seawater revealed that 3.4 ± 0.6% of {sup 137}Cs was desorbed within 8 h. More than 96% of {sup 137}Cs remained strongly bound to clays. Hence, particle size is a key factor that determines the travel time and distance during the dispersion of {sup 137}Cs in the ocean. - Highlights: • Cs-137 of estuary sediment impacted by the FDNPP was measured. • Physical and chemical properties were measured also.

  10. Radioactive Cs in the estuary sediments near Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Yamasaki, Shinya; Imoto, Junpei; Furuki, Genki; Ochiai, Asumi; Ohnuki, Toshihiko; Sueki, Keisuke; Nanba, Kenji; Ewing, Rodney C.; Utsunomiya, Satoshi

    2016-01-01

    The migration and dispersion of radioactive Cs (mainly "1"3"4Cs and "1"3"7Cs) are of critical concern in the area surrounding the Fukushima Daiichi Nuclear Power Plant (FDNPP). Considerable uncertainty remains in understanding the properties and dynamics of radioactive Cs transport by surface water, particularly during rainfall-induced flood events to the ocean. Physical and chemical properties of unique estuary sediments, collected from the Kuma River, 4.0 km south of the FDNPP, were quantified in this study. These were deposited after storm events and now occur as dried platy sediments on beach sand. The platy sediments exhibit median particle sizes ranging from 28 to 32 μm. There is increasing radioactivity towards the bottom of the layers deposited; approximately 28 and 38 Bq g"−"1 in the upper and lower layers, respectively. The difference in the radioactivity is attributed to a larger number of particles associated with radioactive Cs in the lower part of the section, suggesting that radioactive Cs in the suspended soils transported by surface water has decreased over time. Sequential chemical extractions showed that ~ 90% of "1"3"7Cs was strongly bound to the residual fraction in the estuary samples, whereas 60 ~ 80% of "1"3"7Cs was bound to clays in the six paddy soils. This high concentration in the residual fraction facilitates ease of transport of clay and silt size particles through the river system. Estuary sediments consist of particles < 100 μm. Radioactive Cs desorption experiments using the estuary samples in artificial seawater revealed that 3.4 ± 0.6% of "1"3"7Cs was desorbed within 8 h. More than 96% of "1"3"7Cs remained strongly bound to clays. Hence, particle size is a key factor that determines the travel time and distance during the dispersion of "1"3"7Cs in the ocean. - Highlights: • Cs-137 of estuary sediment impacted by the FDNPP was measured. • Physical and chemical properties were measured also. • Increasing radioactivity was

  11. Radioactive Cs in the Severely Contaminated Soils Near the Fukushima Daiichi Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kaneko, Makoto; Iwata, Hajime; Shiotsu, Hiroyuki; Masaki, Shota; Kawamoto, Yuji; Yamasaki, Shinya; Nakamatsu, Yuki; Imoto, Junpei; Furuki, Genki; Ochiai, Asumi [Department of Chemistry, Kyushu University, Fukuoka (Japan); Nanba, Kenji [Department of Environmental Management, Faculty of Symbiotic System Science, Fukushima University, Fukushima (Japan); Ohnuki, Toshihiko [Advanced Science Research Center Japan Atomic Energy Agency, Tokai (Japan); Ewing, Rodney C. [Department of Geological Sciences, Center for International Security and Cooperation, Stanford University, Stanford, CA (United States); Utsunomiya, Satoshi, E-mail: utsunomiya.satoshi.998@m.kyushu-u.ac.jp [Department of Chemistry, Kyushu University, Fukuoka (Japan)

    2015-09-01

    Radioactive Cs isotopes ({sup 137}Cs, t{sub 1/2} = 30.07 years and {sup 134}Cs, t{sub 1/2} = 2.062 years) occur in severely contaminated soils within a few kilometer of the Fukushima Daiichi nuclear power plant at concentrations that range from 4 × 10{sup 5} to 5 × 10{sup 7} Bq/kg. In order to understand the mobility of Cs in these soils, both bulk and submicron-sized particles elutriated from four surface soils have been investigated using a variety of analytical techniques, including powder X-ray diffraction analysis, scanning electron microscopy (SEM), transmission electron microscopy (TEM), and analysis of the amount of radioactivity in sequential chemical extractions. Major minerals in bulk soil samples were quartz, feldspar, and minor clays. The submicron-sized particles elutriated from the same soil consist mainly of mica, vermiculite, and smectite and occasional gibbsite. Autoradiography in conjunction with SEM analysis confirmed the association of radioactive Cs mainly with the submicron-sized particles. Up to ~3 MBq/kg of {sup 137}Cs are associated with the colloidal size fraction (<1 μm), which accounts for ~78% of the total radioactivity. Sequential extraction of the bulk sample revealed that most Cs was retained in the residual fraction, confirming the high binding affinity of Cs to clays, aluminosilicate sheet structures. The chemistry of the fraction containing submicron-sized particles from the same bulk sample showed a similar distribution to that of the bulk sample, again confirming that the Cs is predominantly adsorbed onto submicron-sized sheet aluminosilicates, even in the bulk soil samples. Despite the very small particle size, aggregation of the particles prevents migration in the vertical direction, resulting in the retention of >98% of Cs within top ~5 cm of the soil. These results suggest that the mobility of the aggregates of submicron-sized sheet aluminosilicate in the surface environment is a key factor controlling the current Cs

  12. Uncertainty analysis of atmospheric deposition simulation of radiocesium and radioiodine from Fukushima Daiichi Nuclear Power Plant

    Science.gov (United States)

