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Sample records for tokai-mura reactor

  1. Coastal observation of Tokai-mura

    International Nuclear Information System (INIS)

    Iwasaki, Kohzi; Kinoshita, Mutsumi; Kurabayashi, Mizumi; Yamato, Aiji; Narita, Osamu

    1976-01-01

    The survey of sea current with a flow direction and speed meter is generally performed to have knowledge and information on the state of flow in a sea area concerned. Such survey has been carried out for long in the sea off Tokai-mura, thereby the flow tendency up to several km offshore has been obtained. In the series of survey by PNC (Power Reactor and Nuclear Fuel Development Corporation) from 1974 to 1975, multi-point simultaneous flow survey was carried out. These results are described together with two- and three-dimensional flow characteristics. (Mori, K.)

  2. Deposition of radionuclides and stable elements in Tokai-mura

    Energy Technology Data Exchange (ETDEWEB)

    Ueno, Takashi; Amano, Hikaru [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    This report presents the data of deposition of radionuclides (Sep. 1993-March 2001) and stable elements (Sep. 1993-Oct. 1995) in Tokai-mura. To evaluate the migration of radionuclides and stable elements from the atmosphere to the ground surface, atmospheric deposition samples were collected from Sep. 1993 to March 2001 with three basins (distance to grand surface were 1.5 m, 4 m, 10 m) set up in the enclosure of JAERI in Tokai-mura, Ibaraki-ken, Japan. Monthly samples were evaporated to dryness to obtain residual samples and measured with a well type Ge detector for {sup 7}Be, {sup 40}K, {sup 137}Cs and {sup 210}Pb. According to the analysis of radioactivity, clear seasonal variations with spring peaks of deposition weight (dry) and deposition amounts of all objective radionuclides were found. Correlation analysis of deposition data also showed that these radionuclides can be divided into two groups. A part of dried sample was irradiated to reactor neutrons at JRR-4 for determination of stable element's deposition. (author)

  3. The reprocessing plant of Tokai-Mura (Japan)

    International Nuclear Information System (INIS)

    Lung, M.; Coignaud, M.

    1978-01-01

    The main stages of cooperation between Japan and the French nuclear industry for the development of the Tokai-Mura plant are presented. The plant facilities and the operating conditions are described [fr

  4. Sea conditions off Tokai-mura

    International Nuclear Information System (INIS)

    Fukuda, Masaaki

    1975-01-01

    The result of investigation on the conditions of oceanic diffusion off Tokai-mura is presented. The diffusion phenomena are very complicated. The turbulent diffusion was analyzed by statistical method used with the data of sea current. The meteorological conditions, geographical feature and sea conditions effect considerably in oceanic diffusion in coastal area. By separating into short range and long range, the dye diffusion experiment and the river water diffusion were analyzed with several diffusion models. The author also describes on the behavior of nuclides connected with the deposition. (auth.)

  5. Effects of the criticality accident at Tokai-mura on the public's attitude to nuclear power generation

    International Nuclear Information System (INIS)

    Kitada, Atsuko; Hayashi, Chikio

    2000-01-01

    The objective of our study was to clarify the effects on the public's attitude of nuclear power and the criticality accident that occurred at the JCO plant in Tokai-mura, Ibaraki Prefecture. For this purpose, we conducted an awareness survey in the Kansai and Kanto areas two months after the accident. Analysis was made on the basis of the comparison of the survey results with the data that the Institute of Nuclear Safety System had accumulated through continuous awareness surveys on nuclear power generation (regular surveys) since 1993. The public's reactions were twofold. On one hand, there were emotional reactions about accidents in nuclear facilities and a reduction in the sense of security. On the other hand, there were reactions concerning the image of nuclear power plant workers and demand on electricity utilities for enhanced employee education and training. The latter reactions correspond to the problems pointed out after the JCO accident. Regarding the utilization of nuclear power generation, the opinion that 'the utilization of nuclear power generation is unavoidable' accounts for 60% of those surveyed. With the opinion that 'nuclear power generation should be utilized' added, 70% of those surveyed take an affirmative attitude to nuclear power utilization. This situation has remained about the same since 1998, the year before the JCO accident. Using the quantification method III to analyze a number of questionnaires about nuclear power generation such as the anxiety about it, we determined overall attitude indexes regarding nuclear power to perform a time sequence comparison. The comparison shows that the attitude after the JCO accident tended to be more negative than in 1998. However, no significant difference in the overall indexes is seen between 1993 and 1998. Judging the comparison results on the basis of the time span starting in 1993 allows us to conclude that the JCO accident has not greatly contributed to worsening the attitude towards nuclear

  6. The JCO criticality accident at Tokai-mura, Japan: an overview of the sampling campaign and preliminary results

    International Nuclear Information System (INIS)

    Komura, K.; Yamamoto, M.; Muroyama, T.; Murata, Y.; Nakanishi, T.; Hoshi, M.; Takada, J.; Ishikawa, M.; Takeoka, S.; Kitagawa, K.; Suga, S.; Endo, S.; Tosaki, N.; Mitsugashira, T.; Hara, M.; Hashimoto, T.; Takano, M.; Yanagawa, Y.; Tsuboi, T.; Ichimasa, M.; Ichimasa, Y.; Imura, H.; Sasajima, E.; Seki, R.; Saito, Y.; Kondo, M.; Kojima, S.; Muramatsu, Y.; Yoshida, S.; Shibata, S.; Yonehara, H.; Watanabe, Y.; Kimura, S.; Shiraishi, K.; Ban-nai, T.; Sahoo, S.K.; Igarashi, Y.; Aoyama, M.; Hirose, K.; Uehiro, T.; Doi, T.; Tanaka, A.; Matsuzawa, T.

    2000-01-01

    A criticality accident occurred on September 30, 1999 at the uranium conversion facility of the JCO Company Ltd. in Tokai-mura, Japan. A collaborating scientific investigation team was organized in two groups, the first to carry out research on the environmental impact (the environmental research group) and the second to assess the radiation effects on residents (the biological research group). This report concerns only the activities of the environmental research group. Four investigative teams were sent on different dates to the accident site and its vicinity to collect samples. About 400 samples were collected and subjected to analysis. An outline of the sampling campaign is presented here along with a brief chronology of the accident and the preliminary key results obtained by the independent research group are summarised in this Special Issue of the Journal of Environmental Radioactivity

  7. Stable isotope ratios of the atmospheric CH4, CO2 and N2O in Tokai-mura

    International Nuclear Information System (INIS)

    Porntepkasemsan, Boonsom; Andoh, Mariko A.; Amano, Hikaru

    2000-11-01

    This report presents the results and interpretation of stable isotope ratios of the atmospheric CH 4 , CO 2 and N 2 O from a variety of sources in Tokai-mura. The seasonal changes of δ 13 CH 4 , δ 13 CO 2 and δ 15 N 2 O were determined under in-situ conditions in four sampling sites and one control site. Such measurements are expected to provide a useful means of estimating the transport mechanisms of the three trace gases in the environment. These isotopic signatures were analyzed by Isotope Ratio Mass Spectrometer (IRMS, Micromass Isoprime). Our data showed the significant seasonal fluctuation in the Hosoura rice paddy during the entire growing season in 1999. Possible causes for the variation are postulated. Additional measurements on soil properties and on organic δ 13 C in rice plant are suggested. Cited outstanding original papers are summarized in the references. (author)

  8. Multiple parameter biodosimetry of exposed workers from the JCO criticality accident in Tokai-mura

    Energy Technology Data Exchange (ETDEWEB)

    Blakely, William F. [Armed Forces Radiobiology Research Institute, Bethesda, MD (United States)

    2002-03-01

    Full text: On 30 September 1999, three workers at the JCO (Japan Nuclear Fuel Conversion Corporation) uranium fuel processing facility in Tokai-mura, Ibaraki Prefecture, Japan, were severely exposed to neutrons and gamma rays. In this issue of the journal, Nishimura et al report the measurement of {sup 32}P in urine from the three victims for early estimation of neutron exposure levels. This is one of several reports that estimate doses received by the exposed workers and residents, based on biological responses, radiation monitoring/transport codes, and other opportunistic dosimetric approaches. The higher relative biological effectiveness (RBE) of neutrons for life-threatening radiation injury justifies efforts to establish a neutron biodosimetry capability. Accurate estimation of the exposure dose by cytogenetic-based chromosome aberration assays, however, requires knowledge of the neutron component in the mixed neutron and gamma radiation scenario. Dose responses for dicentric and ring type chromosome aberration yields measured in peripheral blood lymphocytes are responsive to radiation quality. Protocols for dose assessment by cytogenetic-chromosome aberration assays are internationally accepted. Analytic approaches using cytogenetic chromosome aberrations are established for dose assessment in mixed neutron and gamma radiation accidents. Use of the premature chromosome condensation, or PCC, assay now permits these measurements even at unusually high doses of gamma and neutron radiation. Hayata and colleagues measured ring-type chromosome aberrations in interphase cells by use of the PCC-ring assay to estimate dose for the three severely exposed patients in this accident. Ring-type aberrations are formed in higher yields after neutron versus gamma radiation but these ring-aberrations do not provide a unique signature response specific for neutron exposures. Intense research efforts are currently underway to identify more specific chromosome aberration and

  9. The Tokai-mura JCO criticality accident and the activities of the accident countermeasure support team of Electric Power Companies, Japan

    International Nuclear Information System (INIS)

    Ogawa, Junko

    2000-01-01

    A criticality accident occurred at the JCO Tokai-mura nuclear fuel processing plant on September 30, 1999. This accident brought the damages which were unrivaled in the history of atomic energy development in Japan, seriously influencing the citizen life to such an extent as requesting for 320,000 inhabitants within 10 kilometers radius to stay indoors for as long as 18 hours. However, it could be said that though three workers suffered fatal injuries, no substantial hazards were made upon the regional inhabitants due to little release of radioactive substances. This video recorded the activities of the Accident Countermeasure Support Team of the Electric Power Companies immediately after the accident occurred, showing the chronological overview of the particulars of the accident. (author)

  10. Effects of the criticality accident at Tokai-mura on the public's attitude to nuclear power generation

    Energy Technology Data Exchange (ETDEWEB)

    Kitada, Atsuko [Institute of Social Research, Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Hayashi, Chikio [The Institute of Statistical Mathematics, Tokyo (Japan)

    2000-09-01

    The objective of our study was to clarify the effects on the public's attitude of nuclear power and the criticality accident that occurred at the JCO plant in Tokai-mura, Ibaraki Prefecture. For this purpose, we conducted an awareness survey in the Kansai and Kanto areas two months after the accident. Analysis was made on the basis of the comparison of the survey results with the data that the Institute of Nuclear Safety System had accumulated through continuous awareness surveys on nuclear power generation (regular surveys) since 1993. The public's reactions were twofold. On one hand, there were emotional reactions about accidents in nuclear facilities and a reduction in the sense of security. On the other hand, there were reactions concerning the image of nuclear power plant workers and demand on electricity utilities for enhanced employee education and training. The latter reactions correspond to the problems pointed out after the JCO accident. Regarding the utilization of nuclear power generation, the opinion that 'the utilization of nuclear power generation is unavoidable' accounts for 60% of those surveyed. With the opinion that 'nuclear power generation should be utilized' added, 70% of those surveyed take an affirmative attitude to nuclear power utilization. This situation has remained about the same since 1998, the year before the JCO accident. Using the quantification method III to analyze a number of questionnaires about nuclear power generation such as the anxiety about it, we determined overall attitude indexes regarding nuclear power to perform a time sequence comparison. The comparison shows that the attitude after the JCO accident tended to be more negative than in 1998. However, no significant difference in the overall indexes is seen between 1993 and 1998. Judging the comparison results on the basis of the time span starting in 1993 allows us to conclude that the JCO accident has not greatly contributed to worsening

  11. Record keeping for the disposal of very low-level concrete waste at the Tokai-Mura site

    International Nuclear Information System (INIS)

    Tsuji, Tomoyuki

    2015-01-01

    The Japan Atomic Energy Agency (JAEA), who conducted the dismantling project of Japan Power Demonstration Reactor (JPDR) completed in March 1996, has been performing the safe demonstration test of near-surface disposal of very low-level (VLL) concrete waste at its Tokai-Mura site. Approximately 1 700 tons of VLL concrete wastes arising from the JPDR dismantling were placed in a simple disposal facility from November 1995 until March 1996, its dimensions were 45 m x 16 m and 3.5 m in depth without any engineered barrier, and covered with soil of 2.5 m thickness. The safe demonstration test of near-surface disposal of VLL concrete waste consists of an operation stage (1995-1996) and a management stage (1996-2024). During the operation stage, the radiation dose around the disposal facility was measured, and groundwater and soil were analysed for radioactivity concentrations. After entering the management stage, radiation monitoring was continued for an additional three years. Inspections for potential outflows, cracks and soil-cover subsidence are conducted once a week. Regarding VLL concrete waste, it has been required to record its radioactivity concentrations and preserve the record until the end of institutional control period in accordance with the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors. JAEA has been required to preserve these records until the end of the institutional control period. It is planned to preserve the radiation monitoring data during the operation stage and until the end of institutional control period. Inspection data are preserved in accordance with the act. When amending the act in 2013, the requirements to implement the periodic safety review were added. For this purpose, it has been required to record in the management stage the following measures: a level of groundwater, radioactivity concentrations in groundwater, rainfall and total amount of rainfall a month. These records will have been

  12. Residual neutron-induced radionuclides in a soil sample collected in the vicinity of the criticality accident site in Tokai-mura, Japan: A Progress Report

    International Nuclear Information System (INIS)

    Nakanishi, Takashi; Hosotani, Risa; Komura, Kazuhisa; Muroyama, Toshiharu; Kofuji, Hisaki; Murata, Yoshimasa; Kimura, Shinzo; Kumar Sahoo, Sarata; Yonehara, Hidenori; Watanabe, Yoshito; Ban-nai, Tada-aki

    2000-01-01

    Residual neutron-induced radionuclides were measured in a soil sample collected in the vicinity of the location where a criticality accident occurred (in Tokai-mura, from 30 September to 1 October, 1999). Concentrations of 24 Na, 140 La, 122 Sb, 59 Fe, 124 Sb, 46 Sc, 65 Zn, 134 Cs and 60 Co in the soil sample were determined by γ-ray spectrometry, and neutron activation analysis was carried out for selected target elements in the sample. Tentative estimates of the apparent thermal and epithermal neutron fluences which reached the sample were obtained through combined analyses of 59 Fe/ 58 Fe, 124 Sb/ 123 Sb, 46 Sc/ 45 Sc, 65 Zn/ 64 Zn, 134 Cs/ 133 Cs and 60 Co/ 59 Co

  13. Cytogenetical dose estimation for 3 severely exposed patients in the JCO criticality accident in Tokai-mura

    International Nuclear Information System (INIS)

    Hayata, Isamu; Kanda, Reiko; Minamihisamatsu, Masako; Furukawa, Akira; Sasaki, Masao S.

    2001-01-01

    A dose estimation by chromosome analysis was performed on the 3 severely exposed patients in the Tokai-mura criticality accident. Drastically reduced lymphocyte counts suggested that the whole-body dose of radiation which they had been exposed to was unprecedentedly high. Because the number of lymphocytes in the white blood cells in two patients was very low, we could not culture and harvest cells by the conventional method. To collect the number of lymphocytes necessary for chromosome preparation, we processed blood samples by a modified method, called the high-yield chromosome preparation method. With this technique, we could culture and harvest cells, and then make air-dried chromosome slides. We applied a new dose-estimation method involving an artificially induced prematurely condensed ring chromosome, the PCC-ring method, to estimate an unusually high dose with a short time. The estimated doses by the PCC-ring method were in fairly good accordance with those by the conventional dicentric and ring chromosome (Dic + R) method. The biologically estimated dose was comparable with that estimated by a physical method. As far as we know, the estimated dose of the most severely exposed patient in the present study is the highest recorded among that chromosome analyses have been able to estimate in humans. (author)

  14. Radioactive airborne effluent discharged from Tokai reprocessing plant. 1998-2007

    International Nuclear Information System (INIS)

    Nakada, Akira; Miyauchi, Toru; Akiyama, Kiyomitsu; Momose, Takumaro; Kozawa, Tomoyasu; Yokota, Tomokazu; Ohtomo, Hiroyuki

    2008-10-01

    This report provides the data set of atmospheric discharges from Tokai reprocessing plant in Tokai-mura, Japan over the period from 1998 to 2007. Daily and weekly data are shown for 85 Kr that is continuously monitored and for the other nuclides (alpha emitters, beta emitters, 3 H, 14 C, 129 I and 131 I) whose activities are evaluated based on weekly samplings (Weekly sampling is continuous for 1 week). The data contained in this report are expected to apply for studying the behavior of the radioactive airborne effluent in the environment. (author)

  15. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Ward, M.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. Tokai Mura end caps arise when the fuel from the Japanese Tokai Mura reactor is decanned prior to fuel processing. Headings are: introduction (origin and arisings); waste characterisation; alternative matrices for encapsulation of waste in form suitable for disposal. (U.K.)

  16. Health hazard of the Tokai mura nuclear accident. Unnecessary fear and improper health checks should be eliminated

    International Nuclear Information System (INIS)

    Takebe, Hiraku

    2000-01-01

    Three workers were heavily exposed to radiations in the Tokai mura nuclear accident, and one of them died due to the acute effects of radiations. Doses for the heavily exposed persons were estimated to be 2.5, 10 and 18 Sv, according to the Science and Technology Agency. Workers who tried to stop the chain reaction by breaking the water pipe were estimated to have been exposed up to 120 mSv. Possible doses for other workers and residents in the neighborhoods were estimated to be less than 10 mSv, with a few workers with slightly higher film badge records. After the accident, many reports in mass-media warned that the exposed persons may develop cancers and leukemias in future and follow-up healthcare should be needed. Judging from our knowledge of the extensive epidemiological survey of the atomic bomb survivors in Hiroshima and Nagasaki, these reports are very misleading. There would be absolutely no or extremely small possibility of developing any health hazard among the workers and the residents except for the three unfortunate heavily exposed workers. If so-called follow-up health checks would involve x-ray diagnosis for cancers, the radiation doses by the diagnosis would exceed the exposure by the accident. Also, the test for the DNA damage applied to some workers and residents is not reliable at all, and could cause unnecessary fear among the persons who were mistakingly said to be of high-risk. (author)

  17. The classification of cases related to Tokai-mura criticality accident. Mental care after radiation exposure

    International Nuclear Information System (INIS)

    Minoshita, Seiko; Satoh, Shinji

    2012-01-01

    Cases classified into each pattern, which the authors have met so far after the criticality accident JCO was introduced. Case is introduced, based on multiple cases actually met in medical institutions, has been created as a model case. When the cases that were considered related to the criticality accident in Tokai-mura was summarized, the cases could be classified by the time consultation. Therefore the cases were discussed along the time, also discussed about the time. From the first year to the second year, the most cases seen were the cases with high anxiety. Then, there were many cases which symptoms were worsened by the impact received through the residents meeting. Among the patients who received counseling from half a year to three years after the incident, the onset of mental illness, and the aggravation of the mental disease increased, too. After two or three years of the incident, there were a lot of consultation with women who were pregnant or had infants then. Four years later, men gradually came to have consultation at hospitals. In addition, the consultation of alcohol from problems of a family member has increased. In the first year, there were many patients that a symptom turned worse since they were shocked by the booing of the residents meeting. On the other hand, the patients that a symptom turned worse because of the prolonged issue increased four years later. Four or five years, after the incident the cases of because of bankruptcy or dismissal, life been deteriorated economically were increased, and some cases were led to the discrete of family in a chain reaction. Approximately 10 years later, due to the increase of the aging population, the amount of patient who were frightened because they got cancer increased since they lost the people around them as a result of cancer. (author)

  18. Permanent cessation of Tokai power plant's operation

    International Nuclear Information System (INIS)

    Satoh, T.

    1998-01-01

    Tokai power plant (166MWe, Magnox type: GCR) is the first commercial reactor in Japan and has been kept operating stable since its commissioning in July 1996. During this period it has produced electricity of approximately 27.7 billion KWh (as of March 1997) and its stable operation has contributed greatly to the stable supply of electricity in Japan. Furthermore, technologies in various fields have been developed, demonstrated and accumulated through the construction and operation of Tokai power plant. It also contributes to training for many nuclear engineers, and constructions and operations of nuclear power stations by other Japanese power companies. As a pioneer, it has been achieved to develop and popularize Japanese nuclear power generation. On the other hand, Tokai power plant has small capacity in its electric power output, even though the size of the reactor and heat exchangers are rather bigger than those of LWR due to the characteristics of GCR. Therefore, the generation cost is higher than the LWR. Since there is no plant whose reactor type is the same as that of Tokai power plant, the costs for maintenance and fuel cycle are relatively higher than that of LWR. Finally we concluded that the longer we operate it, the less we can take advantage of it economically. As a result of the evaluation for the future operation of Tokai power plant including the current status for supply of electricity by the Japanese utilities and study of decommissioning by Japanese government, we decided to have a plan of stopping its commercial operation of Tokai power plant in the end of March, 1998, when we completely consume its fuel that we possess. From now on, we set about performing necessary studies and researches on the field of plant characterization, remote-cutting, waste disposal for carrying out the decommissioning of Tokai power plant safely and economically. We are going to prepare the decommissioning planning for Tokai power plant in a few years based on the

  19. Tokai works semi-annual progress report, July--December 1975

    International Nuclear Information System (INIS)

    1976-09-01

    The Power Reactor and Nuclear Fuel Development Corporation (PNC) is a semi-governmental organization responsible for the development of advanced power reactors and nuclear fuels in Japan. The Tokai Works is the PNC center for research and development of nuclear fuels concerned with plutonium fuels fabrication, fuel reprocessing, and centrifugal uranium enrichment. Accomplishments in the activities of Tokai Works during the latter half of 1975 are summarized as follows: (1) Plutonium fuels development--Fabrication of core fuel assemblies is being continued for initial loading of the Experimental Fast Breeder Reactor JOYO and remodeling is being carried out on the facility for fabrication of plutonium fuels for the Prototype Heavy Water Moderated and Boiling Light Water Cooled Reactor FUGEN; (2) Fuel reprocessing--Construction of the Tokai Reprocessing Plant is nearly completed and preparation for its commissioning is being made; (3) Development of centrifugal uranium enrichment is being performed successfully

  20. Remote systems and remote maintenance of a reprocessing plant in Japan

    International Nuclear Information System (INIS)

    Funaya, T.

    1977-01-01

    The design concept and overall maintenance philosophy applied in the Power Reactor and Nuclear Fuel Development Corporation Reprocessing Plant at Tokai-mura, Japan, are briefly introduced. Details on remote systems and remote maintenance in mechanical processing areas are described

  1. Development of posture-specific computational phantoms using motion capture technology and application to radiation dose-reconstruction for the 1999 Tokai-Mura nuclear criticality accident

    International Nuclear Information System (INIS)

    Vazquez, Justin A; Caracappa, Peter F; Xu, X George

    2014-01-01

    The majority of existing computational phantoms are designed to represent workers in typical standing anatomical postures with fixed arm and leg positions. However, workers found in accident-related scenarios often assume varied postures. This paper describes the development and application of two phantoms with adjusted postures specified by data acquired from a motion capture system to simulate unique human postures found in a 1999 criticality accident that took place at a JCO facility in Tokai-Mura, Japan. In the course of this accident, two workers were fatally exposed to extremely high levels of radiation. Implementation of the emergent techniques discussed produced more accurate and more detailed dose estimates for the two workers than were reported in previous studies. A total-body dose of 6.43 and 26.38 Gy was estimated for the two workers, who assumed a crouching and a standing posture, respectively. Additionally, organ-specific dose estimates were determined, including a 7.93 Gy dose to the thyroid and 6.11 Gy dose to the stomach for the crouching worker and a 41.71 Gy dose to the liver and a 37.26 Gy dose to the stomach for the standing worker. Implications for the medical prognosis of the workers are discussed, and the results of this study were found to correlate better with the patient outcome than previous estimates, suggesting potential future applications of such methods for improved epidemiological studies involving next-generation computational phantom tools. (paper)

  2. Risk communication activities toward nuclear safety in Tokai: your safety is our safety

    International Nuclear Information System (INIS)

    Tsuchiya, T.

    2007-01-01

    As several decades have passed since the construction of nuclear power plants began, residents have become gradually less interested in nuclear safety. The Tokai criticality accident in 1909, however, had roused residents in Tokai-Mura to realize that they live with nuclear technology risks. To prepare a field of risk communication, the Tokai-Mura C 3 project began as a pilot research project supported by NISA. Alter the project ended, we are continuing risk. communication activities as a non-profit organisation. The most important activity of C 3 project is the citizen's inspection programme for nuclear related facilities. This programme was decided by participants who voluntarily applied to the project. The concept of the citizen's inspection programme is 'not the usual facility tours'. Participants are involved from the planning stage and continue to communicate with workers of the inspected nuclear facility. Since 2003, we have conducted six programmes for five nuclear related organisations. Participants evaluated that radiation protection measures were near good but there were some problems concerning the worker's safety and safety culture, and proposed a mixture of advice based on personal experience. Some advice was accepted and it did improve the facility's safety measures. Other suggestions were not agreed upon by nuclear organisations. The reason lies in the difference of concept between the nuclear expert's 'safety' and the citizen's 'safety'. Residents do not worry about radiation only, but also about the facility's safety as a whole including the worker's safety. They say, 'If the workers are not safe, you also are unable to protect us'. Although the disagreement remained, the participants and the nuclear industry learned much about each other. Participating citizens received a substantial amount of knowledge about the nuclear industry and its safety measures, and feel the credibility and openness of the nuclear industry. On the other hand, the nuclear

  3. Annual report of the CTR Blanket Engineering research facility in 1994

    International Nuclear Information System (INIS)

    1995-09-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor(CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1994. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (author)

  4. Annual report of the CTR blanket engineering research facility in 1993

    International Nuclear Information System (INIS)

    1994-08-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor (CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1993. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (author)

  5. Tokai densitometer manual

    International Nuclear Information System (INIS)

    Sprinkle, J.K. Jr.; Hsue, S.T.; Junck, K.

    1987-01-01

    In 1979, the Tokai densitometer was installed at the Tokai Reprocessing Plant in Tokai, Japan. It uses a nondestructive active technique (K-edge absorption densitometry) to assay solutions for plutonium content. The original hardware was upgraded in 1984 and 1985. This manual describes the instrument's operation after the upgrade. 2 refs

  6. Statistics of meteorological data at Tokai Research Establishment in JAERI

    International Nuclear Information System (INIS)

    Sekita, Tsutomu; Tachibana, Haruo; Matsuura, Kenichi; Yamaguchi, Takenori

    2003-12-01

    The meteorological observation data at Tokai site were analyzed statistically based on a 'Guideline of meteorological statistics for the safety analysis of nuclear power reactor' (Nuclear Safety Commission on January 28, 1982; revised on March 29, 2001). This report shows the meteorological analysis of wind direction, wind velocity and atmospheric stability etc. to assess the public dose around the Tokai site caused by the released gaseous radioactivity. The statistical period of meteorological data is every 5 years from 1981 to 1995. (author)

  7. Annual report of the CTR Blanket Engineering research facility in 1992

    International Nuclear Information System (INIS)

    1993-08-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor (CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1992. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (J.P.N.)