    Morino, Yu; Ohara, Toshimasa; Yumimoto, Keiya

    2014-05-01

    Chemical transport models (CTM) played key roles in understanding the atmospheric behaviors and deposition patterns of radioactive materials emitted from the Fukushima Daiichi nuclear power plant (FDNPP) after the nuclear accident that accompanied the great Tohoku earthquake and tsunami on 11 March 2011. In this study, we assessed uncertainties of atmospheric simulation by comparing observed and simulated deposition of radiocesium (137Cs) and radioiodine (131I). Airborne monitoring survey data were used to assess the model performance of 137Cs deposition patterns. We found that simulation using emissions estimated with a regional-scale (~500 km) CTM better reproduced the observed 137Cs deposition pattern in eastern Japan than simulation using emissions estimated with local-scale (~50 km) or global-scale CTM. In addition, we estimated the emission amount of 137Cs from FDNPP by combining a CTM, a priori source term, and observed deposition data. This is the first use of airborne survey data of 137Cs deposition (more than 16,000 data points) as the observational constraints in inverse modeling. The model simulation driven by a posteriori source term achieved better agreements with 137Cs depositions measured by aircraft survey and at in-situ stations over eastern Japan. Wet deposition module was also evaluated. Simulation using a process-based wet deposition module reproduced the observations well, whereas simulation using scavenging coefficients showed large uncertainties associated with empirical parameters. The best-available simulation reproduced the observed 137Cs deposition rates in high-deposition areas (≥10 kBq m-2) within one order of magnitude. Recently, 131I deposition map was released and helped to evaluate model performance of 131I deposition patterns. Observed 131I/137Cs deposition ratio is higher in areas southwest of FDNPP than northwest of FDNPP, and this behavior was roughly reproduced by a CTM if we assume that released 131I is more in gas phase

  13. Time changes in radiocesium concentration in aquatic systems affected by the Fukushima Daiichi NPP accident

    Science.gov (United States)

    Onda, Yuichi; Taniguchi, Keisuke; Kato, Hiroaki; Yoshimura, Kazuya; Wakiyama, Yoshifumi; Iwagami, Sho; Tsujimura, Maki; Sakaguchi, Aya; Yamamoto, Masatoshi

    2015-04-01

    Due to Fukushima Daiichi Nuclear Power Plant accident, radioactive materials including Cs-134 and Cs-137 were widely distributed in surrounded area. The radiocesiums have been transported in river networks. The monitoring started at 6 sites from June 2011. Subsequently, additional 24 monitoring sites were installed between October 2012 and January 2013. Flow and turbidity (for calculation of suspended sediment concentration) were measured at each site, while suspended sediments and river water were collected every one or half month to measure Cs-134 and Cs-137 activity concentrations by gamma spectrometry. Also detailed field monitoring has been condcuted in Yamakiya-district, Kawamata town, Fukushima prefecture. These monitoring includes, 1) Radiocesium wash-off from the runoff-erosion plot under different land use, 2) 2. Measurement of radiocesium transfer in forest environment, in association with hydrological pathways such as throughfall and overlandflow on hillslope, 3) Monitoring on radiocesium concentration in soil water, ground water, and spring water, 4)Monitoring of dissolved and particulate radiocesium concentration in river water, and stream water from the forested catchment, and 5)Measurement of radiocesium content in drain water and suspended sediment from paddy field. Our monitoring result demonstrated that the Cs-137 concentration in eroded sediment from the runoff-erosion plot has been almost constant for the past 3 years, however the Cs-137 concentration of suspended sediment from the forested catchment showed slight decrease through time. On the other hand, the suspended sediment from paddy field and those in river water from large catchments exhibited rapid decrease in Cs-137 concentration with time. The decreasing trend of Cs-137 concentration were fitted by the two-component exponential model, differences in decreasing rate of the model were compared and discussed among various land uses and catchment scales. Such analysis can provide

  14. Whole-body counting of Fukushima residents after the TEPCO Fukushima Daiichi Nuclear Power Station accident

    Energy Technology Data Exchange (ETDEWEB)

    Momose, Takumaro; Takada, Chie; Nakagawa, Takahiro; Nakai, Katsuta; Kurihara, Osamu; Tsujimura, Norio; Furuta, Sadaaki [Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, Tokai, Ibaraki (Japan); Ohi, Yoshihiro; Murayama, Takashi; Suzuki, Takashi [Japan Atomic Energy Agency, Nuclear Science Research Institute, Tokai, Ibaraki (Japan); Uezu, Yasuhiro [Japan Atomic Energy Agency, Fukushima Environmental Safety Center, Fukushima, Fukushima (Japan)

    2012-11-15

    At the request of the Fukushima government, the Japan Atomic Energy Agency (JAEA) started whole-body counting of residents on July 11, 2011, to assess radiation exposure after the TEPCO Fukushima Daiichi Nuclear Power Station accident. JAEA has examined residents in Iitate, Kawamata, Namie, and eight other local communities. The measurement capacity of the whole-body counting device is approximately 100 persons per day, and the total number of people to measure reached 9,927 by the end of January 2012. Two types of whole-body counter (WBC), each of which has two large-sized NaI(Tl) detectors, were used to perform the measurements. Physical phantoms (a Canberra RMC-II transfer phantom or a water-filled block phantom developed by JAEA) were used to perform the efficiency calibration of the WBCs, and results of this calibration were verified by comparing them with different-sized BOttle Mannequin ABsorber (BOMAB) phantoms imitating an adult male, a 10-year-old child, and a 4-year-old child. Short half-life radionuclides (e.g., {sup 131}I) originating from the accident were not detected in the present work, because the measurements were made starting four months after the accident. These measurements showed that about 80% of the residents were below a minimum detectable amount (MDA) of the measured radionuclides in the whole-body content. No artificial nuclides other than {sup 134}Cs and {sup 137}Cs were detected in the present whole-body counting. The maximum whole-body content of radiocesium ({sup 134}Cs and {sup 137}Cs in total) was 2.7 kBq for children (< 8 years old) and 14 kBq for adults. The radioactivity ratio ({sup 137}Cs/{sup 134}Cs) was estimated to be from 1.12 to 1.26. An acute intake scenario via inhalation of radiocesium was assumed in the present dose estimation for all the residents who were measured by the end of January 2012. The committed effective dose (CED) to 99.8% of the residents was found to be below 1 mSv. There were only 25 subjects with a