  8. Annual report of the CTR Blanket Engineering research facility in 1996

    International Nuclear Information System (INIS)

    1998-02-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor (CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1996. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (J.P.N.)

  9. Proceedings of the Third CSNI Workshop on Iodine Chemistry in Reactor Safety

    International Nuclear Information System (INIS)

    Ishigure, K.; Saeki, M.; Soda, K.; Sugimoto, J.

    1992-03-01

    The Third CSNI Workshop on Iodine Chemistry in Reactor Safety was held at Tokai Research Establishment of Japan Atomic Energy Research Institute at Tokai-mura, Ibaraki-ken, Japan, on September 11 to 13, 1991. About 60 experts attended the Workshop from 10 countries and 2 international organizations. In the Workshop, 29 papers were presented in five sessions on various aspects of iodine chemistry in reactor safety, such as radiolytic and surface reactions of iodine species, fundamental and integral tests, modeling and code developments. The information exchanged and the discussions followed resulted in extended and promoted understanding of iodine behavior in accidents of light water reactors and also gave a large expectation for the further progresses coming in the future. It should be emphasized that a most important and unique forum has been established through the Workshop for exchanging information and collaboratively solving the important problems in the field of the iodine chemistry in nuclear reactor safety. At the Workshop, an effort was made to integrate all information for better use by safety analysts. There is no doubt that a lot of information on iodine behaviour has been accumulated, but in many cases this information needs to be co-ordinated and well organised for safety analyses of nuclear reactors. It is essential that the results of laboratory studies and integral experiments together with modelling activities are well co-ordinated. Therefore, the goal was: - to review the knowledge and understanding of the chemistry of iodine of relevance to the prediction of its behaviour in nuclear reactors during a range of operational and accident conditions; - to define those areas of chemistry which are important but poorly understood and require further study. As shown by the conclusions of the Workshop, there is no doubt that this objective was widely attained

  10. The disappointments for nuclear energy in Japan; Les deconvenues pour l'energie nucleaire au Japon

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Several dysfunctions are reported in this paper: A reactor (Onagawa) closed after a nitrogen leakage; a small leakage of radioactive water in the nuclear power plant of Mihama assessment raised to five deaths, the operator stops its nuclear power plants for inspection, the Japan face to its ageing nuclear power plants, the truth about the cost of M.O.X., the seven reactors of Japan closed for inspection after cracks and leaks hidden to authorities, Tokai MURA accident. (N.C.)

  11. The disappointments for nuclear energy in Japan

    International Nuclear Information System (INIS)

    2004-01-01

    Several dysfunctions are reported in this paper: A reactor (Onagawa) closed after a nitrogen leakage; a small leakage of radioactive water in the nuclear power plant of Mihama assessment raised to five deaths, the operator stops its nuclear power plants for inspection, the Japan face to its ageing nuclear power plants, the truth about the cost of M.O.X., the seven reactors of Japan closed for inspection after cracks and leaks hidden to authorities, Tokai MURA accident. (N.C.)

  12. Restoration of trust and activities for public consensus toward installation of newly added units

    International Nuclear Information System (INIS)

    Ogawa, Junko; Murabe, Yoshikazu

    2001-01-01

    Japan Atomic Power Company, as a pioneer of nuclear power generation in Japan, owns 4 units in total in Tokai Mura, Ibaraki Prefecture and Tsuruga City, Fukui Prefecture. The Tokai Power Plant installed at Tokai Mura has ceased its commercial operation, now in preparation for decommissioning. It is necessary for Japan to promote nuclear power generation with such factors taken into consideration as self-reliance and stable supply of energy, reduction of CO 2 emissions for prevention of global warming, etc., despite fallen confidence in nuclear energy due to various troubles like the JCO accident. Under such circumstances, our Company has the plan to add 2 Units of Advanced Pressurised Water Reactor (APWR ) as Units No. 3 and 4 of the Tsuruga Power Generating Station, each rated to be 1,530 MWe, the world largest capacity , totalling 3,070 MWe. at this nuclear site. This paper presents the basic Corporate principles for promotion of understanding of nuclear energy itself, and the Corporate activities for promotion of understanding by the community people on adding the Tsuruga Units 3 and 4, in pursuant to the basic principles, discussing how the public trust in nuclear energy should be restored in the toughest situation against nuclear energy, and how the added installation of the nuclear units should be promoted

  13. The second eddy current testing of zircaloy tube samples from the OECD Halden reactor project at Reactor Fuel Examination Facility, Tokai, JAERI

    International Nuclear Information System (INIS)

    Ohwada, Isao; Nishino, Yasuharu

    1986-07-01

    The Reactor Fuel Examination Facility in Tokai/JAERI (Japan Atomic Energy Research Institute) joined to the second round robin programme on eddy current test of the Halden/IFE. In the programme, two zircaloy tube samples with some artificial defects were provided for measurements. To clarify the locations in axial and azimuthal directions, types and dimensions of the provided artificial defects, measured signals from eddy current test were analysed in comparison with the known defects on the calibration tube. As a result, fourteen defects were determined from the measurements. Then, the location, the type and the relative dimension of them were also revealed. The results of those eddy current test are described in this paper. (author)

  14. Innovation was not enough a history of the Midwestern Universities Research Association (MURA)

    CERN Document Server

    Jones, Lawrence; Sessler, Andrew; Symon, Keith; Young, Donald

    2010-01-01

    This book presents a history of the Midwestern Universities Research Association (MURA) during its lifetime from the early 1950s to the late 1960s. MURA was responsible for a number of important contributions to the science of particle accelerators, including the invention of fixed field alternating gradient accelerators (FFAG), as well as contributions to accelerator orbit theory, radio frequency acceleration techniques, colliding beams technology, orbit instabilities, computation methods, and designs of accelerator magnets and linear accelerator cavities. A number of students were trained by MURA in accelerator techniques, and went on to important posts where they made further contributions to the field. The authors were all members of the MURA staff and themselves made many contributions to the field. No other such history exists, and there are relatively few publications devoted to the history of particle accelerators.

  15. Living with the consequences of criticality incident

    International Nuclear Information System (INIS)

    Tanaka, Y.

    2001-01-01

    The response of population in Tokai-Mura and Japan on the Tokai-Mura reprocessing plant accident of 30 September, 1999 at the nuclear fuel production plant is considered. Results of the public opinion poll on the question under consideration, response of mass media are presented. On evidence of the questioning high quota of people (58 %) advocates further development of the nuclear energetics in spite of fears induced by the accident. However positive attitude to the nuclear energetics reduces from 60 % to 58 %, negative attitude increases from 31 % to 37 %. The accident has an important bearing on regional residents because of its direct effect [ru

  16. Delivery and installation of PC/FRAM at the PNC Tokai Works

    International Nuclear Information System (INIS)

    Sampson, T.E.; Kelley, T.A.; Kroncke, K.E.; Menlove, H.O.; Baca, J.; Asano, Takashi; Terakado, Shigeru; Goto, Yasushi; Kogawa, Noboru

    1997-11-01

    The authors report on the assembly, testing, delivery, installation, and initial testing of three PC/FRAM plutonium isotopic analysis systems at the Power Reactor and Nuclear Fuel Development Corporation's Tokai Works. These systems are intended to measure the isotopic composition and 235 U/plutonium of mixed oxide (MOX) waste in 200-L waste drums. These systems provide capability for performing measurements on lead-lined drums

  17. Mura - čovjek - priroda

    OpenAIRE

    Kantar, Sandra; Ivanek-Martinčić, Marjana; Augustinović, Zvjezdana

    2008-01-01

    U ovom je radu dan pregled radova studenata Visokoga gospodarskog učilišta iz Križevaca, nastalih u sklopu Interreg III A projekta suradnje pod naslovom »Mura - čovjek - priroda«. U projektu su sudjelovali Poljoprivredni fakultet Georgikon iz Keszthelyja Sveučilišta Veszprem, Poljoprivredni muzej Georgikon iz Keszthelyja, Nacionalni park Balaton, nevladina organizacija za zaštitu prirode »Bijeli gavran« i Visoko gospodarsko učilište iz Križevaca. Na hrvatskoj strani, priroda uz Muru je vrl...

  18. Approach to mitigate intergranular stress corrosion cracking and dose rate reduction rate by water chemistry control in Tokai-2

    International Nuclear Information System (INIS)

    Hisamune, Kenji

    2015-01-01

    The Japan Atomic Power Company (JAPC) had been working on material replacement and measures to mitigate stress in order to maintain the integrity of the structural material of Tokai-Daini nuclear power plant (Tokai-2, BWR, 1,100 MWe; commercial operation started on November 28, 1978). In addition, as Stress Corrosion Cracking (SCC) environmental mitigation measures, we have been reducing the sulfate ion concentration in the reactor water by improving the regeneration method of the ion exchange resin at condensate purification system. Furthermore, in conducting the SCC environmental mitigation measures by applying hydrogen water chemistry (HWC) and HWC during start-up (HDS), we have been reducing the oxidizing agent concentration in the reactor water. On the other hand, as a plant that has not installed condensate filters, we have been working on feed water iron concentration reduction measures in Tokai-2 as part of the dose reduction measures. Therefore, we have improved condensate demineralizer's ion exchange resin and the ion exchange resin cleaning method using the ARCS (Advanced Resin Cleaning System) in order to improve the iron removal performance of condensate demineralizer. This document reports the improvement effect of the SCC environmental mitigation measures and the dose reduction measures by water chemistry management at Tokai-2. In addition, the dose reduction effect of the recently applied zinc injection, and the Electrochemical Corrosion Potential (ECP) monitoring plan under the On-Line Noble Chemical Addition (OLNC™) to be implemented later shall be introduced. (author)

  19. The 4th technological meeting of Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Ohnishi, Tohru; Maki, Akira; Shibata, Satomi; Yatogi, Hideo; Nyui, Daisuke; Hashimoto, Takakazu; Fukuda, Kazuhito; Ohzeki, Tatsuya

    2001-11-01

    ''The 4th technological meeting of Tokai Reprocessing Plant (TRP)'' was held in JNFL Rokkasho site on October 11 th , 2001. The report contains the proceedings, transparencies and questionnaires of the meeting. This time, we reported about ''Maintenance and repair results of Tokai Reprocessing Plant'' based on technology and knowledge accumulated in Tokai Reprocessing Plant. (author)

  20. Dose evaluation based on {sup 24}Na activity in the human body at the JCO criticality accident in Tokai-mura

    Energy Technology Data Exchange (ETDEWEB)

    Momose, Takumaro; Tsujimura, Norio; Tasaki, Takashi; Kanai, Katsuta; Kurihara, Osamu; Hayashi, Naomi; Shinohara, Kunihiko [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan). Tokai Works

    2001-09-01

    {sup 24}Na in the human body, activated by neutrons emitted at the JCO criticality accident, was observed for 62 subjects, where 148 subjects were measured by the whole body counter of JNC Tokai Works. The 148 subjects, including JCO employees and the contractors, residents neighboring the site and emergency service officers, were measured by the whole-body counter. The neutron-energy spectrum around the facility was calculated using neutron transport codes (ANISN and MCNP), and the relation between an amount of activated sodium in human body and neutron dose was evaluated from the calculated neutron energy spectrum and theoretical neutron capture probability by the human body. The maximum {sup 24}Na activity in the body was 7.7 kBq (83 Bq({sup 24}Na)/g({sup 23}Na)) and the relevant effective dose equivalent was 47 mSv. (author)

  1. Development of Tokai reprocessing plant maintenance support system (TORMASS) in the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Shimizu, Kazuyuki; Tomita, Tsuneo; Sakai, Katsumi

    2008-01-01

    The maintenance work of many equipments such as mechanical, electrical and instrumentations installed in Tokai reprocessing plant has been performed more then 10,000 times per year and about 90% of maintenances were preventive work. For the maintenance management, optimization of maintenance information is required. Therefore, Tokai Reprocessing Plant Maintenance Support System (TORMASS) was developed from 1985 to 1992 as the aim of construction for suitable maintenance management system. About 24,000 equipments of specifications and about 261,000 maintenance detail were registered in this system. TORMASS has been used for the repair, inspection and replacement of equipment since 1992. (author)

  2. Current status of JAERI Tokai hot cell facilities

    International Nuclear Information System (INIS)

    Itami, Hiroharu; Morozumi, Minoru; Yamahara, Takeshi

    1992-01-01

    JAERI has 4 hot cell facilities in order to examine high radioactive materials. Three of them, the Research Hot Laboratory, the Reactor Fuel Examination Facility and the Waste Safety Testing Facility are located in the JAERI Tokai site, and the rest is the JMTR Hot Laboratory in the Oarai site. The Research Hot Laboratory (RHL) was constructed for post-irradiation examination (PIE), especially nuclear related basic research experiment, such as metallurgical, chemical and mechanical examination on fuels and materials irradiated in research and test reactors. This facility has 10 large dimension concrete and 38 lead cells. At present the RHL is used for various kinds of examinations of high radioactive samples such as fuels of research and test reactors, power reactors and high temperature testing reactor (HTTR), and structural materials. The Reactor Fuel Examination Facility (RFEF) was designed and constructed for carrying out PIE of irradiated full-size fuel assemblies of light water reactors (LWRs). This facility has a storage pool, 8 concrete and 5 lead cells. They are currently used for safety evaluation on high burnup and advanced lWR fuels as part of the national program. The Waste Safety Testing Facility (WASTEF) was designed and constructed for safety research on long-term storage and disposal of high level radioactive wastes, generated by fuel reprocessing. The WASTEF has 5 concrete cells and 1 lead cell. Examinations on the behavior of various long-lived fission products in a glass form and in a canister and, releasing behavior of them out of a canister are carrying out under the condition at storage. (author)

  3. Contamination of incinerator at Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Takahashi, Mutsuo

    1994-01-01

    Originally, at Tokai Reprocessing Plant an incinerator was provided in the auxiliary active facility(waste treatment building). This incinerator had treated low level solid wastes generated every facilities in the Tokai Reprocessing Plant since 1974 and stopped the operation in March 1992 because of degeneration. The radioactivity inventory and distribution was evaluated to break up incinerator, auxiliary apparatuses(bag filter, air scrubbing tower, etc.), connecting pipes and off-gas ducts. This report deals with the results of contamination survey of incinerator and auxiliary apparatuses. (author)

  4. Tokai carbon: A processing sales position is put on Europe; Tokai kabon: oshu ni kako hanbai kyoten

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-30

    It went through the same company with increase in England establishing a business generalization company in Europe, and Tokai carbon purchased the processing sales company graphite-technology (GT Company, England and Birmingham City) of fine carbon. The thing that it aimed at the expansion of the fine carbon business in Europe. A system from the middle product to the final product is prepared, and the reclamation of the new field is included, and it starts active business development by the bribery of the GT Company. Moreover, the head office is set up in London, and Tokai carbon Europe where it was established newly is capital 3400000 pounds. (translated by NEDO)

  5. Biological effects of neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Ogiu, Toshiaki; Ohmachi, Yasushi; Ishida, Yuka [National Inst. of Radiological Sciences, Chiba (JP)] [and others

    2003-03-01

    Although the occasion to be exposed to neutrons is rare in our life, except for nuclear accidents like in the critical accident at Tokai-mura in 1999, countermeasures against accident should be always prepared. In the Tokai-mura accident, residents received less than 21 mSv of neutrons and gamma rays. The cancer risks and fetal effects of low doses of neutrons were matters of concern among residents. The purpose of this program is to investigate the relative biological effectiveness (RBE) for leukemias, and thereby to assess risks of neutrons. Animal experiments are planed to obtain the following RBEs: (1) RBE for the induction of leukemias in mice and (2) RBE for effects on fetuses. Cyclotron fast neutrons (10 MeV) and electrostatic accelerator-derived neutrons (2 MeV) are used for exposure in this program. Furthermore, cytological and cytogenetic analyses will be performed. (author)

  6. Tokai-1 decommissioning project

    International Nuclear Information System (INIS)

    Hirano, Tomoko

    2002-01-01

    The Tokai Power Station (166 MWh in its electric output) of the first commercial nuclear power station in Japan ended its business operation for more than thirty-one years, on end of March, 1998. Through its construction and operation, it has built foundation of nuclear power generation and grown a number of nuclear energy relating engineers. And, technologies and experiences obtained by its construction and operation built base of technology on nuclear power generation in Japan. After now, to share a new role of proof on safe and rational abolishment measure of the first commercial nuclear power stations in Japan, its abolishment measure was begun since December, 2001. It aims at realization of rational subdivision and processing/disposition of wastes, and construction to future LWR abolishment measure. Here were described history of the Tokai Power Station, its outline and process to beginning of stoppage of generation, conditions from the stoppage to beginning of its abolishment measure, outline on its abolishment plan, performing conditions on its abolishment measure, safety security measures, processing and disposition of wastes, and technical development. (G.K.)

  7. Challenge for reconstruction of public confidence

    International Nuclear Information System (INIS)

    Matsuura, S.

    2001-01-01

    Past incidents and scandals that have had a large influence on damaging public confidence in nuclear energy safety are presented. Radiation leak on nuclear-powered ship 'Mutsu' (1974), the T.M.I. incident in 1979, Chernobyl accident (1986), the sodium leak at the Monju reactor (1995), fire and explosion at a low level waste asphalt solidification facility (1997), J.C.O. incident (Tokai- MURA, 1999), are so many examples that have created feelings of distrust and anxiety in society. In order to restore public confidence there is no other course but to be prepared for difficulty and work honestly to our fullest ability, with all steps made openly and accountably. (N.C.)

  8. Summary of the function and the safety design of the Tokai Reprocessing Utility Center

    International Nuclear Information System (INIS)

    Yanai, Chisato; Yamazaki, Toshihiko; Tomita, Tsuneo; Horii, Shinichi; Uryu, Mituru; Ishiguro, Nobuharu; Kobayashi, Kentarou

    1998-01-01

    The Tokai Reprocessing Utility Center is a new facility to replace the utilities to the Tokai Reprocessing Plant such as the emergency power supply, compressed air, etc. which are scattered about the site and have became superannuated. The Facility building has a base-isolation system that is a strongly resistant to earthquake. After completion, the center will supply utilities to the Main Plant, the Central Building, the Auxiliary Active Facility, etc. of the Tokai Reprocessing Plant. This document outlines the function and the safety design of the Tokai Reprocessing Utility Center. (author)

  9. Quantitative assessment of slit Mura defect in a thin film transistor-liquid crystal display based on chromaticity and optical density

    International Nuclear Information System (INIS)

    Tzu, Fu-Ming; Chou, Jung-Hua

    2010-01-01

    An innovative non-contact optical inspection method is developed to quantify slit Mura defects for thin film transistor–liquid crystal displays (TFT-LCDs). From the measurements of both chromaticity and optical densities across the slit Mura, the results indicate that the optical density profile is a concave shape and the chromaticity distribution is a convex shape. A linear relation with a negative slope exists between the chromaticity and optical density. A larger colour difference has a steeper slope, and vice versa. All of the measurements with uncertainties of a 99.7% confidence interval satisfy the requirements of the flat panel display industry. The proposed method can accurately quantify the pattern of blue slit Mura of TFT-LCDs; even the perceptibility is below the just noticeable difference

  10. Setting of cesium residual ratio of molten solidified waste produced in Japan Atomic Power Company Tokai and Tokai No.2 Power Stations

    International Nuclear Information System (INIS)

    2013-02-01

    JNES investigated the appropriateness of a view of the Japan Nuclear Fuel Co. on cesium residual content and the radioactivity measurement precision regarding the molten solidified (with lowered inorganic salt used) radioactive wastes which were produced from Japan Atomic Power Company Tokai and Tokai No. 2 Power Stations. Based on the written performance report from the request and past disposal confirmation experience, a view of the JNFC is confirmed as appropriate that setting of 15% cesium residual ratio for molten solidified with volume ratio larger than 4% and less than 10% cases. (S. Ohno)

  11. Proceedings of the 2006 symposium on nuclear data

    International Nuclear Information System (INIS)

    Hazama, Taira; Fukahori, Tokio

    2008-09-01

    The 2006 Symposium on Nuclear Data was held at RICOTTI at Tokai-mura, Ibaraki-ken, Japan, on 25th and 26th of January 2007, with about 80 participants. Nuclear Data Division of Atomic Energy Society of Japan organized this symposium with cooperation of North Kanto Branch of the society. In the oral sessions, presented were 6 papers on topics of nuclear data needs for the fission reactor developments and non-energy nuclear applications. In the poster session, presented were 16 papers concerning experiments, evaluations, benchmark tests, applications, and so on. Tutorials on nuclear data, which were for uses of covariance data and MVP code, were also done. Major part of those presented papers is compiled in this proceedings. (author)

  12. Fire and explosion incident at bituminization demonstration facility of PNC Tokai works, on march 11, 1997

    International Nuclear Information System (INIS)

    Miura, A.; Sato, Y.; Koyama, T.; Omori, E.; Kato, Y.; Suzuki, H.; Norjiri, I.; Yamanouchi, T.

    2001-01-01

    On March 11, a fire and explosion incident occurred at the Bituminization Demonstration Facility (BDF) of Tokai Reprocessing Plant in Power Reactor and Nuclear Fuel Development Corporation (PNC). Soon after the incident, PNC (now reorganized to JNC) started to investigate the facility damage, operational records around the incident, technical notes including facility design and reviews of R and D results, operators witness and to perform several analysis, tests and calculations. This paper describes outline and cause of the incident which were concluded based on the results of continuous serious investigation, analysis and calculation. (author)

  13. Instructions on the nuclear critical accident and how to correspond to future

    International Nuclear Information System (INIS)

    Kimura, Itsuro

    2000-01-01

    The nuclear accident occurred at Tokai Works of the JCO Co., Ltd. is a simple but disallowable one formed by neglecting possibility of nuclear fission chain reaction, one of three dangers specific to nuclear power facilities and by feeding middle concentrated uranium solution with more than critical mass into a precipitation tank. As a man consumed most of his life to nuclear power, it is to occur a critical accident forming about 50 previous examples in the world and about 10 victims at Tokai-mura the most earnestly promoting its experiment and analysis and to generate new victims, what was thought to be the most regrettable in this accident. How the previous experiences and results in Tokai-mura could be transmitted to the JCO Co., Ltd. ? This was a large alarm-bell for persons engaging to R and D on nuclear power. As this accident was much deplorable and apological for the common public, it must be carried out to thoroughly analyze its causes, to establish its future responses, and to promote its essential countermeasures. As it is important to open informations on its contents, it is hopeful not to over-exaggerate and over-differentiate the accident, to calmly and scientifically analyze the risk as well as in the other accidents, and to construct actually effective countermeasures. (G.K.)

  14. Annual report on the effluent control of low level liquid water in Tokai Works. FY2004

    International Nuclear Information System (INIS)

    Takeishi, Minoru; Miyagawa, Naoto; Watanabe, Hitoshi

    2005-08-01

    This report was written about the effluent control of low level liquid waste in JNC Tokai Works Fiscal Year 2004, from 1st April 2004 to 31th March 2005. In this period, the quantities and concentrations of radioactivity in liquid waste from Tokai Works were under the discharge limits of 'Safety Regulations for the Tokai Reprocessing Plant' and regulations of government. (author)

  15. Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

    Energy Technology Data Exchange (ETDEWEB)

    Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    Asignificant amount of operating experience has now been accumulated by boiling-water-reactor power plants. By the end of 1962, over 2200 million kWh of electricity have been generated by three plants operating on utility.system - Dresden Nuclear Power Station, Commonwealth Edison Company, Morris, Illinois; Vallecitos Atomic Power Plant, Pacific Gas and Electric Company and General Electric Company, Pleasanton, California; and Kahl Nuclear Power Station, Rheinisch Westfaelisches Elektrizitaetswerk and Bayernwerk, Kahl-am-Main, West Germany. Boiling-water-reactor power-plant performance, under routine electric-utility operating conditions, has been excellent. Reactor and plant availability and capacity factor provide a sound basis for anticipation of continuing reliable performance from boiling-water-reactor power stations. During 1963, four additional boiling-water-reactor plants will begin power operation: Big Rock Point Nuclear Plant, Consumers Power Company, Charlevoix, Michigan; Humboldt Bay Plant Nuclear Unit, Pacific Gas and Electric Company, Eureka, California; Garigliano Nuclear Power Station, Societa Elettronucleare Nazionale, Scauri, Italy; and Japan Power Demonstration Reactor, Japan Atomic Energy Research Institute, Tokai Mura, Japan. The start-up and initial operation of these plants confirms the expectation of reliable performance established by Dresden, Kahl, and Vallecitos. Performance records of Dresden, Kahl and Vallecitos have clearly proved the stability and safety of boiling-water reactors. Additionally, radiation levels within the plant and in the environs have been significantly below limits established by operating licences. Simplicity and ease of operation of boiling-water reactors has been confirmed. Load following characteristics of the Dresden dual-cycle boiling-water reactor have been excellent. Major and minor maintenance and repair work can be accomplished by ordinary craft unions, and without undue hardship or time limits caused by

  16. Tokai advanced safeguards technology exercise task T-F: study of selected capabilities needed to apply DYMAC principles to safeguarding the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Lowry, L.L.; Augustson, R.H.

    1979-10-01

    Selected technical capabilities needed to apply the DYMAC principles to safeguarding the Tokai reproprocessing plant are presented. The measurements needed to close the mass balance around the process line and the analysis methods for assessing the results were investigated. Process conditions at the Tokai plant were used when numerical values were needed to assist the analyis. A rationale is presented for the selection of instruments (x-ray fluorescence spectrometers, x-ray densitometers, and gamma-ray spectrometers) best suited to establishing plutonium concentrations and inventories in the feed tanks. The current state of the art in estimating inventory in contactors is reviewed and profitable directions for further work are recommended. A generalized performance surface has been developed that can measure the diversion sensitivity of the safeguard system when the instrument performance levels, the number of measurements made, and the false alarm probability are specified. An analysis of its application to the Tokai plant is given. Finally, a conceptual approach to the problem of IAEA safeguards verification is discussed. It appears possible that, in the process of verifying, the full power of the plant operator's safeguard system can be brought to the service of the IAEA

  17. Sociological aspects of 3.11 Fukushima Daiichi Accident aftermath and the Genshiryoku-mura (nuclear village, or pro-nuclear concession sector)

    Energy Technology Data Exchange (ETDEWEB)

    Sawada, T., E-mail: tetsuo@nr.titech.ac.jp [Tokyo Inst. of Technology, Research Laboratory for Nuclear Reactors, Meguro-ku, Tokyo (Japan)

    2014-07-01

    In the 3.11 Fukushima Daiichi Accident aftermath, information contamination induced societal confusion that led to unnecessarily grave fear among the public. The origins and development of the information contamination, and the labeling of Goyo-gakusha and Genshiryoku-mura were phenomenologically analyzed. The historical background to, and reasons for emergence of Goyo-gakusha's were examined by using an axiological approach. The analyses and examination have clarified a typical case of the origins to formation of Genshiryoku-mura. (author)

  18. Evaluation of the influences of nuclear accident by hedonic approach

    International Nuclear Information System (INIS)

    Takai, Toru

    2005-01-01

    The purpose of this sturdy is to examine the influences on residential land prices of criticality accident in Tokai-mura. To clarify the influences, three types of hedonic model are used to estimate land prices around JCO before and after the accident. The result of estimation indicates that land prices decreased according to proximity to JCO after the accident. (author)

  19. TASTEX: Tokai Advanced Safeguards Technology Exercise

    International Nuclear Information System (INIS)

    1982-01-01

    During the years 1978 to 1981 the Governments of France, Japan and the United States of America cooperated with the International Atomic Energy Agency in the TASTEX (Tokai Advanced Safeguards Technology Exercise) programme. The aim of this programme was to improve the technology for the application of international safeguards at reprocessing facilities, and the results are presented in the present report

  20. The extraction behavior of some noticeable nuclides in the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Yamanouchi, T.; Sasao, N.; Ozawa, M.; Yamana, H.

    1987-01-01

    The extraction behavior of some TRU nuclides and Ru-106 were investigated on the basis of the process analytical data obtained during this decade of the hot operation in the Tokai Reprocessing Plant. Some characteristics of their extraction behavior under Tokai-flowsheet became clear. They were explainable by the chemical features of these nuclides in conjunction with the chemical conditions of the process. Some extraction-simulation calculations were performed to supplement the understanding of their characteristic behaviors

  1. Levels of tritium concentration in the environmental samples around JAERI TOKAI

    International Nuclear Information System (INIS)

    Matsuura, K.; Sasa, Y.; Nakamura, C.; Katagiri, H.

    1995-01-01

    By the operation of research reactors, tritium-handling facilities, nuclear power plants, and a reprocessing facility around JAERI TOKAI, tritium is released into the environment in compliance with the regulatory standards. To investigate the levels of tritium concentration in environmental samples around JAERI, rain, air (vapor and hydrogen gas), and tissue-free water of pine needles were measured and analyzed from 1984 to 1993. Sampling locations were determined by taking into consideration wind direction, distance from nuclear facilities, and population distribution. The NAKA site (about 6 km west-northwest from the Tokai site) was also selected as a reference point. Rain and tissue-free water of pine needles were sampled monthly. For air samples, sampling was carried out for two weeks by using the continuous tritium sampler. After the pretreatment of samples, tritium concentrations were measured by a low background liquid scintillation counter (detection limit 0.8 Bq/l). Annual mean tritium concentrations in rain observed at six points for 10 years was 0.8 to 8.9 Bq/l, which decreased with distance from the nuclear facilities. Tritium concentrations in rain obtained at Chiba City were around 0.8 Bq/l (1987-1988) and those at the NAKA site were 0.8 to 3.8 Bq/l. Annual mean HTO concentrations in air at three points for 10 years were 9.2 x 10 -2 to 1.1 Bq/m 3 , although HT concentrations in air, ranging from 1.7 x 10 -2 to 5.8 x 10 -2 Bq/m 3 , were not influenced by the operation of the nuclear facilities. Annual mean tritium concentrations in tissue-free water of pine needles at four points for 10 years were 1.4 to 31 Bq/l. Those at the NAKA site ranging from 1.4 to 6.2 Bq/l were in good agreement with the reported value by Takashima of 0.78 to 3.0 Bq/l at twenty-one locations in Japan. Monthly mean HTO concentrations in air for 10 years showed a good correlation with absolute humidity, while other samples showed no seasonal variation. Higher level tritium

  2. Openness and transparency: the road to public confidence

    International Nuclear Information System (INIS)

    Jaczko, G.

    2007-01-01

    This workshop on transparency of Nuclear Regulatory Activities was held from 22 to 24 May 2007, in Tokyo and Tokai-Mura, Japan. The first session was devoted to clarifying the concept of transparency as used in the field of nuclear safety regulation. This document is the presentation of the chairman of the session and offers a global evaluation of the session. (A.L.B.)

  3. The neutron computer tomography

    International Nuclear Information System (INIS)

    Matsumoto, G.; Krata, S.

    1983-01-01

    The method of computer tomography (CT) was applied for neutrons instead of X-rays. The neutron radiography image of samples was scanned by microphotometer to get the transmission data. This process was so time-consuming that the number of incident angles to samples could not be increased. The transmission data was processed by FACOM computer and CT image was gained. In the experiment at the Japan Research Reactor No. 4 at Tokai-mura with 18 projection angles, the resolution of paraffin in the aluminum block was less than 0.8 mm. In the experiment at Van de Graaf accelerator of Nagoya University, this same resolution was 1.2 mm because of the angle distribution of neutron beam. This experiment is the preliminary one, the facility which utilizes neutron television and video-recorder will be necessary for the next stage. (Auth.)

  4. Development of engineering scale HLLW vitrification technique at PNC

    International Nuclear Information System (INIS)

    Nagaki, H.; Oguino, N.; Tsunoda, N.; Segawa, T.

    1979-01-01

    Some processes have been investigated to develop the technology of solidification of the high-level radioactive liquid waste generated from the nuclear fuel reprocessing plant operated by the Power Reactor and Nuclear Fuel Development Corporation (PNC) at Tokai-mura. This report covers the present state of development of a Joule-heated ceramic melter and a direct megahertz induction-heated melter. Engineering-scale tests have been performed with both melters. The Joule-heated melter could produce 45 kg or 16 liters of glass per hour. The direct-induction furnace was able to melt 5 kg or 1.8 liters of glass per hour. Both melters were composed of electrofused cast refractory brick. Thus it was possible to melt the glass at above 1200 0 C. Glass produced at higher melting temperatures is generally superior. 3 figures, 2 tables

  5. Report on planning of input earthquake vibration for design of vibration controlling structure, in the Tokai Works, Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    Uryu, Mitsuru; Shinohara, Takaharu; Terada, Shuji; Yamazaki, Toshihiko; Nakayama, Kazuhiko; Kondo, Toshinari; Hosoya, Hisashi

    1997-05-01

    When adopting a vibration controlling structure for a nuclear facility building, it is necessary to evaluate a little longer frequency vibration properly. Although various evaluation methods are proposed, there is no finished method. And, to the earthquake itself to investigate, some factors such as effect of surface wave, distant great earthquake, and so on must be considered, and further various evaluations and investigations are required. Here is reported on an evaluation method of the input earthquake vibration for vibration controlling design establishing on adoption of the vibration controlling structure using a vibration control device comprising of laminated rubber and lead damper for the buildings of reprocessing facility in Tokai Works. The input earthquake vibration for vibration controlling design shown in this report is to be adopted for a vibration controlling facility buildings in the Tokai Works. (G.K.)

  6. Remote repair and inspection technics in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Koyama, Kenji; Ishibashi, Yuzo; Otani, Yosikuni

    1986-01-01

    Tokai reprocessing plant of Power Reactor and Nuclear Fuel Development Corp. is the only factory in Japan which treats 0.7 t/day of the spent fuel from LWR power stations and recovers remaining uranium and newly produced plutonium. Since the reprocessing plant started the hot test in September, 1977, about eight years have elapsed, and 233 t of spent fuel was treated as of August, 1985. During this period, the development of various remote working techniques have been carried out to cope with the failure of equipment and to strengthen the preventive maintenance of equipment. In this report, the development of the techniques for the remote repair of leaking dissolving tanks and the development of the remote inspection system for confirming the soundness of equipment in cells are described. In nuclear facilities, from the viewpoint of the reduction of radiation exposure accompanying the works under high radiation, labor saving, the increase of capacity factor by shortening the period of repair works, the improvement of safety and reliability of the facilities by perfecting checkup and inspection and so on, it is strongly desired to put robots in practical use for maintenance and inspection. (Kako, I.)

  7. Collaboration of nuclear knowledge. Execution of science partnership project promoted by MEXT and repercussion effect obtained from the viewpoint of intellectual collaboration

    International Nuclear Information System (INIS)

    Yanagisawa, Kazuaki; Nagasawa, Naotsugu; Sasagawa, Sumiko; Nakano, Koji

    2007-09-01

    The Fujioka Technical High School (FTHS) applied to the Science Partnership Project (SPP-2006), which was financially supported by the MEXT and promoted by the Japan Science and Technology Agency, and was approved the proposal entitled as 'Nuclear Technology and Its Future for Nuclear-Cite Neighboring Students'. FTHS decided to make intellectual linkage with Takasaki Branch, Japan Atomic Energy Agency (JAEA) and with Institute for Environmental Sciences, having with the following 5 menus. 1. Outline of nuclear energy. 2. Outline of radiation application and experimental practice. 3. Radiation and health for understanding the natural radiation and radioactivity. 4. Sightseeing of nuclear facilities around Tokai-mura. 5. Reporting of SPP activities. Adding to normal lectures listed above, the authors made several educational trials from the viewpoint of intellectual linkage. First is to verify the change of interest in students through lectures on nuclear, second is to reveal that which nuclear fields are interested by a majority of students, third is to make direct comparison of intellectual ability between the students and 5 specialists. Resultantly, if one teaches correctly the basic concept of nuclear energy and radiation application as learning inputs, aparting from his mind to nuclear and understanding ability of student increased 3 times than his background level. A comprehensive faculty of the students to the 5 specialists is 1/5 before making lecture but increased markedly to 1/2 after the lecture. A majority of students understand the matter of reprocessing, reactor accidents and food irradiation but understand poorly the location and name of the commercial nuclear power plant as well as the basic function of the power reactors. The latter is however recovered by the sightseeing of commercial power plants and fuel fabrication facilities located around Tokai-mura. Namely, to seeing is to believing. To teach a radiation application and a basic idea of nuclear

  8. Case law and administrative decisions

    International Nuclear Information System (INIS)

    2003-01-01

    Some extracts of case law: ruling of the Supreme Administrative Court on the decision to shut units 3 and 4 of Kozloduy nuclear power plant (Bulgaria), judgement of the County Court of Cherbourg concerning the import of spent fuel to La Hague (France), judgement of the Nagoya High Court on the invalidity of the licence to establish the Monju reactor, judgement of the Mito District Court issuing penalties in respect of the Tokai-Mura accident, the Principle of justification: the application of the Principle to the Manufacture of MOX fuel in the UK, Ruling of the US Court of International trade in relation to the sale of uranium enrichment services in the United States, Commission v Council Accession of the Community to the Convention on nuclear safety, government decision not to appeal court ruling on the continued operation of the Borssele nuclear power plant. (N.C.)

  9. The annal of british RPV steel plates for first nuclear power station in Japan (1). Unforseen accidents araised before nuclear power plant open

    International Nuclear Information System (INIS)

    Miyoshi, Shigeru

    2011-01-01

    This article described the author's experiences of reactor vessel steel plates for the first nuclear power station, Tokai-mura reactor. The station is an advanced Calder Hall type. The electrical output is 166 MWe. The reactor vessel was spherical with internal diameter of 189 cm and wall thickness of 83 mm. Material was a fine-grain, aluminum-killed steel. Each part of pressure vessel, bottom cap, belt 1, 2, 3, 4 and top cap, were prefabricated with welding of plates, then lifted into the reactor building and assembled with welding. Steel plates were imported from UK, press formed to spherical segments in Japan and transferred to the site. Ultrasonic testing, magnetic particle testing of groove face (crack detection), sizing of groove and sulfur print tests were performed as an on-site acceptance testing. Inclusions and lamination openings were observed at groove faces due to gas flame cutting. White spot was observed at rupture face of tensile test specimen. At the liquid penetration testing after back gauging of extra seam, a crack-like indication with length of less than 3 mm was observed. Reexamination of groove face by magnetic particles testing showed indications of inclusion cloud or alumina cloud. These would be cracks caused by hydrogen embrittlement. (T. Tanaka)

  10. Survey of secular change for the buildings of nuclear fuel facility in JNC Tokai Works

    International Nuclear Information System (INIS)

    Uryu, Mitsuru; Kyue, Tadashi; Satoko, Hiroyuki; Yamazaki, Toshihiko

    2002-06-01

    Some nuclear facilities of JNC such as Tokai Reprocessing Plant or Tokai Plutonium Fuel plant have been operating over 20 years since their completion. These facilities' buildings are constructed near the seaside, so we are that, we are surveying the secular change, estimating the tendency and counterplan to operate the facilities stably. In this paper, we report the abstract of the result of the survey, and the maintenance stage of the diagnostic techniques etc. (author)

  11. Comparison of nuclear safety research reactor (TRIGA-ACPR) performance with analytical prediction

    International Nuclear Information System (INIS)

    West, G.B.; Whittemore, W.L.

    1976-01-01

    The NSRR was taken critical on June 30, 1975 at the Japan Atomic Energy Research Institute - Tokai-mura, Japan. Following initial core loading and control rod calibration, a series of pulsing tests was performed to characterize the performance of the reactor. A comparison has been made of performance parameters actually measured in the 157 element core versus predicted values based upon design analyses. The nuclear parameters measured were quite close to prediction. A $4.70 pulse produced a minimum period of 1.12 msec, a peak power of 20,500 MW and yielded a prompt energy release of 103 MW-sec. Pulse tests with experimental UO 2 fuel pins in the central irradiation cavity have produced 320 cal/gm, averaged at the axial center of 10% enriched UO 2 , for a 100 MW-sec pulse. The pulse rods for the NSRR contain B 4 C enriched to about 93 percent in Boron-10 in order to achieve maximum design performance with only three pulse rods. The total worth for the three transient rods was measured to be about $5.05 (vs $5.07 calculated for the 165 element core), thus verifying the effectiveness of the Boron-10 enrichment to achieve the desired result. Analysis of fuel temperature measurements made in the NSRR show that, for fuel temperatures produced during pulsing greater than 900 deg. C, heat transfer in the 0.010-inch gap between fuel and clad is enhanced by the minor outgassing of hydrogen which is characteristic of that temperature region. The hydrogen is normally all reabsorbed within about 100 sec of maximum temperature, at which time the heat transfer is characteristic of air (or argon) in the gap. In some of the temperature-instrumented elements, however, all of the hydrogen was not reabsorbed and as a result these elements gave significantly lower temperatures for high power steady state operation than were recorded prior to pulsing. In general, the NSRR parameters measured during startup were quite close to analytical prediction and the overall performance of the

  12. Present state of the monitoring for internal contamination at Tokai Research Establishment, Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Akaishi, J.; Fukuda, H.; Mizushita, S.

    1980-01-01

    At Tokai Research Establishment, JAERI, over one thousand people work in hot areas such as reactors, accelerators, chemical laboratories and waste treatment plants. The monitoring for internal contamination of this personnel is presented. Routine and special monitoring are carried out. The object of the former is to check for the presence of significant contamination, and that of the latter is to estimate body burden and committed dose equivalent, if necessary. Heavy shield and shadow shield whole body counters, a low energy lung counter and a wound monitor are used to detect the internal contamination due to γ or chi ray emitters, and bioassay technique is used for α or β emitters and uranium. The results of the monitoring until now are presented. (H.K.)

  13. A JNFL - COGEMA cooperation. Focus on the uranium tests of the Rokkasho mura Reprocessing Plant

    International Nuclear Information System (INIS)

    Griffon, Jean-Paul; Ohtou, Yoshihiro

    2005-01-01

    Description of a new type of cooperation for the start-up of the Rokkasho-mura Reprocessing Plant. After recalling the background of this cooperation the paper describes its main features: training on a sister plant and in RRP facilities, on site assistance backed-up by a dedicated team having full access to the sister plant information from the design stage to actual operations. (author)

  14. Operating document on management division waste management section in Tokai works in the 2002 fiscal year. Document on present of affairs

    International Nuclear Information System (INIS)

    Kobayashi, Kentarou; Isozaki, Kouei; Akutu, Shigeru; Nakanishi, Masahiro; Ozone, Takashi; Terunuma, Tomomi

    2003-04-01

    This document is announced about task of Waste Management Division Waste Management Section in the 2002 fiscal year. Mainly, our task is that treated Low level solid waste, stored Low level solid waste and stored High level solid waste. Those wastes are generated from Tokai reprocessing plant in Tokai Works. We carried out task safely as planned. The results are as follows. (1) We incinerated that combustible Low level solid waste of 70.5 ton in Incinerate facility. Such wastes were generated from operation of Tokai reprocessing plant and cleaned up operation of Tokai bituminization facility (The fire and explosion incident of Tokai bituminization facility). (2) We stored Low level solid waste that generated the waste of 1,071 drums. It is found that Storage facilities will not fill on this condition Low level radioactive waste treatment facility is started operation. (3) We stored High level solid waste that generated the waste of 117 drums from Tokai reprocessing plant. And, it is found that there facilities will not fill on this condition generated wastes of about 100 drams by a year. (4) We started printing of the data from the 2002 fiscal year to intranet which amount of stored Low level solid waste and High level solid waste in order to educate-the amount reduction of waste generating (at those facilities). (author)

  15. Application of Whole Body Counter to Neutron Dose Assessment in Criticality Accidents

    Energy Technology Data Exchange (ETDEWEB)

    Kurihara, O.; Tsujimura, N.; Takasaki, K.; Momose, T.; Maruo, Y. [Japan Nuclear Cycle Development Institute, Tokai (Japan)

    2001-09-15

    Neutron dose assessment in criticality accidents using Whole Body Counter (WBC) was proved to be an effective method as rapid neutron dose estimation at the JCO criticality accident in Tokai-mura. The 1.36MeV gamma-ray of {sup 24}Na in a body can be detected easily by a germanium detector. The Minimum Detectable Activity (MDA) of {sup 24}Na is approximately 50Bq for 10minute measurement by the germanium-type whole body counter at JNC Tokai Works. Neutron energy spectra at the typical shielding conditions in criticality accidents were calculated and the conversion factor, whole body activity-to-organ mass weighted neutron absorbed dose, corresponding to each condition were determined. The conversion factor for uncollied fission spectrum is 7.7 [(Bq{sup 24}Na/g{sup 23}Na)/mGy].

  16. Report of meteorological observations in site of Tokai Research Establishment in 1971

    International Nuclear Information System (INIS)

    1978-05-01

    Covered are the meteorological observations from January to December 1971 in Tokai Research Establishment as monthly summaries, including daily and hourly mean wind speeds, frequencies of wind directions and atmospheric stability. (auth.)

  17. Present state of the monitoring for internal contamination at Tokai Research Establishment, Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Akaishi, J.; Fukuda, H.; Mizushita, S.

    1980-01-01

    Results are presented of internal contamination surveys carried out since 1969 at Tokai Research Establishment. Routine monitoring sometimes revealed significant internal contamination for tritium workers, but almost never for others. The number of subjects for special monitoring varied according to the activities. In 1965, the number of subjects for special monitoring was nearly 300, due to a reactor repair that year. In recent years, the number or special monitoring has been several tens or so. With regard to special monitoring, the workers with significant internal contamination were less than 50%. The internal dose (50 years) estimated for the majority of subjects was of mrem order. During the past 15 years, only several cases of exposure of rem order were found. The highest dose experienced was about 4 rems ( 131 I thyroid) (U.K.)

  18. Radiation dose registration and epidemiological study for workers of nuclear institutions in Japan

    International Nuclear Information System (INIS)

    Kumatori, T.

    1992-01-01

    The first nuclear reactor was operated in 1957 at Tokai-mura in Japan. Since then radiation dose of workers has been controlled by nuclear institutions according to the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors. However, many nuclear power plants and other nuclear facilities were built, resulting in the remarkable increase of workers in controlled areas. Further, periodical inspection and repair work at nuclear facilities were carried out by employees of subcontractors, who were engaged in such work at many different facilities, so that it was getting more and more difficult to obtain accurate information of radiation dose on these workers. In order to meet this situation, the open-quotes Radiation Dose Registration Center for Workersclose quotes (RADREC) was established in November 1977 within the open-quotes Radiation Effects Associationclose quotes (REA), which was founded in September 1960 for the purpose of supporting the research on radiation effects and radiation protection. In January 1978, RADREC was designated by the Government as an organization to preserve the records on exposure of radiation workers, which was linked up with the registration system

  19. Criticality management of Tokai reprocessing facility

    Energy Technology Data Exchange (ETDEWEB)

    Nojiri, Ichiro [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

    2001-01-01

    In fuel cycle centers a number of equipment and vessels of various types and of complex design are used in several processes, i.e. dissolution of spent fuels, separation and storage of uranium and plutonium from fission products and transuranium elements. For each processes, Monte Carlo codes are frequently applied to manage the fuel criticality. Safety design depends largely on specific features of each facilities. The present report describes status of criticality management for main processes in Tokai Reprocessing Facility, JNC, and the criticality conditions specifically existing there. The guiding principle throughout consists of mass control, volume control, design (form) control, concentration control, and control due to employment of neutron poisons. (S. Ohno)

  20. Practice of producing cement packages for sea dumping and their quality control in Tokai Research Establishment, JAERI

    International Nuclear Information System (INIS)

    Hattori, Yoshiro; Fujisaki, Setsuo; Usami, Jun; Morishita, Satoru; Komatsu, Shigeru

    1980-07-01

    The production of cement packages for the exploratory sea dumping has been carried out at Waste Disposal and Decontamination Section, Tokai Research Establishment, JAERI. And around 1,000 packages were completed until 1979. The production practice were conducted based on NEA guideline and domestic regulation. In order to meet the guideline and regulation, consistent quality control is necessary to the production procedure. This Report describes about the procedure and quality control that were practiced from 1977 to 1979 in Tokai Research Establishment. (author)

  1. Tokai Advanced Safeguards Technology Exercise (TASTEX). An experience in international co-operation on safeguards

    International Nuclear Information System (INIS)

    Fukuda, G.; Koizumi, T.; Higuchi, K.

    1983-01-01

    TASTEX stands for Tokai Advanced Safeguards Technology Exercise, and was the joint programme of Japan, the United States of America, France and the International Atomic Energy Agency for developing, testing and evaluating advanced safeguards technology to be used in reprocessing facilities. The TASTEX programme, which started early in 1978 and successfully ended in May 1981, consisted of thirteen safeguards-technology-related tasks, from Task A to M. They were classified into four groups from the viewpoints of their usefulness and effectiveness: (1) Tasks technically feasible for international safeguards application in the near future: Tasks E, G, H and part of Task A (underwater CCTV and monitoring cameras); (2) Tasks which can be used in the future if research and development are continued: Tasks F, I, J, C and the other part of Task A (exclusive of the themes shown in (1)); (3) Tasks which may be used in future at the Tokai Reprocessing Facility if research and development are continued: Tasks K and L; and (4) Tasks which are difficult to be used at the Tokai Reprocessing Facility: Tasks B, D and M. The tasks classified under Group (1) are being developed further as part of the JASPAS (Japan Support Programme for Agency's Safeguards) project. (author)

  2. Abstracts of the Mini-Symposium on Stability and Bifurcation in Fluid Motions September 9-10, 1994, Tokai, Japan

    International Nuclear Information System (INIS)

    Fujimura, Kaoru

    1995-01-01

    This is the abstracts of the Mini-Symposium on Stability and Bifurcation in Fluid Motions held on September 9-10, 1994 at the Tokai Establishment of JAERI and the Tokai Kaikan. Sixteen talks were given on various important subjects related with stability and bifurcation phenomena in fluids. All of them are theoretical and numerical analyses involving linear stability analysis, weakly nonlinear analysis, bifurcation analysis, and direct computation of nonlinearly equilibrium solutions. (author)

  3. Abstracts of the Mini-Symposium on Stability and Bifurcation in Fluid Motions September 9-10, 1994, Tokai, Japan

    Energy Technology Data Exchange (ETDEWEB)

    Fujimura, Kaoru [ed.; Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1995-01-01

    This is the abstracts of the Mini-Symposium on Stability and Bifurcation in Fluid Motions held on September 9-10, 1994 at the Tokai Establishment of JAERI and the Tokai Kaikan. Sixteen talks were given on various important subjects related with stability and bifurcation phenomena in fluids. All of them are theoretical and numerical analyses involving linear stability analysis, weakly nonlinear analysis, bifurcation analysis, and direct computation of nonlinearly equilibrium solutions. (author).

  4. The compensation of damage in Germany following the Chernobyl accident

    International Nuclear Information System (INIS)

    Eich, W.

    2003-01-01

    In the framework of the workshop on the indemnification of damage in the event of a nuclear accident, this paper presents the proceeding of the the discussion on the compensation of damage in Germany following the Chernobyl accident. This paper presents also the national experiences and opinions, a documentation of the Federal Office of Administration on the topic, the example of Tokai-mura accident third party liability and compensation and the third party liability in the field of nuclear law in Ireland. (A.L.B.)

  5. Activity report on the utilization of research reactors. Japanese fiscal year, 2002

    International Nuclear Information System (INIS)

    2004-08-01

    During the fiscal year 2002, the Tokai Research Establishment research reactors carried out 7 cycles of joint use reactor operation at JRR-3 and 39 cycles at JRR-4. The research reactors are being utilized for various purposes including experimental studies such as neutron scattering, prompt gamma analysis, neutron radiography and medical irradiation (BNCT), and irradiation utilization such as neutron activation analysis of various samples, Irradiation Test of Reactor Materials and fission track. This volume contains 279 activity reports, which are categorized into the fields of neutron scattering (9 subcategories), neutron radiography, neutron activation analysis, reactor materials, prompt gamma analysis, and others, submitted by the users in JAERI and from other organizations. (author)

  6. Activity report on the utilization of research reactors. Japanese fiscal year, 2003

    International Nuclear Information System (INIS)

    2005-09-01

    During the fiscal year 2003, the Tokai Research Establishment research reactors carried out 8 cycles of joint use reactor operation at JRR-3 and 42 cycles at JRR-4. The research reactors are being utilized for various purposes including experimental studies such as neutron scattering, prompt gamma analysis, neutron radiography and medical irradiation (BNCT), and irradiation utilization such as neutron activation analysis of various samples, Irradiation Test of Reactor Materials and fission track. This volume contains 246 activity reports, which are categorized into the fields of neutron scattering (9 subcategories), neutron radiography, neutron activation analysis, reactor materials, prompt analysis, and others, submitted by the users in JAERI and from other organizations. (author)

  7. Estimation of the spatiotemporal evolution of slow slip events in the Tokai region, central Japan, during 1994 - 2016 using GNSS data

    Science.gov (United States)

    Sakaue, H.; Nishimura, T.; Fukuda, J.; Kato, T.