  15. Recent condition of Fukushima-Daiichi nuclear plant accident in Japan

    Science.gov (United States)

    Ohnishi, Takeo

    2012-07-01

    Japanese government pronounced that the second step had been succeeded in the cooling down of the reactors on the middle of Dec 2011 at Fukushima-Daiichi nuclear power plant. In future, government aims to take out fuels from 4 reactors and shields their units. The nuclear power plants in Japan are gradually decreasing, because the checking for them has been performed and the permission of the re-start of them are difficult to be gained. On January 1st 2012, only 7 units are operating in Japan, though the about 54 units were set before the accident. At the end of December 2011, most radiations are emitted from cesium. The radioactivity in air and land around the plant was daily reported in newspaper. Government often gave the information about some RI-contamination in foods. They were taken off from the markets. At now stage, the most important project is the decontamination of radioactive materials from houses, schools, public facilities and industries. Government will newly classify three evacuation areas from April 2012. At the end of March, evacuees under 20 mSv/year possibly can go back their homes (evacuation-free area). The environmental doses will be depressed by decontamination under 10 mSv/year. At the range of 20-50 mSv, people will be controlled to live these area, they can go back their houses temporally (evacuation area). Over 50 mSv/year, however, people can go back house until 5 years at least (prohibited area). In new radiation limitation for a risk of human health, government made 100 mSv and 20 mSv for life span for one year, respectively. The aim of decontamination was set up to 10 mSv for 1 year and 5 mSv for next stage. A target at school is under1 mSv for children. Government accepted a new severe limitation per1 Kg at four groups; milk of baby (100 Bq) and milk (100 Bq), drinking water (10 Bq) and food (100 Bq). Tokyo electric Power Company and government should pay the sufficient compensation to evacuees. In future, they should keep health

  16. New Standards in Liquid Waste Treatment at Fukushima Dai-ichi - 13134

    Energy Technology Data Exchange (ETDEWEB)

    Sylvester, Paul; Milner, Tim; Ruffing, Jennifer; Poole, Scott [EnergySolutions, 100 Center Point Circle, Suite 100, Center Point II, Columbia, SC 29210 (United States); Townson, Paul; Jensen, Jesse [EnergySolutions, 2345 Stevens Drive, Suite 240, Richland, WA 99354 (United States)

    2013-07-01

    The earthquake and tsunami on March 11, 2011 severely damaged the Fukushima Dai-ichi nuclear plant leading to the most severe nuclear incident since Chernobyl. Ongoing operations to cool the damaged reactors at the site have led to the generation of highly radioactive coolant water. This is currently mainly treated to remove Cs-137 and Cs-134 and passed through a reverse osmosis (RO) unit to reduce the salinity before being cycled back to the reactors. Because only the Cs isotopes are removed, the RO reject water still contains many radioactive isotopes and this has led to the accumulation of over 200,000 cubic meters (52 million gallons) of extremely contaminated water which is currently stored on site in tanks. EnergySolutions, in partnership with Toshiba, were contracted to develop a system to reduce 62 isotopes in this waste down to allowable levels. This was a significant technical challenge given the high background salt content of the wastewater, the variation in aqueous chemistry of the radioactive isotopes and the presence of non-active competing ions (e.g. Ca and Mg) which inhibit the removal of isotopes such as Sr-89 and Sr-90. Extensive testing was performed to design a suitable system that could meet the required decontamination goals. These tests were performed over a 6 month period at facilities available in the nearby Fukushima Dai-ni laboratory using actual waste samples. This data was then utilized to design a Multi Radioactive Nuclides Removal System (MRRS) for Fukushima which is a modified version of EnergySolutions' proprietary Advanced Liquid Processing System (ALPS)'. The stored tank waste is fed into a preliminary precipitation system where iron flocculation is performed to remove a number of isotopes, including Sb-125, Ru-106, Mn-54 and Co-60. The supernatant is then fed into a second precipitation tank where the pH is adjusted and the bulk of the Mg, Ca and Sr precipitated out as carbonates and hydroxides. After passing through a

  17. Simulation analysis on accident at Fukushima Daiichi Nuclear Power Plant Unit 2 by SAMPSON code

    International Nuclear Information System (INIS)

    Takahashi, Atsuo; Pellegrini, Marco; Mizouchi, Hideo; Suzuki, Hiroaki; Naitoh, Masanori

    2015-01-01

    The accident occurred at the Fukushima Daiichi Nuclear Power Plant Unit 2 has been investigated by the severe accident analysis code, SAMPSON with more realistic boundary conditions and newly introduced models. In Unit 2, the Reactor Core Isolation Cooling system (RCIC) is thought to have worked for unexpectedly long time (about 70 hours) without batteries. It is thought to be due to balance between injected water from the RCIC pump and supplied mixture of steam and water to the RCIC turbine. To confirm the RCIC working condition and reproduce the measured plant properties, such as pressure and water level in the reactor pressure vessel (RPV), we introduced two-phase turbine driven pump model into SAMPSON. In the model, mass flow rate of water injected by RCIC was calculated through mass flow rate of steam included in extracted two-phase flow, steam generated from flashing of water included in extracted two-phase flow, and turbine efficiency degradation originated by the mixture of steam and water flowing to the RCIC turbine. To reproduce the dry well (DW) pressure, we assumed that torus room was flooded by the tsunami and heat was removed from the suppression chamber to the sea water. Simulation results by SAMPSON basically agree with the measured values such as pressure in the RPV and in the DW until several days after the scram. However, some contradictions between the simulation results and the measured values, such as that inversion of the RPV pressure at 10 hours after scram in the measurement happened at 14 hours in the simulation and that the DW pressure showed different behavior between simulation and measurement when SRV started periodic operation at 71 hours, are still remain and are under consideration. In the current calculation, model for falling core to the lower plenum was modified so that debris is not retained at the core plate based on observation of the XR2-1 experiment. Additionally, model of the RPV failure by melting of the penetrating pipe

  18. Tracking Radioactive Fallout from the Fukushima Dai-ichi Accident in Arctic Snow

    Science.gov (United States)

    Osterberg, E. C.; Thompson, J.; Landis, J.; Albert, M. R.; Campbell, S. W.; Hawley, R. L.; Virginia, R. A.