    2017-12-01

    In the Tokai region, central Japan, the long-term slow slip events (L-SSEs) observed on the subducting Philippine Sea Plate (PSP) from 2000 to 2005 and since 2013. Moreover, many short-term slow slip events (S-SSEs) have been observed in the Tokai region since 1996. Sakaue et al. (2017) reported that the spatiotemporal evolution of an L-SSE and S-SSEs on the PSP beneath the Tokai region from 2013 to 2015. This study is probably the first case that migration of slip for S-SSE (Mw GPS Research) in the Tokai region. It is well known that GNSS time series have many systematic signals that do not result from SSEs. These systematic signals include, for example, seasonal variations, cosiesmic and post-seismic deformation of the 2004 off Southeast Kii Peninsula eqrthquake and the 2011 Tohoku-oki earthquake (Mw. 9.0), crustal deformation of volcanic activity on Miyake-jima island and so on. After removing these systematic signals, we applied a modified Network Inversion Filter (NIF) [Fukuda et al., 2008]. The original NIF [Segall & Matthews, 1997] assumes a constant hyperparameter for the temporal smoothing of slip rates and thus often results in oversmoothing of slip rates. The modified NIF assumes a time-variable hyperparameter, so that changes in slip rates are effectively extracted from GNSS time series.The results indicate that not only the spatiotemporal evolutions of the 2000 Tokai L-SSE and the 2013 L-SSE but also the spatiotemporal evolution of S-SSEs are estimated. We will present a comparison of the spatiotemporal evolutions between the 2000 Tokai L-SSE and the 2013 L-SSE and possible dependence of the occurrence style of S-SSEs on the occurrence of the L-SSEs.

  8. Research and development activities for reactor decommissioning. Developing technology of Fuji Electric Co., Ltd

    International Nuclear Information System (INIS)

    Shirakawa, Masahiro; Takaya, Jyunichi; Mizukoshi, Seiji; Hosoda, Hiroshi; Tomizuka, Chiaki; Funaguchi, Susumu; Ito, Katsuhito

    1997-01-01

    Fuji Electric Co., Ltd. is conducting decommissioning R and D for commercial reactor, especially for gas cooled reactor since the construction of the Tokai-1 power station of JAPCO, in the field of system engineering, residual radioactivity evaluation, dismantling of core internals, remote handling, treatment and disposal of radioactive waste, and radioactivity measurement. These R and D have been performed mainly under contract of JAPCO and JAERI. This paper gives a summary of the present status and future plan concerning technical development for decommissioning of nuclear reactor by Fuji Electric Co., Ltd. (author)

  9. Criticality safety evaluation in Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Shirai, Nobutoshi; Nakajima, Masayoshi; Takaya, Akikazu; Ohnuma, Hideyuki; Shirouzu, Hidetomo; Hayashi, Shinichiro; Yoshikawa, Koji; Suto, Toshiyuki

    2000-04-01

    Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 'Criticality safety of single unit' in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units. (author)

  10. Proceedings of the international symposium NUCEF 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-08-01

    Japan Atomic Energy Research Institute (JAERI) held the international symposium NUCEF 2005 at Techno Community Square RICOTTI in Tokai-mura on February 9 and 10, 2005. This symposium was co-organized by Japan Nuclear Cycle Development Institute (JNC), and Nuclear Fuel Cycle Safety Research Committee authorized the program. Two hundred thirty-nine participants from 11 countries presented fifty-nine papers, and discussed recent research activities and its outputs on waste disposal safety, fuel cycle facility safety including criticality safety, and separation process development. The presented papers are compiled in the proceedings. (author)

  11. K-edge densitometer (KED)

    Energy Technology Data Exchange (ETDEWEB)

    Sprinkle, J.K.; Hansen, W.J.

    1993-02-11

    In 1979, a K-edge densitometer (KED) was installed by the Safeguards Assay group from Los Alamos National Laboratory in the PNC reprocessing plant at Tokai-mura, Japan. It uses an active nondestructive assay technique, KED, to measure the plutonium concentration of the product solution. The measurement uncertainty of an assay depends on the count time chosen, but can be 0.5% or better. The computer hardware and software were upgraded in 1992. This manual describes the operation of the instrument, with an emphasis on the user interface to the software.

  12. Proceedings of the 1st symposium on advanced science research

    International Nuclear Information System (INIS)

    1995-09-01

    The 1st symposium on advanced science research was held in Tokai-mura, Ibaraki-ken, on 23-24 March, 1995, under the auspices of JAERI. Two hundred and sixty scientists attended the symposium; over 40% of the attendants were from universities and laboratories outside JAERI. This proceedings consists of 6 oral presentations of the research activities in the Advanced Science Research Center, 70 poster presentations on the field of basic science from both the inside and outside of JAERI and 2 panel discussions on the actinide physics and biocrystallography. (author)

  13. Major earthquake of Friday March 11, 2011, magnitude 8.9 at 5:46 UT, off Honshu island (Japan)

    International Nuclear Information System (INIS)

    2011-01-01

    On Friday March 11, 2011, at 5:46 UT (2:46 PM local time), a magnitude 8.9 earthquake took place at 80 km east of Honshu island (Japan). The earthquake affected a large part of the Honshu territory and led to the automatic emergency shutdown of all nuclear power plants of the east coast. This paper recalls first the seismo-tectonic and historical seismic context of the Japan archipelago and the first analyses of the Tohoku earthquake impact on nuclear facilities. At the time of publication of this information report, no radioactive release in the environment and no anomaly at the Tokai-Mura and Rokkasho-Mura sites were mentioned. However, the evacuation of populations in a 3 to 10 km area around the Fukushima-Dai-ichi power plant had been ordered by the Governor as preventive measure, which made one think that the situation at this specific site was particularly worrying. (J.S.)

  14. Major earthquake of Friday March 11, 2011, magnitude 8.9 at 5:46 UT, off Honshu island (Japan); Seisme majeur au large de l'Ile d'Honshu (Japon) du vendredi 11 mars 2011 Magnitude = 8,9 a 5h46 (TU)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    On Friday March 11, 2011, at 5:46 UT (2:46 PM local time), a magnitude 8.9 earthquake took place at 80 km east of Honshu island (Japan). The earthquake affected a large part of the Honshu territory and led to the automatic emergency shutdown of all nuclear power plants of the east coast. This paper recalls first the seismo-tectonic and historical seismic context of the Japan archipelago and the first analyses of the Tohoku earthquake impact on nuclear facilities. At the time of publication of this information report, no radioactive release in the environment and no anomaly at the Tokai-Mura and Rokkasho-Mura sites were mentioned. However, the evacuation of populations in a 3 to 10 km area around the Fukushima-Dai-ichi power plant had been ordered by the Governor as preventive measure, which made one think that the situation at this specific site was particularly worrying. (J.S.)

  15. Annual report on the environmental radiation monitoring around Tokai Reprocessing Plant. FY 2001. Document on present state of affairs

    International Nuclear Information System (INIS)

    Shinohara, Kunihiko; Takeishi, Minoru; Miyagawa, Naoto

    2002-06-01

    Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on ''Safety Regulations for the Tokai Reprocessing Plant, Chapter IV - Environmental Monitoring''. This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant during April 2001 to March 2002. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant. (author)

  16. Evaluation on maintenance technology developed in Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Yamamura, Osamu

    2008-01-01

    Tokai reprocessing plant (TRP) has been processing 1,140 tons of spent fuels, including 29tons of Fugen MOX fuels, since the beginning of its active operation in Sept.1977. For 30 years operation of TRP, many technological problems have been overcome to obtain the stable and reliable operation. This knowledge of maintenance technology could contribute to the safety and stable operation of Rokkasho reprocessing plant (RRP), as well as to the design and construction of the next reprocessing plant. (author)

  17. 30 years of experience in safe transportation of nuclear materials

    International Nuclear Information System (INIS)

    Kaneko, K.

    2004-01-01

    In April 2003, Nuclear Fuel Transport Co., Ltd. (NFT) marked the 30 th anniversary of its founding. NFT was established in 1973 and in 1978, commenced SF transport to the reprocessing plant in Tokai-mura. And then, after making preparations to transport nuclear materials to the various facilities at the Nuclear Fuel Cycle Center in Rokkasho-mura, NFT successfully started transportation of LLW (low level waste) to Rokksho-mura's LLW disposal center in 1992, domestic land transportation of HLW returned from overseas to the HLW storage center in 1995, domestic land transportation of natural hexafluoride delivered from overseas to the uranium enrichment plant in 1996, and transportation of SF to the reprocessing plant in 2000. NFT has realized an annual SF transportation capacity of 300 MTU and is currently making great company wide efforts to meet the Rokkasho Reprocessing Plant's future SF annual reprocessing capacity of 800MTU. At the end of FY2003, NFT had successfully transported 560 casks (about 1,730 MTU) of SF in more than 200 voyages in total, about 160,000 drums of LLW in around 100 voyages in total. This paper introduces the record of safe transport and its experience over the past 30 years and prospect for future transport business

  18. 30 years of experience in safe transportation of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Kaneko, K. [Nuclear Fuel Transport Co., Ltd., Tokyo (Japan)

    2004-07-01

    In April 2003, Nuclear Fuel Transport Co., Ltd. (NFT) marked the 30{sup th} anniversary of its founding. NFT was established in 1973 and in 1978, commenced SF transport to the reprocessing plant in Tokai-mura. And then, after making preparations to transport nuclear materials to the various facilities at the Nuclear Fuel Cycle Center in Rokkasho-mura, NFT successfully started transportation of LLW (low level waste) to Rokksho-mura's LLW disposal center in 1992, domestic land transportation of HLW returned from overseas to the HLW storage center in 1995, domestic land transportation of natural hexafluoride delivered from overseas to the uranium enrichment plant in 1996, and transportation of SF to the reprocessing plant in 2000. NFT has realized an annual SF transportation capacity of 300 MTU and is currently making great company wide efforts to meet the Rokkasho Reprocessing Plant's future SF annual reprocessing capacity of 800MTU. At the end of FY2003, NFT had successfully transported 560 casks (about 1,730 MTU) of SF in more than 200 voyages in total, about 160,000 drums of LLW in around 100 voyages in total. This paper introduces the record of safe transport and its experience over the past 30 years and prospect for future transport business.

  19. Application of the basic concepts of dynamic materials accountancy to the Tokai spent fuel reprocessing facilityssing facility

    International Nuclear Information System (INIS)

    Lovett, J.E.; Ikawa, Koji; Hirata, Mitsuho; Augustson, R.H.

    1980-11-01

    During 1978 and 1979 individuals from the International Atomic Energy Agency, the Los Alamos Scientific Laboratory, and the Japan Atomic Energy Research Institute investigated the feasibility of applying the basic concepts of dynamic materials accountancy to PNC-Tokai reprocessing facility in Japan. The system developed for Tokai requires weekly in-process physical inventories for the process MBA, and allows 2-3 additional days for completion of measurements and for data reduction and evaluation. The study concluded that such a system would be feasible, and recommended that an actual field test should be conducted as soon as feasible. (author)

  20. Design of the vitrification plant for HLLW generated from the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Vematsu, K.

    1986-01-01

    Power Reactor and Nuclear Fuel Development Corporation (PNC) is now designing a vitrification plant. This plant is for the solidification of high-level liquid waste (HLLW) which is generated from the Tokai Reprocessing Plant, and for the demonstration of the vitrification technology. The detailed design of the plant which started in 1982 was completed in 1984. At present the design improvement is being made for the reduction of construction cost and for the licensing which is going to be applied in 1986. The construction will be started in autumn 1987. The plant has a large shielded cell with low flow ventilation, and employs rack-mounted module system and high performance two-armed servomanipulator system to accomplish the fully remote operations and maintenance. The vitrification of HLLW is based on the liquid-fed Joule-heated ceramic melter process. The processing capacity is equivalent to the reprocessing of 0.7 ton of heavy metals per day. The glass production rate is about 9 kg/h, and about 300 kg of glass is poured periodically from the bottom of the melter into a canister. Produced glass is stored under the forced air cooling condition

  1. Radiological attacks and accidents. Medical consequences

    International Nuclear Information System (INIS)

    Sakuta, Hidenari

    2007-01-01

    Probability of the occurrence of radiological attacks appears to be elevated after the terrorist attacks against the United States on September 11 in 2001. There are a lot of scenarios of radiological attack: simple radiological device, radiological disperse device (RDD or dirty bomb), attacks against nuclear reactor, improvised nuclear device, and nuclear weapons. Of these, RDD attack is the most probable scenario, because it can be easily made and can generate enormous psychological and economic damages. Radiological incidents are occurring to and fro in the world, including several cases of theft to nuclear facilities and unsuccessful terrorist attacks against them. Recently, a former Russian spy has allegedly been killed using polonium-210. In addition, serious radiological accidents have occurred in Chernobyl, Goiania, and Tokai-mura. Planning, preparation, education, and training exercise appear to be essential factors to cope with radiological attacks and accidents effectively without feeling much anxiety. Triage and psychological first aid are prerequisite to manage and provide effective medial care for mass casualties without inducing panic. (author)

  2. Concentration of 7Be in the lower atmosphere and fallout rate in Tokai

    International Nuclear Information System (INIS)

    Amano, Hikaru; Kasai, Atsushi

    1981-01-01

    Beryllium-7, cosmic ray produced radioactivity, its monthly average concentration in the lower atmosphere and monthly fallout rate were measured in Tokai, Japan. Then, the monthly variations were compared with those of fission products due to nuclear detonations in the atmosphere. The concentration of 7 Be in the lower atmosphere ranged from 0.5 x 10 -1 pCi/m 3 to 2.5 x 10 -1 pCi/m 3 in Tokai between the observed period, 1975 - 1977. The fallout rate of 7 Be vibrated widely, its range was from the detection limits to 1.2 x 10 4 pCi/m 2 . The monthly variations were not always the same with variations of the fission products. Fallout rate of 7 Be depended on the rain strongly. The concentration of 7 Be in the rain was measured, too. Then the range was from 9.2 pCi/l to 1.9 x 10 2 pCi/l between the observed period 1976.9 - 1977.2. (author)

  3. Improvement of shearing machine in the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Takae, Akiyoshi; Otani, Yoshikuni

    1994-01-01

    The shearing machine in the Tokai Reprocessing Plant has been improved and refurbished through its operational experience for about 20 years. Every component except the shear housing and magazine is changed for improved things by PNC, while the shearing machine had been designed and fabricated originally by a French Company. The improvement of the shearing machine was carried out for the purpose of settling the problems which were experienced in the past operation, and improving durability, remote maintainability, and operability. The details of their improvement work are described. (author)

  4. Workshop of the JAEA-Tokai Tandem Accelerator. Memorial of 100,000-hour operation

    International Nuclear Information System (INIS)

    Ishii, Tetsuro; Osa, Akihiko

    2009-04-01

    Workshop of the JAEA-Tokai tandem accelerator has been held every two years. As a memorial of 100,000-hour operation of the tandem accelerator, we have organized the workshop focusing on the activity at this facility. This workshop covers developments and experiments carried out so far, together with experiments in progress and proposals in future. As previous series of workshops, we offered an opportunity to have active discussion among scientists in different fields including accelerator, nuclear physics, nuclear chemistry, radiation effects, atomic physics and so on, aiming at extending facility and research interactively. As a memorial lecture, we invited Dr. Akira Tonomura of fellow of Hitachi, Ltd, a distinctive scientist for development of electron holography. He delivered a lecture titled 'Structure of magnetic flux observed by electron beam'. He once used the tandem accelerator to induce columnar defects in high-temperature superconductor and studied vortices trapped along the defects. Prof. Shigeru Kubono of University of Tokyo, a chairman of program advisory committee of the tandem accelerator, encouraged us through a talk of 'Expectations for the JAEA-Tokai tandem accelerator'. This workshop was held at Advanced Science Research Center Building in Nuclear Science Research Institute on January 6th and 7th in 2009, having 24 oral presentations and 48 posters, and successfully carried out with as many as 120 participants and a lot of science discussions. This review is the collection of slides of oral presentations. The colored slides can be also found in the home page of the tandem accelerator facility (http://rrsys.tokai-sc.jaea.go.jp/rrsys/html/tandem/index.html). (author)

  5. Biological dose estimation for accidental supra-high dose gamma-ray exposure

    International Nuclear Information System (INIS)

    Chen, Y.; Yan, X.K.; Du, J.; Wang, Z.D.; Zhang, X.Q.; Zeng, F.G.; Zhou, P.K.

    2011-01-01

    To correctly estimate the biological dose of victims accidentally exposed to a very high dose of 60 Co gamma-ray, a new dose-effect curve of chromosomal dicentrics/multicentrics and rings in the supra-high dose range was established. Peripheral blood from two healthy men was irradiated in vitro with doses of 60 Co gamma-rays ranging from 6 to 22 Gy at a dose rate of 2.0 Gy/min. Lymphocytes were concentrated, cultured and harvested at 52 h, 68 h and 72 h. The numbers of dic + r were counted. The dose-effect curves were established and validated using comparisons with doses from the Tokai-mura accident and were then applied to two victims of supra-high dose exposure accident. The results indicated that there were no significant differences in chromosome aberration frequency among the different culture times from 52 h to 72 h. The 6-22 Gy dose-effect curve was fitted to a linear quadratic model Y = -2.269 + 0.776D - 7.868 x l0 -3 D 2 . Using this mathematic model, the dose estimates were similar to data from Tokai-mura which were estimated by PCC ring. Whole body average doses of 9.7 Gy and 18.1 Gy for two victims in the Jining accident were satisfactorily given. We established and successfully applied a new dose-effect curve of chromosomal dicentrics plus ring (dic + r) after 6-22 Gy γ-irradiation from a supra-high dose 60 Co gamma-ray accident.

  6. Modification in fuel processing of Mitsubishi Nuclear Fuel's Tokai Works

    International Nuclear Information System (INIS)

    1976-01-01

    Results of the study by the Committee for Examination of Fuel Safety, reported to the AEC of Japan, are presented, concerning safety of the modifications of Tokai Works, Mitsubishi Nuclear Fuel Co., Ltd. Safety has been confirmed thereof. The modifications covered are the following: storage facility of nuclear fuel in increase, analytical facility in transfer, fuel assemblage equipment in addition, incineration facility of combustible solid wastes in installation, experimental facility of uranium recovery in installation, and warehouse in installation. (Mori, K.)

  7. Proceedings of the specialists' meeting on reactor group constants

    Energy Technology Data Exchange (ETDEWEB)

    Katakura, Jun-ichi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-08-01

    This report is the Proceedings of the Specialists' Meeting on Reactor Group Constants. The meeting was held on February 22-23, 2001 at Tokai Research Establishment of Japan Atomic Energy Research Institute with the participation of 59 specialists. The evaluation work for JENDL-3.3 is going on for the publication in a short time. The processing JENDL-3.3 file to make reactor group constants is needed when it is used in application fields. In the meeting, the present status of the reactor group constants was reviewed and the issues relating to them were discussed in such fields as thermal reactor, criticality safety, fast reactor, high energy region, burn-up calculation and radiation shielding. At the final session in the meeting, standardization of reactor group constants was discussed and the need of the reference group constants was confirmed by the participants. The 11 of the presented papers are indexed individually. (J.P.N.)

  8. Annual report on the present state and activities of the radiation protection division, JNC Tokai Works in fiscal 2003

    International Nuclear Information System (INIS)

    2004-10-01

    This annual report summarizes the activities, such as radiation control in the radiation facilities, personnel monitoring, monitoring of gas and liquid waste effluents, environmental monitoring, instrumentation, safety research, and technical support, undertaken by the Radiation Protection Division at JNC Tokai Works in fiscal 2003. The major radiation facilities in the Tokai Works are the Tokai Reprocessing Plant (TRP), three MOX fuel fabrication facilities, the Chemical Processing Facility (CPF), and various other radioisotope and uranium research laboratories. The Radiation Protection Division is responsible for radiation control in and around these radiation facilities, including personnel monitoring, workplace monitoring, consultation on radiological work planning and evaluation, monitoring of gas and liquid waste effluents, environmental monitoring, instrumentation, calibration, quality assurance, and safety research. The Division also provides technical support and cooperation to other international and domestic institutes in the radiation protection field. In fiscal 2003, the results of radiological monitoring showed the situation to be normal, and no radiological incident or accident occurred. The maximum annual effective dose to radiation workers was 6.2 mSv and the mean annual effective dose was 0.1 mSv. Individual doses were kept within the annual dose limit specified in the safety regulations. The estimated effective dose caused by gas and liquid effluents form the TRP to members of the public around the Tokai Works was 4.2 x 10 -4 mSv. Environmental monitoring and effluent control were performed appropriately in compliance with safety regulation and standards. In addition, the various preparations were made for introduction of the quality assurance to regulation since fiscal 2004. (author)

  9. Impact of the Tokai reprocessing plant on the workers and on the surrounding environment

    International Nuclear Information System (INIS)

    Tago, I.

    1996-01-01

    The Tokai reprocessing plant began operation in September 1977 to establish oxide fuel reprocessing technology in Japan. Its designed capacity is about 0.7 metric tons of uranium per day. This report gives an example of the evaluation of the health and environmental aspects of a reprocessing plant. (author)

  10. Water electrolysis plants for hydrogen and oxygen production. Shipped to Tsuruga Power Station Unit No.1, and Tokai No.2 power station, the Japan Atomic Power Co

    International Nuclear Information System (INIS)

    Ueno, Syuichi; Sato, Takao; Ishikawa, Nobuhide

    1997-01-01

    Ebara's water electrolysis plants have been shipped to Tsuruga Power Station Unit No.1, (H 2 generation rate: 11 Nm 3 /h), and Tokai No.2 Power Station (H 2 generation rate: 36 Nm 3 /h), Japan Atomic Power Co. An outcome of a business agreement between Nissho Iwai Corporation and Norsk Hydro Electrolysers (Norway), this was the first time that such water electrolysis plants were equipped in Japanese boiling water reactor power stations. Each plant included an electrolyser (for generating hydrogen and oxygen), an electric power supply, a gas compression system, a dehumidifier system, an instrumentation and control system, and an auxiliary system. The plant has been operating almost continuously, with excellent feedback, since March 1997. (author)

  11. Environmental radiation monitoring system in Tokai and Oarai areas

    International Nuclear Information System (INIS)

    Morita, Shigeki

    1983-01-01

    In the Tokai and the Oarai areas there are total of seventeen enterprises, different in size and kind, connected with nuclear energy. Environmental monitoring is carried out in the cooperation of the Government, local governments and enterprises according to the plans by a prefectural monitoring committee. The purpose is in the following three aspects: (1) Estimation of the dose of general people, based on environmental radioactivity and released radioactivity data (2) Grasping the radioactive accumulation on long-terms (3) Detection of abnormal releases from the enterprises at an early stage. By environmental monitoring made thus far, no rise in environmental radioactivities due to the enterprises is indicated. (author)

  12. Local governments' roles of the compensation for damage by the Tokai JCO criticality accident

    International Nuclear Information System (INIS)

    Tanabe, Tomoyuki

    2003-01-01

    The Tokai JCO criticality accident on September 30, 1999 was the first case to which The Law on Compensation for Nuclear Damage was applied. Although the Law on Compensation for Nuclear Damage formulates the outline of the institutional framework for nuclear third party liability together with operator's insurance scheme, details of actual compensation procedure are not specified. By this reason, the compensation procedure in the Tokai accident had been executed without a concrete legal specification and a precedent. In spite of this situation, the compensation procedure with the accident led to an unexpectedly successful result. We observe the several reasons why the compensation procedure was implemented successfully despite the lack of concrete legal specification and a precedent. One of the reasons is that the local governments, Tokai Village and Ibaraki Prefecture, immediately took the leadership in implementing a temporary regime of compensation procedure without wasting time for waiting national government's directives. Upon practicing this compensation procedure, the local governments implemented the following steps. (1) Initial estimation of the amount and scope of damage. (2) Providing the criteria and heads of damage subject to compensation. (3) Unitary compensation procedure at the local levels. (4) Distribution of emergency payments for the victims. (5) Facilitating compensatory negotiation between the victims and JCO as arbitrator. However, some concerns are also pointed out about the fact that the local government directed the whole procedure without sufficient adjustment with the national government for compensation policy. Among all, in the compensation led by the local governments, it was difficult to guarantee fairness of compensation because victims who are influential on the local government such as industrial associations would have unfairly strong negotiation power in the compensatory negotiation, while the operator being responsible for the

  13. Accidents and failures in reactor facilities for test and research and reactor facilities in the stage of research and development in fiscal year 1987

    International Nuclear Information System (INIS)

    1988-01-01

    The number of accidents and failures reported in fiscal year 1987 in conformity with the law on the regulation of nuclear reactors and others was three. One case occurred during operation, and two cases occurred in shutdown state. One case was caused by improper construction management, and two cases were due to improper maintenance management. The effect of radioactivity to the surrounding environment of reactor facilities due to these accidents and failures did not arise. These occurred in the NSRR of Japan Atomic Energy Research Institute (Tokai), the experimental FBR Joyo and the ATR Fugen Power Station of Power Reactor and Nuclear Fuel Development Corp. In addition to these, the light troubles reported on the basis of the notice from the director of Science and Technology Agency dated September 1, 1981, were three cases. (K.I.)

  14. COGEMA Experience in Uranous Nitrate Preparation

    International Nuclear Information System (INIS)

    Tison, E.; Bretault, Ph.

    2006-01-01

    Separation and purification of plutonium by PUREX process is based on a sequence of extraction and back extraction which requires reducing plutonium Pu IV (extractable form) into Pu III (inextractable form) Different reducers can be used to reduce Pu IV into Pu III. Early plants such as that for Magnox fuel at Sellafield used ferrous sulfamate while UP 1 at Marcoule used uranous sulfamate. These reducers are efficient and easy to prepare but generates ferric and/or sulphate ions and so complicates management of the wastes from the plutonium purification cycle. Recent plants such as UP3 and UP2 800 at La Hague, THORP at Sellafield, and RRP at Rokkasho Mura (currently under tests) use uranous nitrate (U IV) stabilized by hydrazinium nitrate (N 2 H 5 NO 3 ) and hydroxyl ammonium nitrate (HAN). In the French plants, uranous nitrate is used in U-Pu separation and alpha barrier and HAN is used in Pu purification. Compared to sulfamate, U IV does not generate extraneous chemical species and uranyl nitrate (U VI) generated by reducing Pu IV follows the main uranium stream. More over uranous nitrate is prepared from reprocessed purified uranyl nitrate taken at the outlet of the reprocessing plant. Hydrazine and HAN offer the advantage to be salt-free reagents. Uranous nitrate can be generated either by electrolysis or by catalytic hydrogenation process. Electrolytic process has been implemented in early plant UP 1 at Marcoule (when changing reducer from uranous sulfamate to uranous nitrate) and was used again in UP2 plant at La Hague. However, the electrolytic process presented several disadvantages such as a low conversion rate and problems associated with the use of mercury. Electrolysis cells with no mercury were developed for the Eurochemic plant in Belgium and then implemented in the first Japanese reprocessing plant in Tokai-Mura. But finally, in 1975, the electrolytic process was abandoned in favor of the catalytic hydrogenation process developed at La Hague. The

  15. Annual report on the present state and activities of the radiation protection division, JNC Tokai Works in fiscal 2004

    International Nuclear Information System (INIS)

    2005-09-01

    This annual report summarizes the activities on radiation control in the radiation facilities, personnel monitoring, monitoring of gas and liquid waste effluents, environmental monitoring, instrumentation, safety research, and technical support, undertaken by the Radiation Protection Division at JNC Tokai Works in fiscal 2004. The major radiation facilities in the Tokai Works are the Tokai Reprocessing Plant (TRP), three MOX fuel fabrication facilities, the Chemical Processing Facility (CPF), and various other radioisotope and uranium research laboratories. The Radiation Protection Division is responsible for radiation control in and around these radiation facilities, including personnel monitoring, workplace monitoring, consultation on radiological work planning and evaluation, monitoring of gas and liquid waste effluents, environmental monitoring, instrumentation, calibration, quality assurance, and safety research. The Division also provides technical support and cooperation to other international and domestic institutes in the radiation protection field. In fiscal 2004, the results of radiological monitoring showed the situation to be normal, and no radiological incident or accident occurred. The maximum annual effective dose to radiation workers was 6.1 mSv and the mean annual effective dose was 0.1 mSv. Individual doses were kept within the annual dose limit specified in the safety regulations. The estimated effective dose caused by gas and liquid effluents from the TRP to members of the public around the Tokai Works was 4.4x10 -4 mSv. Environmental monitoring and effluent control were performed appropriately in compliance with safety regulation and standards. Research and development on radiation protection in nuclear fuel cycle are also performed actively. Safety audit and Nuclear Safety Inspection were made in accordance with the quality assurance system which had been introduced to safety regulation since fiscal 2004. (author)

  16. Some examples of the cavity filling along transportation routes above abandoned room and pillar lignite Mines in Tokai Region

    International Nuclear Information System (INIS)

    Sakamoto, A.; Yamada, N.; Sugiura, K.; Kawamoto, T.