    2011-12-01

    The March 11, 2011 magnitude 9.0 Tohoku, Japan earthquake produced a tsunami that inundated the Fukushima Dai-ichi nuclear power plant and led to the accidental release of radioactive 131I, 132Te, 134Cs, and 137Cs to the atmosphere. The Japanese Nuclear Safety Commission estimates that 12,000 TBq of 137Cs were released to the atmosphere during the incident, which represents ~14% of the total estimated 137Cs emission from the Chernobyl disaster in April 1986. Measurements of airborne radiation collected at the Fukushima plant illustrate that >50% of the total emitted radiation was released on March 15 and 16 associated with explosions and fires at reactor units 1, 2, and 4, and 70% was emitted in the first 5 days of the event. The source of the radiation is thus well constrained in time and space, providing an opportunity to better understand long-range atmospheric transport processes from Asia to the Arctic, while also assessing the magnitude of the fallout in the Arctic. Here we describe the 137Cs and 134Cs fallout flux near Thule, Greenland (1700 m a.s.l.), at Summit (3200 m a.s.l.), Greenland, and within Denali National Park, Alaska (2400-3900 m a.s.l.) based on series of large-volume (5-15 l) snow pit samples collected in June and July, 2011. In addition to assessing the spatial variability of Fukushima fallout in the Arctic, the elevation range of samples allows for an analysis of any vertical heterogeneity in fallout transport and deposition. Major ion concentrations and stable water isotope ratios are used to confirm the seasonal timing of the Fukushima fallout horizon in the snowpack. Radiocesium was concentrated and isolated from the snow pit meltwater using the well-established ammonium phosphomolybdate (AMP) adsorption method, and 134Cs and 137Cs concentrations were measured using gamma spectrometry with a Canberra 3523 well-type intrinsic Ge-detector at the Dartmouth College Short-Lived Isotope Laboratory. NOAA HYPLIT atmospheric forward

  19. Study on public awareness of utilizing nuclear power in China. Changes in public awareness after the accident of Fukushima Daiichi Nuclear Power Plants

    International Nuclear Information System (INIS)

    Xu, Ting; Wakabayashi, Toshio

    2012-01-01

    The purpose of this study is to clarify public awareness of utilizing nuclear power in China and to determine the effects of the accident of Fukushima Daiichi nuclear power plants. Web online surveys were carried out before and after the accident of Fukushima Daiichi nuclear power plants. The online survey before the accident of Fukushima Daiichi nuclear power plants had 4,255 adult respondents consisting of 1,851 males and 2,404 females. The online survey after the accident had 721 respondents consisting of 406 males and 315 females. The two online surveys about the attitude toward nuclear power plants consisted of 37 items, such as the necessity of nuclear power plants, the reliability of safety, and government confidence. As a result, respondents of the online surveys in China consider that nuclear energy is more important than the anxiety of accident. On the other hand, women have sensation of fear for the accident of Fukushima Daiichi nuclear power plants and radiation. (author)

  20. MDEP AP1000WG Design-Specific Common Position CP-AP1000WG-02. Common position addressing Fukushima Daiichi NPP accident-related issues

    International Nuclear Information System (INIS)

    2016-09-01

    A severe accident involving several units took place in Japan at Fukushima Daiichi nuclear power plant (NPP) in March 2011. The immediate cause of the accident was an earthquake followed by a tsunami coupled with inadequate provisions against the consequences of such events in the design. Opportunities to improve protection against a realistic design basis tsunami had not been taken. As a consequence of the tsunami, safety equipment and the related safety functions were lost at the plant, leading to core damage in three units and subsequently to large radioactive release. Several studies have already been performed to better understand the accident progression and detailed technical studies are still in progress in Japan and elsewhere. In the meantime, on-going studies on the behaviour of nuclear power plants in very severe situations, similar to Fukushima Daiichi, seek to identify potential vulnerabilities in plant design and operation; to suggest reasonably practicable upgrades; or to recommend enhanced regulatory requirements and guidance to address such situations. Likewise, agencies around the world that are responsible for regulating the design, construction and operation of AP1000 R plants are engaged in similar activities. The MDEP AP1000 R Working Group (AP1000 WG) members consist of members from Canada, China, the United Kingdom and the United States. Since the regulatory review of their AP1000 R applications have not been completed by all of these Countries yet, this paper identifies common preliminary approaches to address potential safety improvements for AP1000 R plants as related to lessons learned from the Fukushima Daiichi accident or Fukushima Daiichi-related issues. In seeking common position, regulators will provide input to this paper to reflect their safety conclusions regarding the AP1000 R design and how the design could be enhanced to address Fukushima Daiichi issues. The common preliminary approaches are organized into five sections

  1. The cross-section of returns, benchmark model parameters, and idiosyncratic volatility of nuclear energy firms after Fukushima Daiichi

    International Nuclear Information System (INIS)