    2005-01-01

    The authors describe the applications of the integrated cavity filling technique to abandoned lignite mines in Tokai region. These abandoned lignite mines were in operation until 1960's and the routes of Tokai By-Pass Expressway and the linear motor car railway line for Aichi Exposition pass over these abandoned mines. Since the size of abandoned mines were much larger than the route of the expressway and the elevated monorail, limited areas relevant to their stability had to be only filled. This article describe the details of cavity filling operations in these two projects, which may be some valuable examples for assessing the methods how to deal problems associated with mine closures in long term. (authors)

  17. Maintenance experiences at analytical laboratory at the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Suzuki, Hisanori; Nagayama, Tetsuya; Horigome, Kazushi; Ishibashi, Atsushi; Kitao, Takahiko; Surugaya, Naoki

    2014-01-01

    The Tokai Reprocessing Plant (TRP) is developing the technology to recover uranium and plutonium from spent nuclear fuel. There is an analytical laboratory which was built in 1977, as one of the most important facilities for process and material control analyses at the TRP. Samples taken from each process are analyzed by various analytical methods using hot cells, glove boxes and hume-hoods. A large number of maintenance work have been so far carried out and different types of experience have been accumulated. This paper describes our achievements in the maintenance activities at the analytical laboratory at the TRP. (author)

  18. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 2:00 PM status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on March 16, 2011, at 2:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of all 6 reactors of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  19. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 9:00 AM status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on March 16, 2011, at 9:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  20. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:00 PM status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on March 15, 2011, at 10:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  1. The program of international intercomparison of accident dosimetry; Le programme d'intercomparaison internationale de dosimetrie d'accident 10-12 juin 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-06-01

    The French institute of radioprotection and nuclear safety (IRSN) has carried out in June 2002 an international intercomparison program for the testing of the physical and biological accident dosimetry techniques. The intercomparison is jointly organized by the IRSN and the OECD-NEA with the sustain of the European commission and the collaboration of the CEA centre of Valduc (France). About 30 countries have participated to this program. Each country has supplied its own dosimeters and biological samples which have been irradiated using the Silene reactor of CEA-Valduc or a {sup 60}Co source. These experiments allow to test the new dosimetric techniques that have been developed since the previous intercomparison program (1993) and to confirm or improve the performances of older techniques. Aside from the intercomparison exercise, this report makes a status of the known radiological accidents and of the effects of high doses of ionizing radiations on human health (symptoms, therapeutics). It explains the phenomenology of criticality accidents, the prevention means, and the history of such accidents up to the Tokai-Mura one in 1999. Finally, the dosimetry of criticality is presented with its physical and biological techniques. (J.S.)

  2. Proceedings of the OECD/CSNI specialists meeting on fuel-coolant interactions

    Energy Technology Data Exchange (ETDEWEB)

    Akiyama, Mamoru; Yamano, Norihiro; Sugimoto, Jun [eds.

    1998-01-01

    The OECD/CSNI Specialists Meeting on Fuel Coolant Interactions (FCI) was held at Tokai-mura in Japan on May 19 through 21, 1997, and attended by 80 participants from 14 countries and one international organizations. In the meeting 36 papers were presented followed by active discussions in six sessions on various aspects of FCI issues, such as reactor application, premixing, propagation/trigger, experiments and code/models. At the end of the Meeting, the participants have reached to the consensus on the summary and recommendations, which consists of the following items; (1) We find no new evidence that would change or violate the conclusion of SERG-2 (1996) that alpha-mode failure is not risk significant. (2) Significant progress has been made since the Santa Barbara meeting (1993). (3) Several areas have been identified, which need further investigations to understand the basic FCI phenomena, and to improve the modeling. (4) We recommend maximizing open communication between various research groups in order to accelerate the resolution of the remaining issues. (5) We recommend that the next specialist meeting be held within 3 to 5 years in order to synthesize the activities described above. (J.P.N.)

  3. The program of international intercomparison of accident dosimetry

    International Nuclear Information System (INIS)

    2002-06-01

    The French institute of radioprotection and nuclear safety (IRSN) has carried out in June 2002 an international intercomparison program for the testing of the physical and biological accident dosimetry techniques. The intercomparison is jointly organized by the IRSN and the OECD-NEA with the sustain of the European commission and the collaboration of the CEA centre of Valduc (France). About 30 countries have participated to this program. Each country has supplied its own dosimeters and biological samples which have been irradiated using the Silene reactor of CEA-Valduc or a 60 Co source. These experiments allow to test the new dosimetric techniques that have been developed since the previous intercomparison program (1993) and to confirm or improve the performances of older techniques. Aside from the intercomparison exercise, this report makes a status of the known radiological accidents and of the effects of high doses of ionizing radiations on human health (symptoms, therapeutics). It explains the phenomenology of criticality accidents, the prevention means, and the history of such accidents up to the Tokai-Mura one in 1999. Finally, the dosimetry of criticality is presented with its physical and biological techniques. (J.S.)

  4. Precise measurement of the sup 2 sup 7 Al(n,2n) sup 2 sup 6 sup g Al excitation function near threshold and its relevance for fusion-plasma technology

    CERN Document Server

    Wallner, A; Priller, A; Steier, P; Vonach, H; Chuvaev, S V; Filatenkov, A A; Ikeda, Y; Mertens, G; Rochow, W

    2003-01-01

    A new accurate measurement of the sup 2 sup 7 Al(n,2n) sup 2 sup 6 Al excitation function leading to the ground state of sup 2 sup 6 Al(t sub 1 sub / sub 2 =7.1 x 10 sup 5 years) in the near-threshold region (E sub t sub h =13.55 MeV) was performed, with the goal to achieve relative cross-sections with the highest accuracy possible using proven methods. In addition, the measurements were also designed to provide good absolute cross-section values, since absolute cross-sections are important for radioactive waste predictions in future fusion reactor materials. Samples of Al metal were irradiated with neutrons in the energy range near threshold (E sub n =13.5-14.8 MeV) in Vienna and St. Petersburg, and at 14.8 MeV in Tokai-mura. In addition, irradiations with neutrons of higher energies (17 and 19 MeV) were performed in Tuebingen, to obtain also cross-section values well above threshold. The amount of sup 2 sup 6 Al produced during the irradiations was measured via accelerator mass spectrometry (AMS). With this...

  5. Evaluation of cold testing for Tokai Vitrification Facility

    International Nuclear Information System (INIS)

    Yoshioka, Masahiro; Inada, Eiichi

    1994-01-01

    The cold testing of the Tokai Vitrification Facility (TVF) was completed at the end of March, 1994 through the tests of nearly two years since May in 1992. The cold testing was carried out in order to evaluate the process equipment, product quality control, remote maintenance capability. The test results shown that TVF has enough performance with safety to treat the liquid waste in each process, and to control the product quality. For the remote maintenance of process equipment in the vitrification cell, the remote maintenance capability was confirmed for all remote equipment in the cell. The improvements were taken for some equipment with problem from the point of the operability and maintenance. It was confirmed by these test results that the TVF can go forward to the hot test operation using actual waste. (author)

  6. Local governments' roles of the compensation for damage by the Tokai JCO criticality accident

    Energy Technology Data Exchange (ETDEWEB)

    Tanabe, Tomoyuki [Central Research Inst. of Electric Power Industry, Tokyo (Japan). Socio-Economic Research Center

    2003-03-01

    The Tokai JCO criticality accident on September 30, 1999 was the first case to which The Law on Compensation for Nuclear Damage was applied. Although the Law on Compensation for Nuclear Damage formulates the outline of the institutional framework for nuclear third party liability together with operator's insurance scheme, details of actual compensation procedure are not specified. By this reason, the compensation procedure in the Tokai accident had been executed without a concrete legal specification and a precedent. In spite of this situation, the compensation procedure with the accident led to an unexpectedly successful result. We observe the several reasons why the compensation procedure was implemented successfully despite the lack of concrete legal specification and a precedent. One of the reasons is that the local governments, Tokai Village and Ibaraki Prefecture, immediately took the leadership in implementing a temporary regime of compensation procedure without wasting time for waiting national government's directives. Upon practicing this compensation procedure, the local governments implemented the following steps. (1) Initial estimation of the amount and scope of damage. (2) Providing the criteria and heads of damage subject to compensation. (3) Unitary compensation procedure at the local levels. (4) Distribution of emergency payments for the victims. (5) Facilitating compensatory negotiation between the victims and JCO as arbitrator. However, some concerns are also pointed out about the fact that the local government directed the whole procedure without sufficient adjustment with the national government for compensation policy. Among all, in the compensation led by the local governments, it was difficult to guarantee fairness of compensation because victims who are influential on the local government such as industrial associations would have unfairly strong negotiation power in the compensatory negotiation, while the operator being

  7. Air concentration of radiocaesium in Tsukuba, Japan following the release from the Tokai waste treatment plant: comparisons of observations with predictions

    International Nuclear Information System (INIS)

    Igarashi, Yasuhito; Aoyama, Michio; Miyao, Takashi; Hirose, Katsumi; Komura, Kazuhisa; Yamamoto, Masayoshi

    1999-01-01

    On March 11, 1997 a fire and explosion accident occurred at the bituminization facility of the Power Reactor and Nuclear Fuel Development, Tokai, Japan. As a result of this accident, 134,137 Cs was detected in an air filter sample collected at the Meteorological Research Institute, Tsukuba during March 10 to 12. The 134,137 Cs air concentration was about 100 and 10 μBq m -3 , respectively. This result suggests that there was little radiation exposure of the residents in the area. The average 137 Cs air concentration during this period was about two orders of magnitude higher than 'baseline' air (sub-μBq m -3 ) during February to April, 1997, measured by ultra-low background γ-spectrometry. By a simple calculation using a Gaussian plume model with the measured data, we estimated the minimum emission of the radioactivity by the PNC accident to be in the range 60 MBq to around 600 MBq. The meteorological condition during the week of the accident are also described

  8. Proceedings of the 1999 workshop on the utilization of research reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-01

    The 1999 workshop on the utilization of reactors, which is the eighth workshop on the theme of research reactor utilization was held at JAERI Tokai and Mito Plaza Hotel, in Japan from November 25 to December 2. This workshop was executed based on the agreement in the Tenth International conference for Nuclear Cooperation in Asia (ICNCA) held in Tokyo, March 1999. The whole workshop consists of the workshop on the theme of following three fields, 1) neutron scattering, 2) radioisotope production and 3) safe operation and maintenance of research reactor, and the sub-workshop carried out the experiments of small angle neutron scattering. The total number of participants for the workshop was about 70 people from 9 countries, i.e. Australia, China, Indonesia, Korea, Malaysia, The Philippines, Thailand, Vietnam and Japan. The 37 of the presented papers are indexed individually. (J.P.N.)

  9. The calculation and estimation of wastes generated by decommissioning of nuclear facilities. Tokai works and Ningyo-toge Environmental Engineering Center

    International Nuclear Information System (INIS)

    Ayame, Y.; Tanabe, T.; Takahashi, K.; Takeda, S.

    2001-07-01

    This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decommissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decommissioning of the nuclear facilities are as follows. (1) Tokai works: The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2) Ningyo-toge Environmental Engineering Center: The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton. (author)

  10. Experience of iodine removal in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Kikuchi, K.; Komori, Y.; Takeda, K.

    1985-01-01

    In the Tokai reprocessing plant about 170 ton of irradiated fuels have been processed since the beginning of hot operations in 1977. There was no effective equipment for iodine removal from the off-gas except for alkaline scrubbers when the plant construction was completed. In order to reduce the iodine discharge to the atmosphere, silver-exchanged zeolite (AgX) filters were installed additionally in 1979 and 1980, and they have been effective. However, those decontamination factors (DFs) were not as high as expected, and increasing the reprocessing amount of spent fuels it became necessary to lower the iodine discharge to the atmosphere. Therefore, other iodine removal equipment is planned to be installed in the plant. Concerning these investigations and development of iodine removal techniques, the iodine concentration of actual off-gases was measured and useful data were obtained

  11. Remote repair of the dissolvers in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Otani, Yosikuni

    1985-01-01

    In the Tokai fuel reprocessing plant, there occurred failures (pinholes) in two dissolver tanks successively in 1982 and 1983. These dissolvers are set under high radiation field, not permitting access of the personnel. So, repair works were carried out after development of the remotely operated repair system. For repair of the failed dissolver tanks, after tests and studies, the means was employed of grinding off the wall surface to small depth and then forming over it a corrosion resistant sealing layer by padding welding. The repair system which enabled the repair and the inspection in the cell by remote operation consisted of six devices including polishing, welding, dye penetration test, etc. Repair works on the dissolvers took two months and a half from September 1983. (Mori, K.)

  12. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 7:00 PM status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on March 16, 2011, at 7:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  13. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 17, 2011, 6:00 AM status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on March 17, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  14. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 18, 2011, 2:00 PM status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on March 18, 2011, at 2:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  15. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 17, 2011, 3:00 PM status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on March 17, 2011, at 3:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  16. In-plant measurements of gamma-ray transmissions for precise K-edge and passive assay of plutonium concentration and isotopic abundance in product solutions at the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Asakura, Y.; Kondo, I.; Masui, J.; Shoji, K.; Russo, P.A.; Hsue, S.T.; Sprinkle, J.K. Jr.; Johnson, S.S.

    1982-01-01

    A field test has been carried out for more than 2 years for determination of plutonium concentration by K-edge absorption densitometry and for determination of plutonium isotopic abundance by transmission-corrected passive gamma-ray spectrometry. This system was designed and built at Los Alamos National Laboratory and installed at the Tokai reprocessing plant of the Power Reactor and Nuclear Fuel Development Corporation as a part of the Tokai Advanced Safeguards Technology Exercise (TASTEX). For K-edge measurement of plutonium concentration, the transmissions at two discrete gamma-ray energies are measured using the 121.1- and 122.1-keV gamma rays from 75 Se and 57 Co. Intensities of the plutonium passive gamma rays in the energy regions between 38 and 51 keV and between 129 and 153 keV are used for determination of the isotopic abundances. More than 200 product solution samples have been measured in a timely fashion during these 2 years. The relative precisions and accuracies of the plutonium concentration measurement are shown to be within 0.6% (1 sigma) in these applications, and those for plutonium isotopic abundances are within 3% for 238 Pu, 0.4% for 239 Pu, 1.2% for 240 Pu, 1.3% for 241 Pu, and 7% for 242 Pu. The time required is 10 min for the concentration assay, 10 min for the isotopics assay, and about 15 min for handling procedures in the laboratory

  17. Identification of a novel UDP-N-acetylglucosamine enolpyruvyl transferase (MurA) from Vibrio fischeri that confers high fosfomycin resistance in Escherichia coli

    Digital Repository Service at National Institute of Oceanography (India)

    Kumar, S.; Parvathi, A.; Hernandez, R.L.; Cadle, K.M.; Varela, M.F.

    -positive and Gram-negative bacteria. The antibiotic is used to treat uncomplicated urinary tract infections (UTIs) caused by E. coli and Enterococcus faecalis world wide (Falagas et al. 2008). Some pathogenic bacteria such as Mycobacterium tuberculosis...A proteins are naturally resistant to fosfomycin, such as in the case of Mycobacterium tuberculosis and Chlamydia trachomatis (DeSmet et al. 1999; McCoy et al. 2003). We compared the deduced amino acid sequence of V. fischeri MurA with the homologous...

  18. Current status of sea transport of nuclear fuel materials and LLW in Japan

    International Nuclear Information System (INIS)

    Kitagawa, Hiroshi; Akiyama, Hideo

    2000-01-01

    Along with the basic policy of the nuclear fuel cycle of Japan, many fuel cycle facilities have been already constructed in Rokkasho-Mura, Aomori prefecture, such as the uranium enrichment plant, the low level waste disposal center and the receiving pool of the spent nuclear fuels for reprocessing. These facilities belong to the Japan Nuclear Fuel Limited. (JNFL). Domestic sea transport of the spent nuclear fuels (SF) has been carried out since 1977 to the Tokai Reprocessing Plant, and the first sea transport of the SF to the fuel cycle facility in Rokkasho-Mura was done in Oct, 1998 using a new exclusive ship 'Rokuei-Maru'. Sea transport of the low level radioactive wastes (LLW) has been carried out since 1992 to the Rokkasho LLW Disposal Center, and about 130,000 LLW drams were transported from the nuclear power plant sites. These sea transport have demonstrated the safety of the transport of the nuclear fuel cycle materials. It is hoped that the safe sea transport of the nuclear fuel materials will contribute to the more progress of the nuclear fuel cycle activities of Japan. (author)

  19. Review of Design Data for Safety Assessment of Tokai Reprocessing Plant. Control of hydrogen gas produced by radiolysis of reprocessing solutions at Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Omori, E.; Surugaya, N.; Takaya, A.; Nakamura, H.; Maki, A.; Yamanouchi, T.

    1999-10-01

    Radioactive materials in aqueous solution at a nuclear fuel reprocessing plant causes radiolytic generation of several gases including hydrogen. Hydrogen accumulating in equipment can be an explosion hazard. In such plants, though the consideration in the design has been fundamentally made in order to remove the ignition source from the equipment, the hydrogen concentration in the equipment should not exceed the explosion threshold. It is, therefore, desired to keep the hydrogen concentration lower than the explosion threshold by dilution with the air introduced into equipment, from the viewpoint which previously prevents the explosion. This report describes the calculation of hydrogen generation, evaluation of hydrogen concentration under abnormal operation and consideration of possible improvement at Tokai Reprocessing Plant. The amount of hydrogen generation was calculated for each equipment from available data on radiolysis induced by radioactive materials. Taking into consideration for abnormal condition that is single failure of air supply and loss of power supply, the investigation was made on the method for controlling so that the hydrogen concentration may not exceed the explosion threshold. Possible means which can control the concentration of hydrogen gas under the explosion threshold have been also investigated. As the result, it was found that hydrogen concentration of most equipment was kept under the explosion threshold. It was also shown that improvement of the facility was necessary on the equipment in which the concentration of the hydrogen may exceed the explosion threshold. Proposals based on the above results are also given in this report. The above content has been described in 'Examination of the hydrogen produced by the radiolysis' which is a part of 'Reviews of Design Data for Safety Assessment of Tokai Reprocessing Plant' (JNC TN8410 99-002) published in February 1999. This report incorporates the detail evaluation so that operation

  20. Proposal of a nuclear cycle research and development plan in Tokai works. The roadmap from LWR cycle to FBR cycle

    International Nuclear Information System (INIS)

    Nakamura, Hirofumi; Abe, Tomoyuki; Kashimura, Takuo; Nagai, Toshihisa; Maeda, Seichiro; Yamaguchi, Toshiya; Kuroki, Ryoichiro

    2003-07-01

    The Generation-II Project Task Force Team has investigated a research and development plan of a future nuclear fuel cycle in Tokai works for about three months from December 19, 2002. First we have discussed about the present condition of Japanese nuclear fuel cycle and have recognized it as the following. The relation of the technology between the LWR-cycle and the FBR-cycle is not clear. MOX Fuel Use in Light Water Reactors is important to establish technology of the FBR fuel cycle. Radioactive waste disposal issue is urgent. Next we have proposed the three basic policies on R and D plan of nuclear fuel cycle in consideration of the F.S. on FBR-cycle. Establishment and advancement of 'the tough nuclear fuel cycle'. Early establishment of the FBR cycle technology to be able to supply energy stably for long-term. Establishment of the radioactive waste treatment and disposal technology, and optimization of nuclear fuel cycle technology from the viewpoint of radioactive waste. And we have proposed the Japanese technical holder system to integrate all LWR and FBR cycle technology. (author)

  1. National conference of the CLI Presidents

    International Nuclear Information System (INIS)

    Lacoste, A.

    2000-01-01

    This document presents the subjects discussed during the 11. national conference of the CLI Presidents. The subjects are proposed in discussion or speech form. They concern the following matter: the annual result of the factory inspection in the electric power plants; the relations between the CLI (Commission on Local Information) and the CSSIN (Superior Council on the Safety and the Nuclear Information); the Tokai-Mura accident and the teaching brought in France; the crisis exercise of Nogent-sur Seine; a presentation of the future Internet site of the Nuclear Safety Authority. The document also includes a synthesis of the working group reflexions concerning the CLI part in a crisis management and in the public information. (A.L.B.)

  2. National conference of the CLI Presidents; Conference nationale des Presidents de CLI

    Energy Technology Data Exchange (ETDEWEB)

    Lacoste, A

    2000-07-01

    This document presents the subjects discussed during the 11. national conference of the CLI Presidents. The subjects are proposed in discussion or speech form. They concern the following matter: the annual result of the factory inspection in the electric power plants; the relations between the CLI (Commission on Local Information) and the CSSIN (Superior Council on the Safety and the Nuclear Information); the Tokai-Mura accident and the teaching brought in France; the crisis exercise of Nogent-sur Seine; a presentation of the future Internet site of the Nuclear Safety Authority. The document also includes a synthesis of the working group reflexions concerning the CLI part in a crisis management and in the public information. (A.L.B.)

  3. INIS regional training seminar for Asia and the Pacific

    International Nuclear Information System (INIS)

    Shimokawa, Jun-ichi; Ebinuma, Yukio

    1985-01-01

    Introduction is made to current practice of the INIS as well as beneficial execution of the 1984 INIS Training Seminar, which was held in Japan on 22-27 October. Under the proper guidance of three lecturers from IAEA. 28 trainees from 9 countries performed 4-day exercises in one of the three courses (subject analysis, descriptive cataloguing and online retrieval) in Tokyo. All of the participants visited to see some organizations related to information processing and documentation in Tsukuba Science City and JAERI at Tokai-mura for the last two day. These curriculum led to not only realization of substantial training but also promotion of friendly understanding of Japan and among them. (author)

  4. Summary of typical routine maintenance activities at Tokai Reprocessing Plant. Supplement (March, 2002)

    International Nuclear Information System (INIS)

    2002-03-01

    Typical maintenance activities, such as replacement of worn out parts and cleaning of filter elements, routinely performed during steady operation are summarized. [The Summary of Typical Routine Maintenance Activities at Tokai Reprocessing Plant] (JNC TN 8450 2001-006) was already prepared in September, 2001. The purpose of this summary is to give elementary understanding on these activities to people who are responsible for explanation them to the public. At this time, the same kind of summary is prepared as a supplement of the previous one. (author)

  5. Dose evaluation for the public around the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Takeishi, Minoru; Furuta, Sadaaki; Miyabe, Kenjiro; Shinohara, Kunihiko

    2007-01-01

    The dose evaluations for the public around the Tokai Reprocessing Plant (TRP) have been carried out by using the mathematical models, because the effects on the environmental radiation due to the operation of the TRP are too small to separate from the background level. The models were developed by the site-specific investigations of the environment and reviewed in several times based on the latest scientific knowledge. The maximum annual effective dose through the whole period of the operation of the TRP was evaluated as 1.4 μSv with the data of the discharge monitoring and the meteorological observation in 1992. The evaluated doses revealed to be kept as far below the annual dose limit for the public as 1 mSv. (author)

  6. JAEA-Tokai TANDEM annual report 2005. April 1, 2005 - March 31, 2006

    International Nuclear Information System (INIS)

    Ishii, Tetsuro; Takeuchi, Suehiro; Oshima, Masumi; Nagame, Yuichiro; Chiba, Satoshi; Sataka, Masao; Osa, Akihiko

    2006-09-01

    This annual report describes research activities, which have been performed using the JAEA-Tokai tandem accelerator with the energy booster from April 1, 2005 to March 31, 2006. Summary reports of 51 papers are categorized into seven research/development fields, i.e., (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, and (7) radiation effects in materials, and lists of publications, meetings, personnel and cooperative researches with universities related to these papers are contained. The 51 of presented papers are indexed individually. (J.P.N.)

  7. Direction of reprocessing technology development based on 30 years operation of Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Nomura, S; Tanaka, T.; Ohshima, H.

    2006-01-01

    Full text: Full text: Recent global interest focuses the possibility of recycling of spent fuel with advanced fast reactor fuel cycle system. Goal of closed fuel cycle is to achieve the maximum use of uranium resources and minimum disposal of waste by multi recycle of TRU as a competitive nuclear energy system. The future reprocessing and fuel fabrication system should be synchronized completely with the advanced reactor system and waste treatment and disposal back-end system to complete closed fuel cycle. To realize such system, current reprocessing system should be changed to handle Pu-U-Minor Actinide with more reductions in the cost and less waste volume, as well as an inherent proliferation resistance. For the successful industrialization of advanced reprocessing technology, it is necessary to combine three key elements of R and D efforts, engineering base demonstration and experiences of plant operation. Tokai Reprocessing Facilities licensed a maximum capacity of 0.7tHM/day began a hot operation in 1977 and reprocessed l,100tHM U02 spent fuel and 20tHM ATR-MOX with a continuous technological improvements under IAEA full scope safeguards. With 30 years experience, candidate of key technologies proposed for realizing the next advanced reprocessing are as follows: 1) Simplified co-extraction process of Pu-Np-U by using multistage centrifugal extractors in stead of pulsed columns; 2) Corrosion free components in acid condition by using corrosion resistant refractory alloys and ceramics; 3) Co-conversion technology to MA containing MOX powder by micro-wave heating method for a short process for MA containing MOX pellets fabrication; 4) Advanced verification of high level radioactive liquid waste combining separation technology of TRU and LLFP elements; 5) Advanced chemical analysis and monitoring system for TRU elements in a plant. These advanced reprocessing technologies will be applied mainly to reprocess the LWR spent fuel accumulated past and future

  8. Experience and projects concerning treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Fukuda, G.; Matsumoto, K.; Miyahara, K.