    Lopatta, Kerstin; Kaspereit, Thomas

    2014-01-01

    This study analyzes how the stock market returns, the factor loadings from the Carhart (1997) 4-factor model, and the idiosyncratic volatility of shares in energy firms have been affected by the Fukushima nuclear accident. Unlike existing studies, which provide evidence of a wealth transfer from nuclear to renewable energy firms for specific countries, we use an international sample and investigate whether changes in the regulatory environment and the firm-specific commitment to nuclear and renewable energies correlate with the capital market's reactions to the Fukushima Daiichi accident. Our findings suggest that the more a firm relies on nuclear power, the more its share price declined after the accident. A commitment to renewable energies does not prevent declines in share prices but significantly helps to reduce the increase in market beta that is associated with this event. Nuclear energy firms domiciled in countries with a higher number of regulatory interventions that were triggered by the catastrophe have lower abnormal returns than those that are domiciled elsewhere. However, as a cross-sectional analysis reveals, a stronger commitment to nuclear power is the main driver for negative stock market returns. Furthermore, nuclear energy firms domiciled in countries with stronger regulatory shifts away from nuclear energy experience significant increases in market beta and the book-to-market equity factor loading according to the Carhart (1997) 4-factor model. We conclude that capital market participants are able to differentiate between the affectedness of firms with respect to their product portfolio. Energy firms could prevent increases in market beta due to catastrophes such as the Fukushima Daiichi accident by shifting some of their energy production from nuclear to renewable or other sources. - Highlights: • Abnormal stock returns of nuclear energy firms around Fukushima Daiichi depend on the mix of their energy portfolio. • Higher commitment to

  2. 'Radiation-induced electrolysis'. A potential root cause of hydrogen explosions in the Fukushima Daiichi accident

    International Nuclear Information System (INIS)

    Saji, Genn

    2014-01-01

    Although water radiolysis, decomposition of water by radiation, is a well-known phenomenon the exact mechanism is not well characterized especially for potential hydrogen generation during severe accidents. The author first reviewed the water radiolysis phenomena in LWRs during normal operation to severe accidents (e.g., TMI- and Chernobyl accidents) and performed a scoping estimation of H_2 generation modeled for the Fukushima Daiichi accident. The estimation incorporates the decay heat curve combined with G-values. When a set of radiological chain reactions are incorporated the resultant reverse reactions were found to reduce the hydrogen generation substantially. In view of the observation that the water radiolysis is not likely induced appreciable effects in H_2 generation during the accident, this author investigated his basic theory named 'radiation-induced electrolysis' in the estimation of amounts of H_2 generation during the active phase of the Fukushima accident. The author's theory was originally developed by including Faraday's Law of Electrolysis into the basic time-dependent material balance equation of radiation-chemical species for his study on accelerated corrosion phenomena which is widely observed in aged plants. With this mechanism as much as 5,300 m"3-STP of accumulated hydrogen gas is estimated to be inside the PCV just prior to the hydrogen explosion which occurred a day after the reactor trip in Unit 1. For Units 2 and 3, the estimated volumes are 5,900 m"3-STP. Within just several hours after the initiation of SBO, as much as a few thousand cubic meters in STP of hydrogen gas is generated due to a high decay heat. With these large volumes of hydrogen gas the hydrogen explosion was a viable possibility upon the 'venting' operation. For the 1F4 Spent Fuel Pool where the entire core loading had been evacuated, SBO was found to have induced a rapid on-set of electrolysis when the pool water temperature reached as high as 50°C with a range of

  3. Overview of insoluble radioactive cesium particles emitted from the Fukushima Dai-ichi Nuclear Power Station

    Science.gov (United States)

    Satou, Yukihiko

    2017-04-01

    In the early stage of the Fukushima Dai-ichi Nuclear Power Station (F1NPS) accident, number of spot type contamination has been observed in computed autoradiography (Kashimura 2013, Shibata 2013, Satou 2014). It's means presence of radioactive particles, however, insoluble cesium particle was overlooked because cesium, which is dominant radioactive element in the accident, becomes ionized in the environment. Adachi et al. (2013) showed presence of cesium (Cs)-bearing particles within air dust sample collected at Tsukuba, 170 km south from the Fukushima site, in midnight of 14 to morning of 15 March 2011. These particles were micrometer order small particles and Cs was could be detectable as element using an energy dispersive X-ray spectroscopy (EDX). However, other radioactive elements such as Co-60, Ru-103 and uranium, which were dominant element of radioactive particles delivered from Chernobyl accident, could not detected. Abe et al. (2014) employed a synchrotron radiation (SR)-micro(μ)-X-ray analysis to the Cs-bearing particles, and they were concluded that (1) contained elements derived from nuclear fission processes and from nuclear reactor and fuel materials; (2) were amorphous; (3) were highly oxidized; and (4) consisted of glassy spherules formed from a molten mixture of nuclear fuel and reactor material. In addition, Satou et al. (2016) and Yamaguchi et al. (2016) disclosed that silicate is main component of Cs-bearing particles. Satou et al. (2015) discovered two types of radioactive particles from soil samples collected in the vicinity of the F1NPS. These particles were remained in the natural environment more than four years, silicate is main component in common of each group particles. Group A particles were very similar to Cs-bearing particles reported by Adachi et al. except particle shape. On the other hand, group B is big particles found in north area from the F1NPS, and the strongest particles contained 20 kBq of Cs-137 within a particle

  4. Environmental Remediation Activities in Japan Following the Fukushima Dai-ichi Reactor Incident - 12603

    Energy Technology Data Exchange (ETDEWEB)

    Lively, J.W.; Kelley, J.L.; Marcial, M.R. [AMEC Environment and Infrastructure (United States); Yashio, Shoko; Kuriu, Nobou; Kamijo, Hiroaki; Jotatsu, Kato [Obayashi Corporation (Japan)

    2012-07-01

    In March 2011, the Fukushima Dai-ichi reactor power plant was crippled by the Great Pacific earthquake and subsequent tsunami. Much of the focus in the news was on the reactor site itself as the utility company (TEPCO), the Japanese government, and experts from around the world worked to bring the damaged plants into a safe shutdown condition and stem the release of radioactivity to the environment. Most of the radioactivity released was carried out to sea with the prevailing winds. Still, as weather patterns changed and winds shifted, a significant plume of radioactive materials released from the plant deposited in the environment surrounding the plant, contaminating large land areas of the Fukushima Prefecture. The magnitude of the radiological impact to the surrounding environmental is so large that the Japanese government has had to reevaluate the meaning of 'acceptably clean'. In many respects, 'acceptably clean' cannot be a one-size-fits-all standard. The economics costs of such an approach would make impossible what is already an enormous and costly environmental response and remediation task. Thus, the Japanese government has embarked upon an approach that is both situation-specific and reasonably achievable. For example, the determination of acceptably clean for a nursery school or kindergarten play yard may be different from that for a parking lot. The acceptably clean level of residual radioactivity in the surface soil of a rice paddy is different from that in a forested area. The recognized exposure situation (scenario) thus plays a large role in the decision process. While sometimes complicated to grasp or implement, such an approach does prioritize national resources to address environment remediation based upon immediate and significant risks. In addition, the Japanese government is testing means and methods, including advanced or promising technologies, that could be proven to be effective in reducing the amount of radioactivity

  5. Accident at the Fukushima Dai-ichi Nuclear Power Stations of TEPCO —Outline & lessons learned—

    Science.gov (United States)

    TANAKA, Shun-ichi

    2012-01-01

    The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others. PMID:23138450

  6. Lessons Learned in Protection of the Public for the Accident at the Fukushima Daiichi Nuclear Power Plant.

    Science.gov (United States)

    Callen, Jessica; Homma, Toshimitsu

    2017-06-01

    What insights can the accident at the Fukushima Daiichi nuclear power plant provide in the reality of decision making on actions to protect the public during a severe reactor and spent fuel pool emergency? In order to answer this question, and with the goal of limiting the consequences of any future emergencies at a nuclear power plant due to severe conditions, this paper presents the main actions taken in response to the emergency in the form of a timeline. The focus of this paper is those insights concerning the progression of an accident due to severe conditions at a light water reactor nuclear power plant that must be understood in order to protect the public.

  7. A numerical study on oceanic dispersion and sedimentation of radioactive cesium-137 from Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Higashi, Hironori; Morino, Yu; Ohara, Toshimasa

    2014-01-01

    We discussed a numerical model for oceanic dispersion and sedimentation of radioactive cesium-137 (Cs-137) in shallow water regions to clarify migration behavior of Cs-137 from Fukushima Daiichi Nuclear Power Plant. Our model considered oceanic transport by three dimensional ocean current, adsorption with large particulate matter (LPM), sedimentation and resuspension. The simulation well reproduced the spatial characteristics of sea surface concentration and sediment surface concentration of Cs-137 off Miyagi, Fukushima, and Ibaraki Prefectures during May-December 2011. The simulated results indicated that the adsorption-sedimentation of Cs-137 significantly occurred during strong wind events because the large amount of LPM was transported to upward layer by resuspension and vertical mixing. (author)

  8. Impact on the marine environment of radioactive releases resulting from the Fukushima-Daiichi nuclear accident. April 4, 2011

    International Nuclear Information System (INIS)

    2011-01-01

    After having outlined that measurements taken over several days in the sea water in the vicinity of the power station have revealed severe contamination of the marine environment by various radionuclides released as a result of the accident at the Fukushima-Daiichi nuclear power station, this report describes the origins of the contamination of the marine environment (release of liquid effluents directly into the sea in the vicinity of the damaged reactors, atmospheric fallout onto the surface of the sea, conveyance of radioactive pollution by rainout of contaminated ground). Then, while proposing several maps, the authors analyse and comment the dispersion in the sea of radioactive pollutants by addressing the following issues: topography of the sea bed and sea currents off the Japanese coast, immediate or short term dispersion (a few days), mid-term dispersion (weeks and months), long term and large scale future of the radioactive pollutants. Finally, the report briefly discusses the impact of radioactive pollution on living species

  9. Development of remote decontamination technologies improving internal environment of reactor buildings at Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    Hotta, Koji; Hayashi, Hirotada; Sakai, Hitoshi

    2016-01-01

    The reactor buildings at the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Co., Inc., which was seriously damaged by the Great East Japan Earthquake of March 11, 2011, have been highly contaminated by radioactive materials. To safely and efficiently advance the processes related to the forthcoming decommissioning of the reactors, it is necessary to improve the hazardous environment inside the reactor buildings. During the more than four years that have elapsed since the Great East Japan Earthquake, Toshiba has been implementing various measures to reduce the ambient dose rates inside the reactor buildings through decontamination work and participation in a national project for the development of remote decontamination technologies for reactor buildings. A variety of vehicles and technologies to support decontamination work have been developed through these activities, and are significantly contributing to improvement of the environment inside the reactor buildings. (author)

  10. Spatiotemporal distribution of radioactive cesium released from Fukushima Daiichi Nuclear Power Station in the sediment of Tokyo Bay, Japan

    International Nuclear Information System (INIS)

    Nakagawa, Ryota; Ishida, Masanobu; Baba, Daisuke; Tanimoto, Satomi; Okamoto, Yuichi; Yamazaki, Hideo

    2013-01-01

    The spatial and temporal distribution of "1"3"4Cs and "1"3"7Cs released from Fukushima Daiichi Nuclear Power Station in the Tokyo Bay sediments were investigated. The total radioactivity of "1"3"4Cs and "1"3"7Cs detected in the Tokyo Bay sediment ranged from 240 to 870 Bq/kg-dry in the estuary of Arakawa River, but the activities detected in other sites were about 90 Bq/kg-dry or less. These results suggested that radioactive cesium, which precipitated to the ground, was carried to the river along with clay particles by rainfall and transported to the estuary. The vertical distribution of radioactive cesium showed that it invaded deeper than estimated based on the accumulation rate of the sediment. It was described that the vertical distribution of radioactive cesium was affected by physical mixing of sediments by tidal current, flood, and bioturbation of benthos. (author)

  11. 14C levels in the vicinity of the Fukushima Dai-ichi Nuclear Power Plant prior to the 2011 accident

    DEFF Research Database (Denmark)

    Xu, Sheng; Cook, Gordon T.; Cresswell, Alan J.