    1984-01-01

    The active operation of Tokai reprocessing plant started in September 1977, and about 170 t U of spent fuel were reprocessed between then and December 1982. During this period, the low-level waste processing plant reduced the amount of radioactivity discharged into the environment. For radioactive liquid waste, the treatment procedures consist mainly of evaporation to keep the discharge into the sea at a low level. For combustible low-level solid waste and the solvent waste, which is of low tributyl phosphate content, incineration has been used successfully (burned: about 150 t of combined LLSW, about 50 m 3 of solvent waste, i.e. diluent waste). Most of the past R and D work was devoted to reducing the activity discharged into the environment. Current R and D work is concerned with the treatment of solvent waste, the conditioning of solid wastes, the bituminization of low-level liquid waste and the vitrification of high-level liquid waste. The paper describes present practices, R and D work and future aspects of the treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant. (author)

  9. Fission-track ages of the Tokai Group and associate formations in the east coast areas of Ise Bay and their significance in geohistory

    International Nuclear Information System (INIS)

    Makinouchi, Takeshi; Danhara, Toru; Isoda, Kunitoshi.

    1983-01-01

    Fission-track ages of volcanic ash layers within the Tokai Group and associate formations in the east coast areas of Ise Bay are obtained by grain-by-grain method with which individual ages for the respective zircon grains are measured. They are as follows; 1) a volcanic ash layer in the Karayama Formation (tentative age: 1.9 +- 0.4 Ma). Among the zircon grains in this layer, essential ones occupy only 1 per cent, and the others are accidental. 2) Ohtani volcanic ash layer (4.3 +- 0.6 Ma). 3) Kosugaya volcanic ash layer (4.0 +- 0.5 Ma). 4) Kaminoma volcanic ash layer (5.3 +- 0.4 Ma). 5) A volcanic ash layer in the Toyoura Formation seems to be older than 10 Ma. 6) Zircon grains in the Kofu volcanic ash layer (Tokai Group) include two types of spontaneous namely track, clear and vague ones. The latter vague tracks are shorter and thiner, and seem to suffer thermal annealing. The ages obtained have clarified the following Points; a) The tentative age, 1.9 Ma, of the ''Karayama'' volcanic ash layer suggests the existence of unknown Plio-Pleistocene sediment in the Nagoya area. b) The sedimentary basin of Lake Tokai was formed in the latest Miocene, about 6.5 Ma. Generation of the basin coincides approximately with the stage of synchronous and abrupt change in sedimentation rate in sedimentary basins on the Pacific side of central and southern Japan. c) The Tokai Group in Chita (Tokoname Group) intercalates the Gilbert/Epoch 5 boundary in the paleomagnetic chronology in the middle horizon of the group. d) Average rate of sedimentation is about 1 m/10 4 yrs in the marginal areas of the basin, and 3-5 m/10 4 yrs in the central areas. (author)

  10. Status of nuclear safety research - 2000

    International Nuclear Information System (INIS)

    Sobajima, Makoto; Sasajima, Hideo; Umemoto, Michitaka; Yamamoto, Toshihiro; Tanaka, Tadao; Togashi, Yoshihiro; Nakata, Masahito

    2000-11-01

    The nuclear safety research at JAERI is performed in accordance with the long term plan on nuclear research, development and use and the safety research yearly plan determined by the government and under close relationship to the related departments in and around the Nuclear Safety Research Center. The criticality accident having occurred in Tokai-mura in 1999 has been the highest level nuclear accident in Japan and ensuring safety in whole nuclear cycle is severely questioned. The causes of such an accident have to be clarified not only technical points but also organizational points, and it is extremely important to make efforts in preventing recurrence, to fulfill emergency plan and to improve the safety of whole nuclear fuel cycle for restoring the reliability by the people to nuclear energy system. The fields of conducting safety research are engineering safety research on reactor facilities and nuclear fuel cycle facilities including research on radioactive waste processing and disposal and research and development on future technology for safety improvement. Also, multinational cooperation and bilateral cooperation are promoted in international research organizations in the center to internationally share the recognition of world-common issues of nuclear safety and to attain efficient promotion of research and effective utilization of research resources. (author)

  11. A study of television imaging system for fast neutron radiography

    International Nuclear Information System (INIS)

    Yoshii, Koji

    1992-01-01

    The neutron radiography with fast neutron beam is a very useful imaging technique for thicker objects, especially those composed of hydrogen-rich materials which are sometimes difficult to image by thermal neutron radiography. The fast neutron radiography has not been studied so much as the thermal neutron radiography. The fast neutron radiography has been studied at the fast neutron source reactor 'Yayoi' of the University of Tokyo built in Tokai-mura. The average neutron energy of the Yayoi is about 1 MeV, and the peak neutron flux at the core center is 0.8 x 10 12 at the maximum operating power of 2 kW. In the experiment on fast neutron radiography, a CR39 nuclear track detector has been used successfully. But in the Yayoi radiography procedure, about 24 hours were required for obtaining an imaging result. To get a prompt imaging result and a real-time imaging result, it is necessary to develop a fast neutron television system, and in this paper, a new fast neutron TV system is proposed. The main difference is the converter material sensitive to fast neutrons. The study on the fast neutron TV system was carried out by using the Baby Cyclotron of Japan Steel Works, and the good images were realized. (K.I.)

  12. PSA application on the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Ishida, Michihiko; Nakano, Takafumi; Morimoto, Kazuyuki; Nojiri, Ichiro

    2003-01-01

    The Periodic Safety Review (PSR) of the Tokai Reprocessing Plant (TRP) has been carrying out to obtain an overall view of actual plant safety. As a part of the PSR, Probabilistic Safety Assessment (PSA) methodology has been applied to evaluate the relative importance of safety functions that prevent the progress of events causing to postulated accidents. Based on the results of the safety reassessments of the TRP that was carried out in 1999, event trees were developed to model sequences of postulated accidents. Event trees were quantified by using the results of fault tree analysis and human reliability analysis. In the quantification, the reliability data generally used in PSA of nuclear power plants were mainly used. Operating experiences of the TRP were also utilized to evaluated both component/system reliability and human reliability. The relative importance of safety functions was evaluated by using two major importance measures, Fussell-Vesely and Risk Achievement Worth both generally used in PSA of nuclear power plants. Through these evaluations, some useful insights into the safety of the TRP have been obtained. The results of the relative importance measures would be utilized to qualify TRP component/equipment important to the safety. (author)

  13. Measurements of national radiation exposure rates on train lines in Tokai area

    International Nuclear Information System (INIS)

    Matsuda, Hideharu

    1996-01-01

    For data accumulation of natural radiation exposure rate derived from gamma-ray and cosmic-ray to evaluate population dose, the author measured the rate in the running vehicles of 12 JR Tokai lines, 17 Nagoya Railway lines, 4 Kinkinippon Railway lines and 1 line of Nagoya City Bus. A portable gamma spectrometer equipped with 3' in diameter x 3' NaI (Tl) scintillation detector was placed on the seat of the vehicle for measurement in the period of December, 1992-August, 1995. Gamma-ray and cosmic-ray exposure rates in air were assessed separately as reported before and expressed in Gy/h. The average exposure rate of gamma-ray in JR Tokai lines was 19.8 nGy/h and of cosmic-ray, 28.5 nGy/h, both of which were markedly varied from line to line. The average rates of gamma-and cosmic-ray were 21.6 nGy/h and 29.0 nGy/h, respectively, in Nagoya Railway lines and 20.9 nGy/h and 28.7 nGy/h, respectively, in Kinkinippon lines. In the city bus, the respective rates were 27.2 nGy/h and 27.0 nGy/h. Thus, the average rates of gamma-ray (about 20 nGy/h) and cosmic-ray (about 29 nGy/h) were not so different between JR and other private railway lines. In the bus, the former rate was slightly lower and the latter, slightly higher. However, the total rates of both rays were in the range of about 50-55 nGy/h in all vehicles examined. (H.O.)

  14. Dose reduction and cost-benefit analysis at Japan's Tokai No. 2 Plant

    International Nuclear Information System (INIS)

    Humamoto, Hisao; Suzuki, Seishiro; Taniguchi, Kazufumi

    1995-01-01

    In the Tokai No. 2 power plant of the Japan Atomic Power Company, about 80% of the annual dose equivalent is received during periodic maintenance outages. A project group for dose reduction was organized at the company's headquarters in 1986; in 1988, they proposed a five-year program to reduce by half the collective dose of 4 person-Sv per normal outage work. To achieve the target dose value, some dose-reduction measures were undertaken, namely, permanent radiation shielding, decontamination, automatic, operating machines, and ALARA organization. As the result, the collective dose from normal outage work was 1.6 person-Sv in 1992, which was less than the initial target value

  15. Report on design and technical standard planning of vibration controlling structure on the buildings, in the Tokai Reprocessing Facility, Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    Uryu, Mitsuru; Terada, Shuji; Shinohara, Takaharu; Yamazaki, Toshihiko; Nakayama, Kazuhiko; Kondo, Toshinari; Hosoya, Hisashi

    1997-10-01

    The Tokai reprocessing facility buildings are constituted by a lower foundation, vibration controlling layers, and upper structure. At the vibration controlling layer, a laminated rubber aiming support of the building load and extension of the eigenfrequency and a damper aiming absorption of earthquake energy are provided. Of course, the facility buildings are directly supported at the arenaceous shale (Taga Layer) of the Miocene in the Neogene confirmed to the stablest ground, as well the buildings with high vibration resistant importance in Japan. This report shows that when the vibration controlling structure is adopted for the reprocessing facility buildings where such high vibration resistance is required, reduction of input acceleration for equipments and pipings can be achieved and the earthquake resistant safety can also be maintained with sufficient tolerance and reliability. (G.K.)

  16. Computer aided radiation protection system at Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Ishida, J.; Saruta, J.; Yonezawa, R.

    1996-01-01

    Radiation control for workers and workforce has been carried out strictly and effectively taking into account ALARA principle at Tokai Reprocessing Plant (TRP) which has treated about 860 tons of irradiated fuels by now since 1977. The outline of radiation control method at TRP has already been described. This paper briefly describes our experiences and the capabilities of Radiological Information Management System (RIMS) for the safety operation of TRP, followed by radiation exposure control and activity discharge control as examples. By operating the RIMS, the conditions of workplace such as dose equivalent rate and air-contamination are easily and rapidly grasped to take prompt countermeasures for radiological protection, localization and elimination of contamination, and also the past experience data are properly applied to new radiological works to reduce exposures associated with routine and special repetitive maintenance operations at TRP. Finally, authors would like to emphasize that the form and system for radiological control of reprocessing plant has been established throughout our 15-year-experience at TRP. (author)

  17. Preliminary field tests of near-real-time materials accountancy system at the Tokai Reprocessing Plant (TASK F)

    International Nuclear Information System (INIS)

    Tsutsumi, Masayori; Sawahata, Toshio; Sugiyama, Toshihide; Tanaka, Kazuhiko; Suyama, Naohiro

    1982-01-01

    A study of applying the proposed near-real-time material accountancy model to the Tokai Reprocessing Plant, PNC (Power Reactor and Nuclear Fuel Development Corp.), showed that the model was feasible and effective to meet the IAEA (International Atomic Energy Agency) safeguards criteria in terms of detection timeliness and sensitivity. This study using the computer simulation technique is shown in this paper. In order to investigate the applicability of the model to the actual plant, the field test was carried out on the process in the material balance area (MBA) which covers the area from the input accountability vessel (IAV) to the product accountability vessel (PAV), in cooperation with JAERI. The key measuring points for dynamic physical inventory counts (D-PIT) are shown. The results of test evaluation are as follows: For timely detection, it will be able to evaluate an abnoumal accountancy in process by using the MUFd (material unaccounted for) obtained by the D-PIT about once every week. Therefore, this seems to satisfy the timely detection of IAEA safeguards criteria. As for detection, sensitivity and verification procedures, in order to clarify these criteria for a large scale reprocessing plant, further research and development will be required. In addition, since the field test was carried out along with normal plant operation, additional man-power problem was also considered. (Wakatsuki, Y.)

  18. JAEA-Tokai tandem annual report 2012. April 1, 2012 - March 31, 2013

    International Nuclear Information System (INIS)

    Nishio, Katsuhisa; Tsukada, Kazuaki; Koura, Hiroyuki

    2014-03-01

    The JAEA-Tokai tandem accelerator complex has been used in various research fields such as nuclear science and material science by researchers not only of JAEA but also from universities, research institutes and industrial companies. This annual report covers developments of accelerators and research activities carried out using the tandem accelerator and superconducting booster from April 1, 2012 to March 31, 2013. Thirty-one summary reports were categorized into seven research/development fields: (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effects in materials. This report also lists publications, meetings, personnel, committee members, cooperative researches and common use programs. (author)

  19. The development of in-cell remote inspection system in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Ishibashi, Yuzo

    1985-01-01

    In the Tokai fuel reprocessing plant, the containment is triple, i.e. the vessel containing radioactive material, then the concrete cell structure and finally the housing building. The fuel reprocessing plant is now proceeding with the development of an in-cell remote inspection system. The inspection system is for inspection of the cell itself and the equipment etc. in the cell, concerning the integrity. Described are the following: the course taken and problems in development of the remote inspection system; development of the floor rambling type remote inspection equipment and the multiple armed type, both for inspection of in-cell ''drip trays''; in-cell equipment inspection devices in specifications etc.; problems in its future development. (Mori, K.)

  20. Guideline for design and construction radiation monitoring equipments for Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Miyabe, Kenjiro; Ninomiya, Kazushige; Jin, Kazumi; Morifuji, Masayuki; Nemoto, Kazuhiko; Sato, Akira; Kawai, Keiichi

    1999-12-01

    Various kind of radiation monitoring equipment are used in radiation controlled area at each facility of Tokai reprocessing plant. These equipments have been designed and constructed based on the users requirements, and permitted by governmental regulation office. And, design has been carried out in consideration of the adoption of the new technology and our operational experience. Then, it has been used effectively for the radiation control of the facilities. This report summarizes the technical requirements that should be taken into consideration in the design and installation of radiation monitoring equipments. These requirements are fundamentally applicable when the equipments of the new facilities will be designed or the present instruments will be replaced. (author)

  1. Radiation exposure of the employes in fiscal 1980 at reactor facilities for testing and research and under development

    International Nuclear Information System (INIS)

    1982-01-01

    The owners of reactors are obligated by the law for the regulation of reactors, etc. to keep the radiation exposure dose of their employes below the permissible level. In fiscal 1980 (from April to March), the exposure dose of employes was largely below the permissible level. Based on the reports made by the owners in accordance with the law, the following data are presented in tables for the whole year and the respective quarters: in the research institutions including Japan Atomic Energy Research Institute (JAERI), Power Reactor and Nuclear Fuel Development Corporation (PNC) and educational institutions, the exposure dose distribution of employes; in the Tokai Research Establishment and Oarai Research Establishment, JAERI, and the Oarai Engineering Center and ATR ''Fugen'' Power Station, PNC, the exposure dose distribution, total exposure dose and average exposure dose of employes and outside workers. (J.P.N.)

  2. Study on neutron dosimetry in JNC Tokai Works

    Energy Technology Data Exchange (ETDEWEB)

    Tsujimura, Norio [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan). Tokai Works

    2003-03-01

    The author developed the neutron reference calibration fields using a {sup 252}Cf standard source surrounded with PMMA (polymethylmethacrylates) moderators at the Japan Nuclear Cycle Development Institute (JNC), Tokai Works. The moderators are concentric, annular cylinders made of lead-contained PMMA with a thickness of 13.5, 35.0, 59.5 and 77.0mm, and the {sup 252}Cf source is guided to the geometric center of moderators by the pneumatic system. These fields can provide the moderated neutron spectra very similar to those encountered around the globe-boxes of the fabrication process of MOX (PuO{sub 2}-UO{sub 2} mixed oxide) fuel. The neutron energy spectrum at the reference calibration point was evaluated from the calculations by MCNP4B and the measurements by the INS-type Bonner multi-sphere spectrometer and the hydrogen-filled proportional counters. The calculated neutron spectra were in good agreements with the measured ones. These fields were characterized in terms of the neutron fluence rate, spectral composition and ambient dose equivalent rate, and have served for the response-characterization of various neutron survey instruments. (author)

  3. Development of new treatment process for low level radioactive waste at Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Horiguchi, Kenichi; Sugaya, Atsushi; Saito, Yasuo; Tanaka, Kenji; Akutsu, Shigeru; Hirata, Toshiaki

    2009-01-01

    The Low-level radioactive Waste Treatment Facility (LWTF) was constructed at the Tokai Reprocessing Plant (TRP) and cold testing has been carried out since 2006. The waste which will be treated in the LWTF is combustible/incombustible solid waste and liquid waste. In the LWTF, the combustible/incombustible solid waste will be incinerated. The liquid waste will be treated by a radio-nuclides removal process and subsequently solidified in cement. This report describes the essential technologies of the LWTF and results of R and D work for the nitrate-ion decomposition technology for the liquid waste. (author)

  4. Maintenance management of emergency power supply equipment (uninterruptible power supply) in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Nishida, Kyosuke; Hiyama, Hisao; Shibata, Satomi; Iwasaki, Shogo; Inami, Shinichi

    2009-01-01

    Uninterruptible power supply systems are installed in the Tokai reprocessing plant in preparation for the emergency case that the commercial power supply is stopped by an accidental or intentional interruption in the supply of electricity. The uninterruptible power supply system particularly provides a temporary power source to the important devices for the radiation control of nuclear critical monitoring in the plant. Thus, the system is potentially important and essential for nuclear plants. The paper reports the current activities such as regular inspections, replacement of parts and system update, to maintain the function of uninterruptible power supply systems. (author)

  5. The report of the criticality accident in a uranium conversion test plant in Tokai-mura

    International Nuclear Information System (INIS)

    Murata, Hajime; Akashi, Makoto

    2002-03-01

    The criticality accident in the title occurred at around 10:35, on Sep. 30, 1999, cost the lives of two workers and caused many residents concern on their health. Moreover, rumors had both social and economic consequences. This report is a detailed account of the roles that many individuals and groups in the National Institute of Radiological Sciences (NIRS) performed in a range of the areas, and is published to discharge NIRS responsibilities in regards to the accident. The report involves chapters of detailed outline of the accident; acceptance of the victims and communications until the identification of the ''criticality'' accident; initial treatment; dose estimation (medical, hematological, physical and biological ones and that by dental metals activated by the neutron); decision making for therapeutic strategies; cooperation with the Network Council for Radiation Emergency Medicine and other medical facilities; emergency importation of medical supplies; treatment and progress (nursing system and radiation injuries); protection from radiation in medical facilities; response to nearby residents of the Plant; international response; press release; Uranium Processing Plant Criticality Accident Investigation Committee and the Health Management Committee organized by the Nuclear Safety Commission; handling of information; and radiation emergency medical preparedness at the NIRS (future issues and prospect). The report is hoped to be useful in preventing the occurrence of future accidents. (K.H.)

  6. NIRS report of the criticality accident in a uranium conversion test plant in Tokai-mura

    International Nuclear Information System (INIS)

    2001-01-01

    This report is a detailed account of the roles that National Institute of Radiological Sciences (NIRS) played at the criticality accident in the title, which occurred at around 10:35, on Sep. 30, 1999 and resulted in death of two workers after all, and is published to discharge NIRS responsibilities in regards to the accident. The accident caused many residents concern on their health and rumors had both social and economic consequences. The report involves chapters of detailed outline of the accident; demand for acceptance of the victims and communications until the identification of the criticality'' accident; the acceptance and initial treatment; the exposure dose estimation (based on acute symptoms, on physics, on chromosomal analyses and on neutron-activated dental metals, and detailed analyses for dose distribution); decision made for therapeutic strategies; cooperation with the Network Council for Radiation Emergency and with other medical facilities; the urgent import of medicine; treatment and processes (patients, nursing system and radiation injuries); radiation protection in medical facilities; response to nearby residents of the Plant; international response; press release; Uranium Processing Plant Criticality Accident Investigation Committee and the Health Management Committee organized by the Nuclear Safety Commission; handling of information; and radiation emergency medical preparedness at the NIRS (future issues and prospect). The report is hopefully useful in preventing the occurrence of future accidents. (N.I.)

  7. JAEA-Tokai tandem annual report 2010. April 1, 2010 - March 31, 2011

    International Nuclear Information System (INIS)

    Matsuda, Makoto; Takeuchi, Suehiro

    2011-12-01

    The JAEA-Tokai tandem accelerator complex has been used in various research fields such as nuclear science and material science by researchers not only of JAEA but also from universities, research institutes and industrial companies. This annual report covers developments of accelerators and research activities carried out using the tandem accelerator, superconducting booster, and radioactive nuclear beam accelerator, from April 1, 2010 to March 31, 2011. Thirty-six summary reports were categorized into seven research/development fields: (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effects in materials. This report also lists publications, meetings, personnel, committee members, cooperative researches and common use programs. (author)

  8. JAEA-Tokai tandem annual report 2013. April 1, 2013 - March 31, 2014

    International Nuclear Information System (INIS)

    Osa, Akihiko; Nishio, Katsuhisa; Tsukada, Kazuaki; Ishikawa, Norito; Toh, Yosuke; Koura, Hiroyuki; Ohkubo, Nariaki; Matsuda, Makoto

    2016-12-01

    The Japan Atomic Energy Agency (JAEA)-Tokai tandem accelerator complex has been used in various research fields such as nuclear science and material science by researchers not only of JAEA but also from universities, research institutes and industrial companies. This annual report covers developments of accelerators and research activities carried out using the tandem accelerator and superconducting booster from April 1, 2013 to March 31, 2014. Thirty-one summary reports were categorized into seven research/development fields: (1) accelerator operation, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effects in materials. This report also lists publications, meetings, personnel, committee members, cooperative researches and common use programs. (author)

  9. JAEA-Tokai tandem annual report 2010. April 1, 2010 - March 31, 2011

    Energy Technology Data Exchange (ETDEWEB)

    Matsuda, Makoto; Takeuchi, Suehiro [Japan Atomic Energy Agency, Nuclear Science Research Institute, Tokai, Ibaraki (Japan); Chiba, Satoshi; Mitsuoka, Shin-ichi; Tsukada, Kazuaki [Japan Atomic Energy Agency, Advanced Science Research Center, Tokai, Ibaraki (Japan); Ishikawa, Norito; Toh, Yosuke [Japan Atomic Energy Agency, Nuclear Science and Engineering Directorate, Tokai, Ibaraki (Japan)

    2011-12-15

    The JAEA-Tokai tandem accelerator complex has been used in various research fields such as nuclear science and material science by researchers not only of JAEA but also from universities, research institutes and industrial companies. This annual report covers developments of accelerators and research activities carried out using the tandem accelerator, superconducting booster, and radioactive nuclear beam accelerator, from April 1, 2010 to March 31, 2011. Thirty-six summary reports were categorized into seven research/development fields: (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effects in materials. This report also lists publications, meetings, personnel, committee members, cooperative researches and common use programs. (author)

  10. JAEA-Tokai tandem annual report 2011. April 1, 2011 - March 31, 2012

    International Nuclear Information System (INIS)

    Nishio, Katsuhisa; Tsukada, Kazuaki; Koura, Hiroyuki

    2014-04-01

    The JAEA-Tokai tandem accelerator complex has been used in various research fields such as nuclear science and material science by researchers not only of JAEA but also from universities, research institutes and industrial companies. This annual report covers developments of accelerators and research activities carried out using the tandem accelerator, superconducting booster, and radioactive nuclear beam accelerator, from April 1, 2011 to March 31, 2012. Twenty-seven summary reports were categorized into seven research/development fields: (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effects in materials. This report also lists publications, meetings, personnel, committee members, cooperative researches and common use programs. (author)

  11. Exposure management systems in emergencies as comprehensive medical care

    International Nuclear Information System (INIS)

    Shinohara, Teruhiko

    2000-01-01

    The emergency management of nuclear hazards relies on a comprehensive medical care system that includes accident prevention administration, environmental monitoring, a health physics organization, and a medical institution. In this paper, the care organization involved in the criticality accident at Tokai-mura is described, and the problems that need to be examined are pointed out. In that incident, even the expert was initially utterly confused and was unable to take appropriate measures. The author concluded that the members of the care organization were all untrained for dealing with nuclear hazards and radiation accidents. The education and training of personnel at the job site are important, and they are even more so for the leaders. Revisions of the regional disaster prevention plans and care manual are needed. (K.H.)

  12. Proceedings of the 2007 symposium on nuclear data

    International Nuclear Information System (INIS)

    Hazama, Taira; Fukahori, Tokio

    2008-11-01

    The 2007 Symposium on Nuclear Data was held at RICOTTI in Tokai-mura, Ibaraki-ken, Japan, on 29th and 30th of November 2007, with about 80 participants. Nuclear Data Division of Atomic Energy Society of Japan organized this symposium with cooperation of North Kanto Branch of the society. In the oral sessions, 10 papers were presented on topics of JEDNL-4, experiments, evaluations, applications, and research activity in China. In the poster session, presented were 12 papers concerning experiments, evaluations, benchmark tests, and so on. Tutorials on nuclear data, which were for cross section data creation process and PHITS code, were also done. Major part of those presented papers is compiled in this proceedings. The 19 of the presented papers are indexed individually. (J.P.N.)

  13. JCO criticality accident termination operation

    International Nuclear Information System (INIS)

    Kanamori, Masashi

    2001-12-01

    On September 30 at around 10:35 AM, criticality accident occurred at the JCO's conversion building in Tokai-mura. Since criticality accident had not been anticipated, neither devices for termination of criticality accident nor neutron detectors were available. Immediately after the information of the accident, our emergency staff (Japan Nuclear Cycle development institute staff) went to JCO site, to measure the intensity of neutrons and gammas. There were four main tasks, first one was to measure the radiation intensity, second one was to terminate the criticality accident, third one is to alert the residents surrounding the JCO site, fourth one is to evacuate the employees in the site. These tasks were successfully performed until October 1. This paper describes about how these operations were performed by the relevant staffs. (author)

  14. Gamma ray NDA assay system for total plutonium and isotopics in plutonium product solutions

    International Nuclear Information System (INIS)

    Cowder, L.R.; Hsue, S.T.; Johnson, S.S.; Parker, J.L.; Russo, P.A.; Sprinkle, J.K.; Asakura, Y.; Fukuda, T.; Kondo, I.

    1979-01-01

    A LASL-designed gamma-ray NDA instrument for assay of total plutonium and isotopics of product solutions at Tokai-Mura is currently installed and operating. The instrument is, optimally, a densitometer that uses radioisotopic sources for total plutonium measurements at the K absorption edge. The measured transmissions of additional gamma-ray lines from the same radioisotopic sources are used to correct for self-attenuation of passive gamma rays from plutonium. The corrected passive data give the plutonium isotopic content of freshly separated to moderately aged solutions. This off-line instrument is fully automated under computer control, with the exception of sample positioning, and operates routinely in a mode designed for measurement control. A one-half percent precision in total plutonium concentration is achieved with a 15-minute measurement

  15. Calculation code used in criticality analyses for the accident of JCO precipitation tank

    International Nuclear Information System (INIS)

    Miyoshi, Yoshinori

    2000-01-01

    In order to evaluate nuclear features on criticality accident formed at the nuclear fuel processing facility in Tokai Works of the JCO, Ltd. (JCO), in Tokai-mura, Ibaraki prefecture, dynamic analyses to calculate output change after occurring the accident as well as criticality analyses to calculate reactivity added to precipitation tank, were carried out according to scenario on accident formation. For the criticality analyses, a continuous energy Monte Carlo code MCNP was used to carry out calculation of reactivity fed into the precipitation tank as correctly as possible. And, SRAC code system was used for calculation on temperature and void reactivity coefficients, effective delayed neutron ratio beta eff , and instantaneous neutron generation time required for parameters controlling transition features at criticality accident. In addition, for the dynamic analyses, because of necessity of considering on volume expansion of solution fuels used as exothermic body and radiation decomposition gas forming into solution, output behavior, numbers of nuclear fission, and so forth at initial burst portion were calculated by using TRACE and quasi-regular code, at a center of AGNES-2 promoting on its development in JAERI. Here were reported on outlines and an analysis example on calculation code using for the nuclear features evaluation. (G.K.)