    2016-01-01

    A 50-year-old Japanese cedar (Cryptomeria japonica) from Okuma, ∼1 km southwest of the Fukushima Dai-ichi Nuclear Power Plant, was cored and each annual ring was analysed for 14C. The 14C specific activity values varied from 330.4 Bq kg−1 C in the tree ring formed in 1971 to 231.2 Bq kg−1 C...... discharges from the reactors during their normal operations. In addition, the specific activities are positively correlated with the annual electricity generation values. The excess 14C specific activities were effective dose of ... ingestion pathway in the study location. The primary wind direction is east-southeast/southeast with a frequency of ∼30%, in comparison to ∼20% frequency for the direction of the site under study (north-northeast/northeast). This would tend to indicate a similar magnitude of additional effective dose...

  12. Multi-Phased, Post-Accident Support of the Fukushima Dai-Ichi Nuclear Power Plant - 12246

    Energy Technology Data Exchange (ETDEWEB)

    Gay, Arnaud; Gillet, Philippe; Ytournel, Bertrand; Varet, Thierry; David, Laurent; Prevost, Thierry; Redonnet, Carol; Piot, Gregoire; Jouaville, Stephane; Pagis, Georges [AREVA NC (France)

    2012-07-01

    In the wake of the March 11 earthquake and tsunami and the subsequent flooding of several of the Fukushima Dai-Ichi reactors, Japan and the Japanese utility TEPCO faced a crisis situation with incredible challenges: substantial amounts of radioactive mixed seawater and freshwater accumulated in the basements of four reactor and other buildings on the site. This water held varying levels of contamination due to the fact that it had been in contact with damaged fuel elements in the cores and with other contaminated components. The overall water inventory was estimated at around 110,000 tons of water with contamination levels up to the order of 1 Ci/l. Time was of the essence to avoid overflow of this accumulated water into the ocean. AREVA proposed, designed and implemented a water treatment solution using a proven chemical coprecipitation process with ppFeNi reagent, which is currently in use for effluent treatment on several nuclear sites including AREVA sites. In addition to the extremely short schedule the other challenge was to adapt the chemical treatment process to the expected composition of the Fukushima water and, in particular, to evaluate the impact of salinity on process performance. It was also necessary to define operating conditions for the VEOLIA equipment that had been selected for implementation of the process in the future facility. The operation phase began on June 17, and by the end of July more than 30,000 tons of highly radioactive saltwater had been decontaminated - the Decontamination Factor (DF) for Cesium was ∼10{sup 4}. It allowed recycling the contaminated water to cool the reactors while protecting workers and the environment. This paper focuses on the Actiflo{sup TM}-Rad water treatment unit project that was part of the TEPCO general water treatment scheme. It presents a detailed look at the principles of the Actiflo{sup TM}-Rad, related on-the-fly R and D, an explanation of system implementation challenges, and a brief summary of

  13. Relationship between particle size and radiocesium in fluvial suspended sediment related to the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Kazuya Tanaka

    2014-01-01

    We collected fluvial suspended sediments in Fukushima after the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident and analyzed the 137 Cs concentration in bulk and size-fractioned samples to investigate the particle-size-dependent distribution of radiocesium. The 137 Cs concentration in bulk suspended sediments decreased from August to December 2011, possibly reflecting a decrease of radiocesium concentration in its source materials. Smaller particles had higher radiocesium concentrations, reflecting larger specific surface areas. Silt- and sand-size fractions occupied more than 95 % of the total 137 Cs in the suspended sediments. The contribution of clay-size fractions, which had the highest 137 Cs concentration, was quite small because of their low frequency. A line of the data showed that the particle size distribution of radiocesium was essential to evaluate the migration and distribution of radiocesium in river systems where radiocesium is mainly present as particulate form after the FDNPP accident. (author)

  14. Heat and fluid flow in accident of Fukushima Daiichi Nuclear Power Plant, Unit 2. Accident scenario based on thermodynamic model

    International Nuclear Information System (INIS)

    Maruyama, Shigenao

    2012-01-01

    An accident scenario of Fukushima Daiichi Nuclear Power Plant, Unit 2 is analyzed from the data open to the public. Phase equilibrium process model was introduced that the vapor and water are at saturation point in the vessels. Proposed accident scenario agrees very well with the data of the plant parameters obtained just after the accident. The estimation describes that the rupture time of the reactor pressure vessel (RPV) was at 22:50 14/3/2011. The estimation shows that the rupture time of the pressure containment vessel (RCP) was at 7:40 15/3/2011. These estimations are different from the ones by TEPCO, however; many measured evidences show good accordance with the present scenario. (author)

  15. Fukushima Daiichi Unit 1 Uncertainty Analysis-Exploration of Core Melt Progression Uncertain Parameters-Volume II.

    Energy Technology Data Exchange (ETDEWEB)

    Denman, Matthew R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brooks, Dusty Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-08-01

    Sandia National Laboratories (SNL) has conducted an uncertainty analysi s (UA) on the Fukushima Daiichi unit (1F1) accident progression wit h the MELCOR code. Volume I of the 1F1 UA discusses the physical modeling details and time history results of the UA. Volume II of the 1F1 UA discusses the statistical viewpoint. The model used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). The goal of this work was to perform a focused evaluation of uncertainty in core damage progression behavior and its effect on key figures - of - merit (e.g., hydrogen production, fraction of intact fuel, vessel lower head failure) and in doing so assess the applicability of traditional sensitivity analysis techniques .

  16. A concept of countermeasure against radioactive wastewater generated in disastrous nuclear accident such as Fukushima Daiichi site case

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kwang-Wook; Lee, Keun-Young; Lee, Eil-Hee; Baek, Yeji; So, Ji-Yang; Chung, Dong-Young; Moon, Jei-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    Before the operation of initial wastewater treatment systems supplied by AREVA and Kurion companies, which were installed about 6 months after the accident, the contaminated water was accumulated in reactor and turbine buildings, then was moved and stored in many hurriedly-prepared storage tanks including even mega float barge. The wastewater treatment systems using Cs-adsorption columns and desalination equipment was not properly operated and there were several small and big leakages of contaminated water from the wastewater treatment system and storage tanks, so that tremendous wastewater had been accumulated during those periods. That thereafter led to many secondary problems in management and treatment of the wastewater. Since the disastrous accident at Fukushima, several measures to more enhance safety of nuclear power plants located on coastal area have been asked. As one of them, a countermeasure against generation of tremendous radioactive wastewater in disastrous nuclear accident like the Fukushima Daiichi station was asked to be prepared.