  16. Dose reduction and cost-benefit analysis at Japan`s Tokai No. 2 Plant

    Energy Technology Data Exchange (ETDEWEB)

    Humamoto, Hisao; Suzuki, Seishiro; Taniguchi, Kazufumi [Japan Atomic Power Co., Otemachi (Japan)

    1995-03-01

    In the Tokai No. 2 power plant of the Japan Atomic Power Company, about 80% of the annual dose equivalent is received during periodic maintenance outages. A project group for dose reduction was organized at the company`s headquarters in 1986; in 1988, they proposed a five-year program to reduce by half the collective dose of 4 person-Sv per normal outage work. To achieve the target dose value, some dose-reduction measures were undertaken, namely, permanent radiation shielding, decontamination, automatic, operating machines, and ALARA organization. As the result, the collective dose from normal outage work was 1.6 person-Sv in 1992, which was less than the initial target value.

  17. JAEA-Tokai tandem annual report 2009. April 1, 2009 - March 31, 2010

    International Nuclear Information System (INIS)

    Matsuda, Makoto; Takeuchi, Suehiro

    2010-12-01

    The JAEA-Tokai tandem accelerator complex has been used in various research fields such as nuclear science and material science by researchers not only of JAEA but also from universities, research institutes and industrial companies. This annual report covers developments of accelerators and research activities carried out using the tandem accelerator, superconducting booster, and radioactive nuclear beam accelerator, from April 1, 2009 to March 31, 2010. Fifty-seven summary reports were categorized into seven research/development fields: (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effects in materials. This report also lists publications, meetings, personnel, committee members, cooperative researches and common use programs. The fifty-seven summary reports are indexed individually. (J.P.N.)

  18. JAEA-Tokai tandem annual report 2008. April 1, 2008 - March 31, 2009

    International Nuclear Information System (INIS)

    Nagame, Yuichiro; Chiba, Satoshi; Mitsuoka, Shinichi

    2009-11-01

    The JAEA-Tokai tandem accelerator complex has been used in various research fields such as nuclear science and material science by researchers not only of JAEA but also from universities, research institutes and industrial companies. This annual report covers developments of accelerators and research activities carried out using the tandem accelerator, superconducting booster, and radioactive nuclear beam accelerator, from April 1, 2008 to March 31, 2009. Fifty-five summary reports were categorized into seven research/development fields: (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effects in materials. This report also lists publications, meetings, personnel, committee members, cooperative researches and common use programs. The fifty-five summary reports are indexed individually. (J.P.N.)

  19. JAEA-Tokai tandem annual report 2007. April 1, 2007 - March 31, 2008

    International Nuclear Information System (INIS)

    Nagame, Yuichiro; Chiba, Satoshi; Ishikawa, Norito; Mitsuoka, Shinichi; Ishii, Tetsuro; Matsuda, Makoto

    2008-11-01

    The JAEA-Tokai tandem accelerator facility has been used in various research fields of heavy-ion nuclear science and material science not only by JAEA personnel but also by researchers from universities, institutes and companies. This annual report describes a summary of research activities carried out in the period between April 1, 2007 and March 31, 2008. The forty-nine summary reports from users were categorized into seven research/development fields: (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effects in materials. Also contained are lists of publications, meetings, technical staff, researchers in JAEA and cooperative researchers with universities. The 49 of the presented papers are indexed individually. (J.P.N.)

  20. The NFI TOKAI SD System - management of the capabilities of operators in fuel fabrication plants

    International Nuclear Information System (INIS)

    Fukushima, T.

    2008-01-01

    Since the JCO criticality accident occurred in 1999, even more emphasis has been placed on the management of nuclear safety in Japan. This is particularly true for the education of operators and the observance of operational procedures. Even prior to this accident, Nuclear Fuel Industries, Ltd., NFI, regarded the education and development of skilled operators very seriously and we have developed an education system, called the SD system (Skill Development system), to assure the careful education of the operators and the improvement of their skill in order to prevent human error events. Our education system in the Tokai works, is explained. (author)

  1. The killing effects of ultraviolet light and x-rays on free-living nematode, Rhabditidae tokai

    International Nuclear Information System (INIS)

    Ishii, Naoaki; Suzuki, Kenshi

    1980-01-01

    The life-shortening effects of ultraviolet light (UV) and X-rays were investigated with a strain of free-living nematode, Rhabditidae tokai. UV exhibited a significant life-shortening effect on adult worms, and it also inhibited growth of larvae, hatching of eggs and reproduction. Sensitivity to UV was decreased with increasing ages. In contrast, nematodes showed a marked resistance to X-rays. Data were obtained suggesting that X-ray-induced single-strand breaks in DNA can be rapidly and efficiently rejoined by a repair mechanism. Malformations were observed when immature larvae were irradiated with X-rays. (author)

  2. Annual report on activities of Radiation Protection Division at JNC Tokai Works in fiscal year of 2001

    International Nuclear Information System (INIS)

    Shinohara, Kunihiko

    2002-08-01

    This annual report is summary of the activities of Radiation Protection Division at JNC Tokai Works in fiscal year of 2001. This report consists of the introduction of the radiation control in working area of the reprocessing plant, the MOX fuel fabrication facilities and laboratories, the discharges control of these facilities, the personal dosimetry, the environmental monitoring, the control of radiation standards and calibration, the maintenance of radiation measurement instruments, the safety study, the technical support for outside organizations and other activities. (author)

  3. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011 (15 mars 2011 - point a 22h00 heures)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 15, 2011, at 10:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  4. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 9:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 16 mars 2011 a 9 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 16, 2011, at 9:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  5. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 2:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 16 mars 2011 a 14 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 16, 2011, at 2:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of all 6 reactors of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  6. Removal of radioactive cesium from surface soils solidified using polyion complex. Rapid communication for decontamination test at Iitate-mura in Fukushima Prefecture

    International Nuclear Information System (INIS)

    Naganawa, Hirochika; Yanase, Nobuyuki; Mitamura, Hisayoshi; Nagano, Tetsushi; Yoshida, Zenko; Kumazawa, Noriyuki; Saitoh, Hiroshi; Kashima, Kaoru; Fukuda, Tatsuya; Tanaka, Shun-ichi

    2011-01-01

    We tried the decontamination of surface soils for three types of agricultural land at Nagadoro district of Iitate-mura (village) in Fukushima Prefecture, which is highly contaminated by deposits of radionuclides from the plume released from the Fukushima Daiichi nuclear power plant. The decontamination method consisted of the peeling of surface soils solidified using a polyion complex, which was formed from a salt solution of polycations and polyanions. Two types of polyion complex solution were applied to an upland field in a plastic greenhouse, a pasture, and a paddy field. The decontamination efficiency of the surface soils reached 90%, and dust release was effectively suppressed during the removal of surface soils. (author)

  7. Development and Field Application Experience of the Reactor Internal Preventive Maintenance Technology

    International Nuclear Information System (INIS)

    Kanno, A.; Yoshikubo, F.; Morinaka, R.; Tanaka, M.; Hasegawa, K.; Hatou, H.

    2012-01-01

    A reactor internal preventive maintenance technology, Water Jet Peening (WJP), has been developed as a stress corrosion cracking (SCC) mitigation technology that has been successfully implemented during refuelling outages at 15 Boiling Water Reactors (BWR) and three (3) Advanced BWRs (during the site construction and in the shop fabrication) in Japan. WJP is one of the most successful underwater peening methods, which utilizes the energy generated from the collapsing of bubbles produced by the cavitating water jet nozzle. The energy produced from the cavitations introduces compressive residual stress on the metal surface and subsurface up to a depth of several hundred micrometers. Most recently, we have successfully applied WJP to the bottom head components and to some cracked areas on the shroud support in the Tokai-2 plant. In the case of the bottom head components, we produced inspection and repair tooling as a contingency in the event SCC was identified and would be required to be repaired prior to the implementation of WJP. (author)

  8. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 3:30 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 15 mars 2011 a 15h30

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 15, 2011, at 3:30 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  9. Restoration potential for Danube River Basin, lower Danube and Mura Drava Danube Biosphere Reserve

    Directory of Open Access Journals (Sweden)

    SCHWARZ Ulrich

    2013-12-01

    Full Text Available Originally main Danube basin floodplains would cover an area of 26,500 km², which is equal to about 3.3% of the total catchment size. In recent history, 80% have been cut off by dikes and dams for flood control, hydropower generation, to improve navigability or simply to meliorate land for agricultural purposes. River regulation, rectification and floodplain loss changed the hydromorphological conditions for many major rivers and cause the loss of large water retention areas, the acceleration and unfavourable superimposition of flood waves, the local increase of flood peaks and the loss of functional wetlands and their ecological services. The aim of the investigations commissioned by World Wide Fund (since 2009, three studies with increasing spatial resolution were carried out, for the whole Danube basin and for the lower Danube, Mura and Drava rivers was the assessment and prioritisation of potential restoration areas to support national and international activities in respect to nature conservation, the ecological status improvement under Water Framework Directive (WFD and flood mitigation. Aside of the review of existing and planned major restoration projects, new areas are proposed based on continuously available data sets including land use, spatial configuration, hydromorphological intactness, overlapping protected areas and different floodplain types.

  10. JAEA-Tokai TANDEM annual report 2006. April 1, 2006 - March 31, 2007

    International Nuclear Information System (INIS)

    2008-01-01

    This annual report describes a summary of each research activity, which has been carried out using the JAEA-Tokai tandem accelerator with the energy booster from April 1, 2006 to March 31, 2007. The forty-eight summary reports were categorized into seven research/development fields, i.e., (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, and (7) radiation effects in materials, in addition, lists of publications, personnel and cooperative researches with universities are contained. Regarding the number of summaries each of the fields is as follows: accelerator operation and development - 11, nuclear structure - 11, nuclear reaction - 6, nuclear chemistry - 5, nuclear theory - 4, atomic physics and solid state physics - 3, radiation effects in materials - 8. The 48 of the presented papers are indexed individually. (J.P.N.)

  11. Free-electron laser research-and-development and utilization program at Tokai, JAERI

    International Nuclear Information System (INIS)

    Kawarasaki, Yuuki

    1992-01-01

    The free-electron laser (FEL) research and development (R and D) and utilization program now underway at the Linac Laboratory, Tokai Research Establishment, JAERI, is presented together with the current status of the R and D. Specific feature of this program is at the points that the R and D period will range over a long time, around a decade, tentatively divided into three developmental phases, aiming at the final utilization in a field of nuclear energy industry and the FEL here under R and D is based on a superconducting (SC) linear accelerator (linac) which will in later phases be incorporated with addition of more SC-cavity modules for beam energy increase and with adoption of rather novel accelerator technique: beam recirculation both for further energy increase and for power economy by beam energy recovery. Application scheme is additionally discussed. (author)

  12. Chemical forms and discharge ratios to stack and sea of tritium from Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Mikami, Satoshi; Akiyama, Kiyomitsu; Miyabe, Kenjiro

    2002-03-01

    Chemical forms and discharge ratios to stack and sea of tritium form Tokai Reprocessing Plant of Japan Nuclear Cycle Development Institute (JNC) were investigated by analyzing monitoring data. It was ascertained that approximately 70-80% of tritium discharged from the main stack was tritiated water vapor (HTO) and approximately 20-30% was tritiated hydrogen (HT) as a result of analyzing the data taken from reprocessing campaign's in 1994, 1995, 1996, 1997, 2000 and 2001, and also that the amount of tritium released from the stack was less than 1% of tritium inventory in spent fuel and the amount of tritium released into sea was approximately 20-40% of inventory. (author)

  13. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:30 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du mardi 15 mars 2011 a 10h30

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 15, 2011, at 10:30 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  14. Analysis of marine samples by neutron-induced prompt gamma-ray technique and ICP-MS

    International Nuclear Information System (INIS)

    Yonezawa, C.; Matsue, H.; McKay, K.; Povinec, P.

    2001-01-01

    Multi-element and isotopic analyses of oils and marine environmental samples were carried out to estimate a contamination source using a 'finger printing' method. Elemental analyses were carried out using neutron-induced prompt gamma-ray analysis (PGA), instrumental neutron activation analysis (INAA) at the Japan Atomic Institute, Tokai-mura, Japan (JAERI) and ICP-MS in the IAEA Marine Environment Laboratory, Monaco (MEL). Fifteen elements including light elements, H, B, N, Si and Ca, which cannot be determined by INAA and ICP-MS, were determined by PGA. A total of 47 elements were determined in the present study. The potential of PGA for the determination of isotopic ratios was tested by measuring 34 S/ 32 S ratios in oils. The evaluation of historical records of marine environmental conditions using annual bands in coral samples was also investigated. (author)

  15. Applicability of simplified methods to evaluate consequences of criticality accident using past accident data

    International Nuclear Information System (INIS)

    Nakajima, Ken

    2003-01-01

    Applicability of four simplified methods to evaluate the consequences of criticality accident was investigated. Fissions in the initial burst and total fissions were evaluated using the simplified methods and those results were compared with the past accident data. The simplified methods give the number of fissions in the initial burst as a function of solution volume; however the accident data did not show such tendency. This would be caused by the lack of accident data for the initial burst with high accuracy. For total fissions, simplified almost reproduced the upper envelope of the accidents. However several accidents, which were beyond the applicable conditions, resulted in the larger total fissions than the evaluations. In particular, the Tokai-mura accident in 1999 gave in the largest total specific fissions, because the activation of cooling system brought the relatively high power for a long time. (author)

  16. Reactor laboratory course for students majoring in nuclear engineering with the Kyoto University Critical Assembly (KUCA)

    International Nuclear Information System (INIS)

    Nishihara, H.; Shiroya, S.; Kanda, K.

    1996-01-01

    With the use of the Kyoto University Critical Assembly (KUCA), a joint reactor laboratory course of graduate level is offered every summer since 1975 by nine associated Japanese universities (Hokkaido University, Tohoku University, Tokyo Institute of Technology, Musashi Institute of Technology, Tokai University, Nagoya University, Osaka University, Kobe University of Mercantile Marine and Kyushu University) in addition to a reactor laboratory course of undergraduate level for Kyoto University. These courses are opened for three weeks (two weeks for the joint course and one week for the undergraduate course) to students majoring in nuclear engineering and a total of 1,360 students have taken the course in the last 21 years. The joint course has been institutionalized with the background that it is extremely difficult for a single university in Japan to have her own research or training reactor. By their effort, the united faculty team of the joint course have succeeded in giving an effective, unique one-week course, taking advantage of their collaboration. Last year, an enquete (questionnaire survey) was conducted to survey the needs for the educational experiments of graduate level and precious data have been obtained for promoting reactor laboratory courses. (author)

  17. Next generation neutron scattering at Neutron Science Center project in JAERI

    International Nuclear Information System (INIS)

    Yamada, Yasusada; Watanabe, Noboru; Niimura, Nobuo; Morii, Yukio; Katano, Susumu; Aizawa, Kazuya; Suzuki, Jun-ichi; Koizumi, Satoshi; Osakabe, Toyotaka.

    1997-01-01

    Japan Atomic Energy Research Institute (JAERI) has promoted neutron scattering researches by means of research reactors in Tokai Research Establishment, and proposes 'Neutron Science Research Center' to develop the future prospect of the Tokai Research Establishment. The scientific fields which will be expected to progress by the neutron scattering experiments carried out at the proposed facility in the Center are surveyed. (author)

  18. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 20, 2011, 6:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 20 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 20, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  19. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 18, 2011, 2:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 18 mars 2011 a 14 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 18, 2011, at 2:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  20. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 17, 2011, 6:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 17 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 17, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  1. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 17, 2011, 3:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 17 mars 2011 a 15 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 17, 2011, at 3:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  2. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 19, 2011, 6:00 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 19 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 19, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  3. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 16, 2011, 7:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 16 mars 2011 a 19 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 16, 2011, at 7:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  4. Accident analysis of heavy water cooled thorium breeder reactor

    International Nuclear Information System (INIS)

    Yulianti, Yanti; Su’ud, Zaki; Takaki, Naoyuki

    2015-01-01

    Thorium has lately attracted considerable attention because it is accumulating as a by-product of large scale rare earth mining. The objective of research is to analyze transient behavior of a heavy water cooled thorium breeder that is designed by Tokai University and Tokyo Institute of Technology. That is oxide fueled, PWR type reactor with heavy water as primary coolant. An example of the optimized core has relatively small moderator to fuel volume ratio (MFR) of 0.6 and the characteristics of the core are burn-up of 67 GWd/t, breeding ratio of 1.08, burn-up reactivity loss during cycles of < 0.2% dk/k, and negative coolant reactivity coefficient. One of the nuclear reactor accidents types examined here is Unprotected Transient over Power (UTOP) due to withdrawing of the control rod that result in the positive reactivity insertion so that the reactor power will increase rapidly. Another accident type is Unprotected Loss of Flow (ULOF) that caused by failure of coolant pumps. To analyze the reactor accidents, neutron distribution calculation in the nuclear reactor is the most important factor. The best expression for the neutron distribution is the Boltzmann transport equation. However, solving this equation is very difficult so that the space-time diffusion equation is commonly used. Usually, space-time diffusion equation is solved by employing a point kinetics approach. However, this approach is less accurate for a spatially heterogeneous nuclear reactor and the nuclear reactor with quite large reactivity input. Direct method is therefore used to solve space-time diffusion equation which consider spatial factor in detail during nuclear reactor accident simulation. Set of equations that obtained from full implicit finite-difference method is solved by using iterative methods. The indication of UTOP accident is decreasing macroscopic absorption cross-section that results large external reactivity, and ULOF accident is indicated by decreasing coolant flow. The

  5. Accident analysis of heavy water cooled thorium breeder reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yulianti, Yanti [Department of Physics, University of Lampung Jl. Sumantri Brojonegoro No.1 Bandar Lampung, Indonesia Email: y-yanti@unila.ac.id (Indonesia); Su’ud, Zaki [Department of Physics, Bandung Institute of Technology Jl. Ganesha 10 Bandung, Indonesia Email: szaki@fi.itb.ac.id (Indonesia); Takaki, Naoyuki [Department of Nuclear Safety Engineering Cooperative Major in Nuclear Energy (Graduate School) 1-28-1 Tamazutsumi,Setagayaku, Tokyo158-8557, Japan Email: ntakaki@tcu.ac.jp (Japan)

    2015-04-16

    Thorium has lately attracted considerable attention because it is accumulating as a by-product of large scale rare earth mining. The objective of research is to analyze transient behavior of a heavy water cooled thorium breeder that is designed by Tokai University and Tokyo Institute of Technology. That is oxide fueled, PWR type reactor with heavy water as primary coolant. An example of the optimized core has relatively small moderator to fuel volume ratio (MFR) of 0.6 and the characteristics of the core are burn-up of 67 GWd/t, breeding ratio of 1.08, burn-up reactivity loss during cycles of < 0.2% dk/k, and negative coolant reactivity coefficient. One of the nuclear reactor accidents types examined here is Unprotected Transient over Power (UTOP) due to withdrawing of the control rod that result in the positive reactivity insertion so that the reactor power will increase rapidly. Another accident type is Unprotected Loss of Flow (ULOF) that caused by failure of coolant pumps. To analyze the reactor accidents, neutron distribution calculation in the nuclear reactor is the most important factor. The best expression for the neutron distribution is the Boltzmann transport equation. However, solving this equation is very difficult so that the space-time diffusion equation is commonly used. Usually, space-time diffusion equation is solved by employing a point kinetics approach. However, this approach is less accurate for a spatially heterogeneous nuclear reactor and the nuclear reactor with quite large reactivity input. Direct method is therefore used to solve space-time diffusion equation which consider spatial factor in detail during nuclear reactor accident simulation. Set of equations that obtained from full implicit finite-difference method is solved by using iterative methods. The indication of UTOP accident is decreasing macroscopic absorption cross-section that results large external reactivity, and ULOF accident is indicated by decreasing coolant flow. The

  6. A review of fast reactor program in Japan

    International Nuclear Information System (INIS)

    1992-01-01

    In accordance with the Long-term Program for Development and Utilization of Nuclear Energy defined by the Japan Atomic Energy Commission (JAEC), Power Reactor and Nuclear Fuel Development Corporation (PNC) is playing the key role in the development of a plutonium utilization system by fast breeder reactor (FBR), which is superior to the uranium utilization system by light water reactor, aiming to achieve future stable long-term energy supply and energy security of Japan. The experimental reactor Joyo, located in the O-arai Engineering Center (OEC) of PNC, has provided abundant experimental data and excellent operational records attaining 43,500 hours operation in total by the end of 1991, since its first criticality in 1977. On the prototype reactor Monju, 97.6% of construction works has already been completed and the function tests are in progress aiming at the initial criticality by the end of FY 1992. As for the demonstration fast breeder reactor (DFBR) of Japan, the Japan Atomic Power Company (JAPC) is promoting design study under the contracts with several leading Japanese fabricators, including Toshiba, Hitachi and Mitsubishi Heavy Industries, for selection of the basic specifications of DFBR. The related research and development (R and D) works are underway at several organizations under the discussion and coordination of the Japanese FBR R and D Steering Committee, which was established by the JAPAC, PNC, Japan Atomic Energy Research Institute (JAERI) and Central Research Institute of Electric Power Industry (CRIEPI). Progress of the design study and the related R and D are reported to the Subcommittee on FBR Development Program of JAEC. Recent major emphases on the PNC R and D are placed on the integrated feedback of all existing R and D results and experiences to the development of demonstration reactor. Furthermore, the overall functional and performance tests of Monju, is another important key role to attain further excellency of FBR technology, with

  7. A review of fast reactor program in Japan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-07-01

    In accordance with the Long-term Program for Development and Utilization of Nuclear Energy defined by the Japan Atomic Energy Commission (JAEC), Power Reactor and Nuclear Fuel Development Corporation (PNC) is playing the key role in the development of a plutonium utilization system by fast breeder reactor (FBR), which is superior to the uranium utilization system by light water reactor, aiming to achieve future stable long-term energy supply and energy security of Japan. The experimental reactor Joyo, located in the O-arai Engineering Center (OEC) of PNC, has provided abundant experimental data and excellent operational records attaining 43,500 hours operation in total by the end of 1991, since its first criticality in 1977. On the prototype reactor Monju, 97.6% of construction works has already been completed and the function tests are in progress aiming at the initial criticality by the end of FY 1992. As for the demonstration fast breeder reactor (DFBR) of Japan, the Japan Atomic Power Company (JAPC) is promoting design study under the contracts with several leading Japanese fabricators, including Toshiba, Hitachi and Mitsubishi Heavy Industries, for selection of the basic specifications of DFBR. The related research and development (R and D) works are underway at several organizations under the discussion and coordination of the Japanese FBR R and D Steering Committee, which was established by the JAPAC, PNC, Japan Atomic Energy Research Institute (JAERI) and Central Research Institute of Electric Power Industry (CRIEPI). Progress of the design study and the related R and D are reported to the Subcommittee on FBR Development Program of JAEC. Recent major emphases on the PNC R and D are placed on the integrated feedback of all existing R and D results and experiences to the development of demonstration reactor. Furthermore, the overall functional and performance tests of Monju, is another important key role to attain further excellency of FBR technology, with

  8. Demonstration of an automated electromanometer for measurement of solution in accountability vessels in the Tokai Reprocessing Plant (part II)

    International Nuclear Information System (INIS)

    Yamonouchi, T.; Fukuari, Y.; Hayashi, M.; Komatsu, M.; Suyama, N.; Uchida, T.