  17. Variation of radiocesium concentrations in cedar pollen in the Okutama area since the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Tsuruoka, H.; Inoue, K.; Sakano, Y.; Hamada, M.; Shimizu, H.; Fukushi, M.

    2015-01-01

    Due to releases of radionuclides in the Fukushima Daiichi Nuclear Power Plant accident, radiocesium ( 134 Cs and 137 Cs) has been incorporated into large varieties of plant species and soil types. There is a possibility that radiocesium taken into plants is being diffused by pollen. Radiocesium concentrations in cedar pollen have been measured in Ome City, located in the Okutama area of metropolitan Tokyo, for the past 3 y. In this research, the variation of radiocesium concentrations was analysed by comparing data from 2011 to 2014. Air dose rates at 1 m above the ground surface in Ome City from 2011 to 2014 showed no significant difference. Concentration of 137 Cs contained in the cedar pollen in 2012 was about half that in 2011. Between 2012 and 2014, the concentration decreased by approximately one-fifth, which was similar to the result of a press release distributed by the Japanese Ministry of Agriculture, Forestry and Fisheries. (authors)

  18. Translocation of radiocesium released by the Fukushima Daiichi nuclear power plant accident in Japanese chestnut and chestnut weevil larvae

    International Nuclear Information System (INIS)

    Sasaki, Yoshito; Ishii, Yasuo; Abe, Hironobu; Mitachi, Katsuaki; Watanabe, Takayoshi; Niizato, Tadafumi

    2016-01-01

    To examine the translocation of radiocesium scattered by the Fukushima Daiichi nuclear power plant accident that occurred in March 2011 to the Japanese chestnut, we investigated the autoradiography and radiocesium concentration in each part of Japanese chestnuts. The Japanese chestnut fruit has a thin skin between the kernel (cotyledons) and shell; the kernel of the fruit is edible. The 137 Cs concentration in each part of the fruit was found to be almost the same at about 1.0 × 10 4 Bq·kg -1 DW, as well as leaves. The radiocesium concentration in chestnut weevil larvae found on the fruit was approximately one-seventh of that in the kernel. (author)

  19. Lesson and learn from 'Fukushima Daiichi' 180 day's tweets. Inevitable NPP renaissance of the culture and technology

    Energy Technology Data Exchange (ETDEWEB)

    Tamaki, Masayoshi B., E-mail: a40507a@cc.nagoya-u.ac.jp [TAMAKI Memorial Inst., Komaki, Aichi (Japan)

    2011-07-01

    Tweeting for severe reactor accident of Toden-EPCO Fukushima Daiichi due to the Eastern Japan M9 earthquake brought me 'Nuclear Renaissance'. Along to the twitter-time-line of the accident consequences, the spent fuel pool, containment, hydrogen explosion, destroyed core, and contamination have been discussed as Inferno. 'Hairo' and back fitting of existing NPPs have been discussed as Purgatorio. NPP Renaissance through nuclear energy synergetics has been discussed as Paradiso. Through these discussions, the East Asia Rim Community takes the role of the 'KOU(one of the keywords in traditional East Asian game 'GO') for realizing 'Nuclear Renaissance' by the 22 Century, resulting in becoming the keystone of the development to the 'All Asia Community'. (author)

  20. Lesson and learn from 'Fukushima Daiichi' 180 day's tweets. Inevitable NPP renaissance of the culture and technology

    International Nuclear Information System (INIS)

    Tamaki, Masayoshi B.

    2011-01-01

    Tweeting for severe reactor accident of Toden-EPCO Fukushima Daiichi due to the Eastern Japan M9 earthquake brought me 'Nuclear Renaissance'. Along to the twitter-time-line of the accident consequences, the spent fuel pool, containment, hydrogen explosion, destroyed core, and contamination have been discussed as Inferno. 'Hairo' and back fitting of existing NPPs have been discussed as Purgatorio. NPP Renaissance through nuclear energy synergetics has been discussed as Paradiso. Through these discussions, the East Asia Rim Community takes the role of the 'KOU(one of the keywords in traditional East Asian game 'GO') for realizing 'Nuclear Renaissance' by the 22 Century, resulting in becoming the keystone of the development to the 'All Asia Community'. (author)

  1. A knowledge on environmental radiation monitoring about the influence from Fukushima Dai-ichi Nuclear Power accident

    International Nuclear Information System (INIS)

    Yoshioka, Mitsuo; Terakawa, Kazuyoshi; Kasai, Toshihiro

    2012-01-01

    A large amount of radioactive substances were released in the atmosphere and contaminated a large area across Japan due to the accident at Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company triggered by Great East Japan Earthquake and tsunami on May 11th 2011. At Fukui University of Technology, monitoring of air radiation (gamma ray) and radiation in environmental samples in Fukui prefecture and some areas of Fukushima prefecture were conducted in order to study the influence of radiation and radioactivity on the citizens as well as the perception of this study results by the citizens. Also, in order to study the dependency of the radiation influence on the distance from the accident location, radiation monitoring of fallouts (air-borne dust, rainwater, sediment mud, and so on) was conducted. In this article, the knowledge obtained on environmental radiation monitoring was summarized and reported. Especially, slightly modified dose-level evaluation for internal exposure was reported. (S.K.)

  2. Morphological abnormalities in gall-forming aphids in a radiation-contaminated area near Fukushima Daiichi: selective impact of fallout?

    Science.gov (United States)

    Akimoto, Shin-ichi

    2014-01-01

    To evaluate the impact of fallout from the Fukushima Daiichi Nuclear Power Plant accident on organisms, this study compared the morphology and viability of gall-forming