    1982-01-01

    This report describes the results of an operational field test of the automated electromanometer system installed at the input accountability vessel (251V10) and the plutonium product accountability vessel (266V23) in the Tokai Reprocessing Plant. This system has been in use since September 1979 when it was installed in the PNC plant by BNL as part of Task-E, one of the thirteen tasks, in the Tokai Advanced Safeguards Technology Exercise (TASTEX) program. The first report on the progress of this task was published by S. Suda, et al., in the Proceedings of the INMM 22nd Annual Meeting. In this paper, further results of measurement and data analysis are shown. Also, the reliability and applicability of this instrument for accountability, safeguards, and process control purposes are investigated using the data of 106 batches for 251V10 and 40 batches for 266V23 obtained during two campaigns in 1981. There were small but significant differences relative to the plant's measurements for both vessels of 251V10 and 266V23; however, the difference for 251V10 was slightly decreased in the latest vessel calibration. Initially, there were many spurious signals originating with the raw data caused by a software error in the system. However, almost normal conditions were obtained after corrections of the program were made

  9. Treatment results of the Tokai-POSG 8610HR pilot protocol for children with high-risk acute lymphoblastic leukemia

    Energy Technology Data Exchange (ETDEWEB)

    Hongo, Teruaki; Inoue, Noriko [Hamamatsu Medical Univ., Shizuoka (Japan); Horibe, Keizo [and others

    1997-10-01

    We reported the treatment results of Tokai-POSG 8610HR pilot protocol for children with high-risk acute lymphoblastic leukemia (ALL). From Oct. 1986 to Jan. 1991, 43 eligible children were enrolled, who had one or more following high-risk factors: age{>=}10 years old, initial white blood cell count (WBC) of 50,000/{mu}l or more, and extramedullary leukemia. All patients received induction therapy consisting of vincristine, dexamethasone, cyclophosphamide and daunorubicin, followed by central nervous system prophylaxis by 24 Gy cranial irradiation, consolidation therapy and cyclic maintenance by multidrugs for 3 years after diagnosis. Complete remission was achieved in 39 patients. The 5-year event-free survival (EFS) rate was 72.6{+-}7.1%. The only factor of an adverse association with EFS was a initial WBC of 10,000/{mu}l or more (p=0.002) in the 24 patients who were 10 years old or over. The factors related to a negative survival were male gender (p=0.031) and an initial WBC of 10,000/{mu}l or more (p=0.0012) in 43 patients. The major toxicities of the therapy were pancreatitis and allergic reaction due to{sub L}-ASP administration, and growth hormone deficiency due to cranial irradiation. Tokai 8610HR pilot protocol was a promising regimen, but further intensive chemotherapy was needed for improvement or the prognosis of the older patients with high initial WBC greater than 10,000/{mu}l. (author)

  10. Treatment results of the Tokai-POSG 8610HR pilot protocol for children with high-risk acute lymphoblastic leukemia

    International Nuclear Information System (INIS)

    Hongo, Teruaki; Inoue, Noriko; Horibe, Keizo

    1997-01-01

    We reported the treatment results of Tokai-POSG 8610HR pilot protocol for children with high-risk acute lymphoblastic leukemia (ALL). From Oct. 1986 to Jan. 1991, 43 eligible children were enrolled, who had one or more following high-risk factors: age≥10 years old, initial white blood cell count (WBC) of 50,000/μl or more, and extramedullary leukemia. All patients received induction therapy consisting of vincristine, dexamethasone, cyclophosphamide and daunorubicin, followed by central nervous system prophylaxis by 24 Gy cranial irradiation, consolidation therapy and cyclic maintenance by multidrugs for 3 years after diagnosis. Complete remission was achieved in 39 patients. The 5-year event-free survival (EFS) rate was 72.6±7.1%. The only factor of an adverse association with EFS was a initial WBC of 10,000/μl or more (p=0.002) in the 24 patients who were 10 years old or over. The factors related to a negative survival were male gender (p=0.031) and an initial WBC of 10,000/μl or more (p=0.0012) in 43 patients. The major toxicities of the therapy were pancreatitis and allergic reaction due to L -ASP administration, and growth hormone deficiency due to cranial irradiation. Tokai 8610HR pilot protocol was a promising regimen, but further intensive chemotherapy was needed for improvement or the prognosis of the older patients with high initial WBC greater than 10,000/μl. (author)

  11. Evaluation of room-scattered neutrons at the JNC Tokai neutron reference field

    Energy Technology Data Exchange (ETDEWEB)

    Yoshida, Tadayoshi; Tsujimura, Norio [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan). Tokai Works; Oyanagi, Katsumi [Japan Radiation Engineering Co., Ltd., Hitachi, Ibaraki (Japan)

    2002-09-01

    Neutron reference fields for calibrating neutron-measuring devices in JNC Tokai Works are produced by using radionuclide neutron sources, {sup 241}Am-Be and {sup 252}Cf sources. The reference field for calibration includes scattered neutrons from the material surrounding sources, wall, floor and ceiling of the irradiation room. It is, therefore, necessary to evaluate the scattered neutrons contribution and their energy spectra at reference points. Spectral measurements were performed with a set of Bonner multi-sphere spectrometers and the reference fields were characterized in terms of spectral composition and the fractions of room-scattered neutrons. In addition, two techniques stated in ISO 10647, the shadow-cone method and the polynomial fit method, for correcting the contributions from the room-scattered neutrons to the readings of neutron survey instruments were compared. It was found that the two methods gave an equivalent result within a deviation of 3.3% at a source-to-detector distance from 50cm to 500cm. (author)

  12. Evaluation of room-scattered neutrons at the JNC Tokai neutron reference field

    International Nuclear Information System (INIS)

    Yoshida, Tadayoshi; Tsujimura, Norio

    2002-01-01

    Neutron reference fields for calibrating neutron-measuring devices in JNC Tokai Works are produced by using radionuclide neutron sources, 241 Am-Be and 252 Cf sources. The reference field for calibration includes scattered neutrons from the material surrounding sources, wall, floor and ceiling of the irradiation room. It is, therefore, necessary to evaluate the scattered neutrons contribution and their energy spectra at reference points. Spectral measurements were performed with a set of Bonner multi-sphere spectrometers and the reference fields were characterized in terms of spectral composition and the fractions of room-scattered neutrons. In addition, two techniques stated in ISO 10647, the shadow-cone method and the polynomial fit method, for correcting the contributions from the room-scattered neutrons to the readings of neutron survey instruments were compared. It was found that the two methods gave an equivalent result within a deviation of 3.3% at a source-to-detector distance from 50cm to 500cm. (author)

  13. Incineration experiences at the Tsuruga P.S. and outline of the advanced type incineration system at the Tokai No. 2 P.S

    International Nuclear Information System (INIS)

    Yui, K.; Kurihara, Y.; Inoue, S.; Takamori, H.; Karita, Y.

    1987-01-01

    In 1978, the first radwaste incineration plant among Japanese nuclear power stations started its operation at Tsuruga P.S., and the first advanced radwaste incineration plant has been constructed and accomplished the test operation in September 1986. This paper describes the outline of Tsuruga incineration plant and its operation achievements, and the outline of advanced incineration technology, Tokai No. 2 incineration plant and its test operation results

  14. Behavior of iodine in the atmosphere-soil-plant system

    International Nuclear Information System (INIS)

    Muramatsu, Yasuyuki; Yoshida, Satoshi; Uchida, Shigeo

    1996-01-01

    Levels and behavior of radioactive and stable iodine in the environment have been studied to obtain parameter values for the assessment of 129 I released from nuclear facilities. The deposition velocity (V D ) of gaseous iodine from the atmosphere to rice grains (rough rice) was 0.00048 cm 3 g -1 s -1 for CH 3 I and 0.15 cm 3 g -1 s -1 for I 2 . The ratio of the iodine distribution in a grain exposed to CH 3 I was as follows, rough rice : brown rice (hulled rice) : polished rice = 1.0 : 0.49 : 0.38. The distribution ratio in polished rice for CH 3 I was about 20 times higher than that for I 2 . The soil-solution distribution coefficient (K d ) for both I - and IO 3 - varied very widely, i.e. -1 . High values were found in soils having high concentrations of total organic carbon, active-Al and active-Fe (Al and Fe extracted by a mixture of oxalic acid and ammonium oxalate). Andosol, one of the most typical Japanese soils derived from deposits of volcanic ash, showed specifically high K d values. The soil-to-plant transfer factors (or concentration ratio) in the edible parts of crops were in the range 0.0002-0.016. The transfer factors for tomato, sweet potato, carrot, soybeans and rice were significantly lower than their leaf values. The value for rice (polished) was 0.002. Iodine was found to be evaporated from the soil-plant system as CH 3 I. The emission of CH 3 I from rice plants grown on flooded soil was much higher than that from oat plants grown on unflooded soil. The 129 I levels in environmental samples collected in and around Tokai-mura, where a spent nuclear fuel reprocessing plant is located, have been determined by neutron activation analysis. The concentrations of 129 I in surface soils ranged from -1 . The 129 I concentrations in forest soil tended to be higher than those in field soils. Most of the 129 I was retained in the first 10 cm of the surface soil collected from forests in Tokai-mura. (author)

  15. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 13, 2011, 7:00 PM status - updated at 11:00 PM; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 13 mars 2011 a 19 heures - Mis a jour a 23 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 13, 2011, at 7:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2 and 3 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  16. Stable iodine contents in human milk related to dietary algae consumption

    International Nuclear Information System (INIS)

    Muramatsu, Yasuyuki; Sumiya, Misako; Ohmomo, Yoichiro

    1983-01-01

    Studies were carried out to investigate iodine contents in human milk with relation to dietary algae consumption by nursing women and to estimate stable iodine intake by breast-fed babies. The iodine contents in human milk collected from the Tokai-mura area showed a fairly wide variation ranging from 80 to 7,000 μg/l, though the highest frequency was around 150 μg/l. It was observed that high contents were closely related to the intake of tangle (Konbu), Laminariaceae, specifically tangle stock and/or tangle shavings (Tororokonbu) as soup. The temporal increase was followed by the rapid decrease when the mothers stopped taking the tangle stock and/or tangle shavings soup. It was observed that water-extractability of iodine from tangle was much higher than that from the other algae, and the water-extractable iodine was absorbable to the human body. (author)

  17. Analysis of neutron propagation from the skyshine port of a fusion neutron source facility

    Energy Technology Data Exchange (ETDEWEB)

    Wakisaka, M. [Hokkaido University, Kita-8, Nishi-5, Kita-ku, Sapporo 080-8628 (Japan); Kaneko, J. [Hokkaido University, Kita-8, Nishi-5, Kita-ku, Sapporo 080-8628 (Japan)]. E-mail: kin@qe.eng.hokudai.ac.jp; Fujita, F. [Hokkaido University, Kita-8, Nishi-5, Kita-ku, Sapporo 080-8628 (Japan); Ochiai, K. [Japan Atomic Energy Institute, Tokai-mura, Ibaraki-ken 319-1195 (Japan); Nishitani, T. [Japan Atomic Energy Institute, Tokai-mura, Ibaraki-ken 319-1195 (Japan); Yoshida, S. [Tokai University, 1117 Kitakaname, Hirastuka, Kanagawa-ken 259-1292 (Japan); Sawamura, T. [Hokkaido University, Kita-8, Nishi-5, Kita-ku, Sapporo 080-8628 (Japan)

    2005-12-01

    The process of neutron leaking from a 14MeV neutron source facility was analyzed by calculations and experiments. The experiments were performed at the Fusion Neutron Source (FNS) facility of the Japan Atomic Energy Institute, Tokai-mura, Japan, which has a port on the roof for skyshine experiments, and a {sup 3}He counter surrounded with a polyethylene moderator of different thicknesses was used to estimate the energy spectra and dose distributions. The {sup 3}He counter with a 3-cm-thick moderator was also used for dose measurements, and the doses evaluated by the counter counts and the calculated count-to-dose conversion factor agreed with the calculations to within {approx}30%. The dose distribution was found to fit a simple analytical expression, D(r)=Q{sub D}exp(-r/{lambda}{sub D})r and the parameters Q{sub D} and {lambda}{sub D} are discussed.

  18. Case examples of chemical plant accidents. What we learn from them?

    International Nuclear Information System (INIS)

    Nakamura, Masayoshi

    2009-01-01

    Lessons learned from the JCO Nuclear Criticality Accident of 30 September 1999 in a uranium conversion test plant in Tokai-mura, Japan, are reviewed by referring some pertinent matters from the official report of this accident to remind of the universal characteristics among possible accidents of chemical plants. The paper discusses the responsibility of the establishment or institution to the demand alternation or request change from the client, how to respond to the proposal arising from the factory floor, and the safety control system of every-day maintenance of the factory which are important to prevent accidents in chemical plants. After explaining a background leading to the JCO accident, the author summarizes the lessons as follows: (1) changeable control system, (2) perfect provision of the manual considering the actual condition, and (3) clarification of the roles each played by the managers and the workers are most necessary and important. (S. Ohno)

  19. The technological study on the decommissioning of nuclear facility, etc. in the Tokai Research Establishment

    International Nuclear Information System (INIS)

    Tomii, Hiroyuki; Matsuo, Kiyoshi; Shiraishi, Kunio; Kato, Rokuro; Watabe, Kozou; Higashiyama, Yutaka; Nagane, Satoru

    2005-03-01

    Since JPDR is dismantled and is removed, in Tokai Research Establishment, Japan Atomic Energy Research Institute, the dismantling of nuclear facility which finished the mission, etc. is advanced. At present, nuclear facility as a dismantling object count the approximately 20 facilities, and decommissioning plan of these facilities becomes an important problem, when the decommissioning countermeasure is considered. However, decommissioning techniques in proportion to various nuclear facility, etc. are clearly, and it has not been determined. In this report, the technical consideration on decommissioning techniques of nuclear facility promoted on the basis of this experience in future, while until now decommissioning experience and technical knowledge are arranged, etc. was added in order to appropriately and surely carry out decommissioning techniques and legal procedures, etc. (author)

  20. Sorption of plutonium and americium on repository, backfill and geological materials relevant to the JNFL low-level radioactive waste repository at Rokkasho-Mura

    International Nuclear Information System (INIS)

    Baston, G.M.N.; Berry, J.A.; Brownsword, M.; Heath, T.G.; Tweed, C.J.; Williams, S.J.

    1995-01-01

    An integrated program of batch sorption experiments and mathematical modeling has been carried out to study the sorption of plutonium and americium on a series of repository, backfill and geological materials relevant to the JNFL low-level radioactive waste repository at Rokkasho-Mura. The sorption of plutonium and americium on samples of concrete, mortar, sand/bentonite, tuff, sandstone and cover soil has been investigated. In addition, specimens of bitumen, cation and anion exchange resins, and polyester were chemically degraded. The resulting degradation product solutions, alongside solutions of humic and isosaccharinic acids were used to study the effects on plutonium sorption onto concrete, sand/bentonite and sandstone. The sorption behavior of plutonium and americium has been modeled using the geochemical speciation program HARPHRQ in conjunction with the HATCHES database

  1. Database structure and file layout of Nuclear Power Plant Database. Database for design information on Light Water Reactors in Japan

    International Nuclear Information System (INIS)

    Yamamoto, Nobuo; Izumi, Fumio.

    1995-12-01

    The Nuclear Power Plant Database (PPD) has been developed at the Japan Atomic Energy Research Institute (JAERI) to provide plant design information on domestic Light Water Reactors (LWRs) to be used for nuclear safety research and so forth. This database can run on the main frame computer in the JAERI Tokai Establishment. The PPD contains the information on the plant design concepts, the numbers, capacities, materials, structures and types of equipment and components, etc, based on the safety analysis reports of the domestic LWRs. This report describes the details of the PPD focusing on the database structure and layout of data files so that the users can utilize it efficiently. (author)

  2. Brief note and evaluation of acute-radiation syndrome and treatment of a Tokai-mura criticality accident patient

    Energy Technology Data Exchange (ETDEWEB)

    Ishii, Takeshi; Futami, Satoru; Nishida, Masamichi; Suzuki, Toru; Sakamoto, Tetsuya; Suzuki, Norio; Maekawa, Kazuhiko [Tokyo Univ. (Japan). Graduate School of Medicine

    2001-09-01

    Patient A who was exposed to a critical dose of radiation developed skin lesions throughout the body surface, gastrointestinal disorder with massive diarrhea and prominent bleeding, which caused severe loss in body fluids. Gastrointestinal bleeding due to the deteriorated intestinal mucosa was considered to be one of the major causes of death, although infection did not develop, possibly because of SDD and aseptic intensive care, until terminal stages. Patient A ultimately developed respiratory and renal failure in addition to skin exudate and gastrointestinal bleeding, and died of multiple organ failure on the 83rd day after exposure. The extreme unevenness of the dose distribution and the neutron versus {gamma}-ray component made the clinical manifestation very complicated. Initially, the mean absorbed dose was calculated as 16-20 GyEq for Patient A, mainly based on neutron-activated {sup 24}Na in the blood. However, a very recent calculation showed that the absorbed skin dose was highest at the upper-right abdomen reaching 61.8 Gy (27.0 as neutron plus 34.8 Gy as {gamma}-ray). The dorsal side was calculated to have received one eighth of the value of the abdominal side, and much smaller neutron component. His absorbed-dose distribution throughout the body was very inhomogeneous because of the closeness of the standing point to the mixing tank. Despite prolonged survival because of intensive care with massive fluids and blood transfusion, peripheral blood stem-cell transplantation, cultured skin-cell grafts, and the administration of cytokines for marrow, the patient was not saved. Restoration of the bone marrow function, prevention of skin fibrosis, radiation lung damage, and repair of gastrointestinal mucosa, and final recovery of the patient were elusive. Abundant personnel and resources were also a prerequisite to allow for the comprehensive and collective intensive care. A further understanding of the effects of high-dose radiation as well as the basic and clinical development of regeneration medicine are important issues for the future. (author)

  3. Crud removal with deep bed type condensate demineralizer in Tokai-2 BWR

    International Nuclear Information System (INIS)

    Abe, Ayumi; Takiguchi, Hideki; Numata, Kunio; Saito, Toshihiko

    1996-01-01

    The major objective and functions for the installation of the deep bed type condensate polishers in BWR power plants is to remove both ionic impurities caused by sea water leakage and suspended impurities called crud mainly consisting of metal oxides which are produced from metal corrosion. In considering the reduction of occupational radiation exposure level, it is extremely important to remove the crud effectively. In recent Japanese BWR power plants, condensate pre-filters with powdered ion exchange resins or with hollow fiber membrane have been installed to remove the crud at the upper stream of the deep bed polishers. In such plants, the crud removal is conventionally the secondary objective for the deep bed polishers. The Japan Atomic Power Company has introduced the small particle ion exchange resin and a soak regeneration method since April 1985, and then applied the low cross-linked resin since July 1995 at Tokai-2 Power Station, to improve the crud removal performance by using only deep bed type condensate demineralizer, and as a result condensate demineralizer outlet iron level has been kept below 1 ppb since 1991

  4. Evaporation of low-activity-level liquid waste at Tokai Reprocessing Plant, 1

    International Nuclear Information System (INIS)

    Nojima, Yasuo; Nemoto, Yuichi; Fukushima, Misao; Shibuya, Jun; Miyahara, Kenji

    1983-01-01

    The operation of Tokai reprocessing plant started in 1977. The determination of the decontamination factors (DF) of the evaporators for low activity level liquid waste (LALW) has been made through the operation. This paper deals with the examination of the first evaporator located at the LALW treatment plant. The operational principle and condition of the evaporator system are briefly explained. The effects of wire-mesh demisters and liquid properties on the decontamination factor were examined in this study. The results are summarized as follows: (1) The DF decreased with the increasing vapor mass velocity on account of entrainment. (2) The DF was able to be improved by using wire-mesh demisters when the vapor mass velocity was less than 2,500 kg/m 2 h. Practically, the most suitable vapor velocity for the evaporator was around 2,000 kg/m 2 h. (3) The DF in the evaporator for 137 Cs, 144 Ce, 90 Sr and 106 Ru was between 10 3 and 10 4 . Regarding 106 Ru, the DF in acid evaporation was less than that in alkaline evaporation. (Aoki, K.)

  5. The origin of volcanic rock fragments in Upper Pliocene Grad Member of the Mura Formation, North-Eastern Slovenia

    Directory of Open Access Journals (Sweden)

    Polona Kralj

    2006-12-01

    Full Text Available Fresh-water, coarse-grained and detritus-dominated Mura Formation in North Eastern Slovenia includes pyroclastic and volcaniclastic deposits originating from Upper Pliocene volcanic activity of basaltic geochemical character. Although localized in occurrence at the hamlet Grad, these pyroclastic and volcaniclastic sediments forma distinctive depositional unit, for which the term “Grad Member” is proposed and introduced in this paper.In the Grad area no lavas or cinder cones are preserved, and the origin of volcaniclastic fragments still uncertain. For this reason, chemical composition of basaltic rock fragments from the Grad Member volcaniclastics has been studied and compared with basaltic rocks from the neighboring locations at Klöch, Kindsberg, Dölling and Neuhaus. The Grad Member pyroclastic and volcaniclastic deposits seem to be fed from the same source which is different from the occurrences in Austria. That supports the idea about the existence of a local volcanic centre in the present Grad area. The old volcanic edificeswerepossiblydestroyed by the late-stage hydrovolcanic eruptions, and pyroclastic and volcaniclastic deposits subjected to constant reworking by fluvial currents in a dynamic sedimentary environment of alluvial fan and braided river systems.

  6. Beyond the ENDF format: A modern nuclear database structure. SG38 meeting, JAEA Tokai site, 9-11 December 2013

    International Nuclear Information System (INIS)

    Fukahori, T.; McNabb, D.; Mattoon, C.; Kugo, T.; Yokoyama, K.; Suyama, K.; Nishihara, K.; Konno, C.; Sato, T.; Brown, D.; White, M.; Beck, B.; Sinitsa, V.; Dunn, M.

    2013-12-01

    WPEC subgroup 38 (SG38) was formed to develop a new structure for storing nuclear reaction data, that is meant to eventually replace ENDF-6 as the standard way to store and share evaluations. The work of SG38 covers the following tasks: Designing flexible, general-purpose data containers; Determining a logical and easy-to-understand top-level hierarchy for storing evaluated nuclear reaction data; Creating a particle database for storing particles, masses and level schemes; Specifying the infrastructure (plotting, processing, etc.) that must accompany the new structure; Developing an Application Programming Interface or API to allow other codes to access data stored in the new structure; Specifying what tests need to be implemented for quality assurance of the new structure and associated infrastructure; Ensuring documentation and governance of the structure and associated infrastructure. This document is the proceedings of the third subgroup meeting which took place at the Tokai site of the Japan Atomic Energy Agency (JAEA) in Japan, on 9-11 December 2013 It comprises all the available presentations (slides) given by the participants as well as one draft paper: A - Introduction: - Welcome (T. Fukahori); - Reviewing our implementation plan (D. McNabb); - Overview of the SG38 wiki (C. Mattoon); B - Feedback from nuclear data users: - Application of nuclear data to light water reactor core analysis (T. Kugo); - Application of nuclear data to fast reactor analysis and design (K. Yokoyama); - Request for the format of the evaluated nuclear data file for the criticality safety evaluation (K. Suyama); - Sensitivity and uncertainty analysis for a minor-actinide transmuter with JENDL- 4.0 (K. Nishihara); - Application of nuclear data libraries in fusion neutronics and some comments (C. Konno); - Particle and heavy ion transport code system PHITS (T. Sato); C - Review of the project sub-tasks: - Top level organization of nuclear data (D. Brown); Documentation: Requirements

  7. Operating experience and development of fluidized-bed denitrators for UNH at Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Sasaki, Minoru; Nakamichi, Hideya; Takeda, Seiichiro; Kubota, Kanya; Katoh, Shuji

    1983-01-01

    The fluidized bed denitrator for uranyl nitrate hexahydrate (UNH) at Tokai reprocessing plant has been operated since 1976. About 170 tons of spent fuel have been reprocessed, and the denitrator has encountered numerous operational problems during the period. This report deals with these technical problems and the associated countermeasures taken, including the dismantling and reconstruction of equipment and the improvement of operating method. The major problems encountered were as follows: (1) the crystallization of UNH on the UNH feeding line, (2) spray nozzle clogging and candle filter clogging, (3) particle growth, (4) plugging of the drawing-out line by nozzle caking, and (5) slugging in fluidized-bed denitration. The total quantity and quality of UO 3 products obtained so far at the plant are also briefly described together with some future R and D programs such as the improvement of UO 3 reactivity and the automation of denitrators. (Aoki, K.)

  8. Atividade pesqueira dos índios Mura no Lago Ayapuá, Baixo Rio Purus, Amazonas, Brasil

    Directory of Open Access Journals (Sweden)

    Artur Bicelli Coimbra, M.Sc.

    2017-03-01

    Full Text Available The artisanal fisheries has great importance forthe Amazonian indigenous communities, as a form of subsistence, and for the cultural and tradition of these communities. In this study, we analyzed the fishery developed in four indigenous communities of the Mura people indigenous of the Lake Ayapuá Land,in the lower Purus River. The fishes were classified according to the composition and importance of the species in weight and number of DOI: http://dx.doi.org/10.20873/uft.2359-3652.2017v4n1p115Revista Desafios –v. 04, n. 1, 2017116individuals, structure and size of the individuals captured, and total weight of the catches, between October and December of 2008. The most commercialized species were the Aruanã (Osteoglossumbicirrhosum, the pescada (Plagioscionsquamosissimus, the "feras" or big catfish (dourada, Brachyplatystomarousseauxiiand the filhote Brachyplatystomafilamentosum and the tucunaré (Cichlamonoculus. The most commonly consumed species were aruanã, tucunaré, piranha-caju (Pygocentrusnattereri and acará-açu (Astronotuscrassipinni. Species such as tucunaré and pescada have catch sizes within the standards permitted by legislation. However, acará-açu, aruanã, tambaqui (Colossomamacropomum, surubim (Pseudoplatystomapunctifer, caparari (Pseudoplatystomatigrinum, filhote and dourada do not have the same legal standard. Most of the production (87% was destined for commercialization with Fish buyer. Preventive and mitigating measures are proposed to ensure the permanence of fish stocks and consequently the sustainability of fishing and the maintenance of the local population.

  9. An emergent proposal on the Committee of Uranium Processing Factory Criticality Accident Survey of the Nuclear Safety Commission. A meantime report dated on November 5, 1999

    International Nuclear Information System (INIS)

    2000-01-01

    The Nuclear Safety Commission was received a decision on thorough investigations of accident reason on criticality accident at the Tokai-mura uranium processing factory of the JCO Incorporation occurred on September 30, 1999, to establish the Committee of Uranium Processing Factory Criticality Accident Survey to elucidate its reason thoroughly and contribute to set up a sufficient reforming prevention countermeasure. This Committee judged that it was important to propose a countermeasure directly obtainable by grasping some fact relations clarified before now as soon as possible and intended to conduct this meantime report of 'emergent proposal' by arrangement of such fact relations. Here were described on accidental conditions and their effects, response to the accident (on prevention of the accident), its reasons and their relating conditions, and some emergent proposals. In the last items, safety security at accidental site, health countermeasures to residents and others, establishment of safety security for nuclear business workers and others, and reconstruction on safety regulation in national government. (G.K.)

  10. Understanding human and organisational factors - Nuclear safety and at-risk organisations

    International Nuclear Information System (INIS)

    Bernard, Benoit

    2014-01-01

    This book addresses human and organisational factors which are present at different moments of the lifetime of an at-risk installation (from design to dismantling). At-risk organisations are considered as firstly human systems, and the objective is then to highlight individual and collective mechanisms in these organisations. Several questions are addressed, notably the origins of at-risk behaviour, and the reasons of the repetition of errors by these organisations. A first chapter, while referring to examples, addresses the human dimension of safety: human and organisational factors as obstacles, normal accidents (Three Mile Island), accidents in high-reliability organisations (Chernobyl), identification of root causes (Tokai-mura), and social-technical approach to safety (Fukushima). By also referring to examples, the second chapter addresses how to analyse at-risk organisations: individual behaviours (case of naval and air transport accidents), team coordination (a fire, the Challenger accident), and organisational regulation (organisations forms and routines, explosion of BP Texas City, explosion of Columbia)

  11. Proceedings of the 4th seminar of R and D on advanced ORIENT 'strategy and technical requirement for new resource of noble metals in advanced atomic energy science'

    International Nuclear Information System (INIS)

    Sasaki, Yuji; Koyama, Shinichi; Ozawa, Masaki

    2010-12-01

    The 4th Seminar of R and D on advanced ORIENT, 'Strategy and technical requirement for new resource of noble metals in advanced atomic energy science' was held in Swany hall, Rokkasho-Mura, on July 30th, 2010 organized by Japan Atomic Energy Agency. The first meeting of this seminar was held at Oarai, Ibaraki on May, 2007, the second seminar was held at Tokai, on November, 2008, and the third seminar was held at Sendai, on October, 2009. Spent nuclear fuel should be recognized as not only mass of radioactive elements but also potentially useful materials including platinum metals and rare earth elements. Taking the cooperation with universities related companies and research institutes, into consideration, we aimed at expanding and progressing the basic researches. In this seminar, there are many poster presentation included, and the useful discussion with many students are performed. This report records abstracts and figures submitted from the oral speakers in this seminar. (author)

  12. Public opinion on atomic energy after JCO accident

    International Nuclear Information System (INIS)

    Okamoto, Koichi; Miyamoto, Sosuke; Ishikawa, Masayori; Shimomura, Hideo; Hori, Hiromoto; Suzuki, Yasuko; Kamise, Yumiko

    2004-04-01

    JCO accident happened on September 30, 1999. This book deals with the public opinion of atomic energy after JCO accident in Japan and comparison with that of USA and France. The analysis of public opinion structure is also shown. The important chapter is the eighth chapter a n opinion survey after the accident , of which sampling areas consisted of three areas such as JCO accident area, the nuclear power plants and the general cities. The analytical results of data showed that the public opinion in Tokai-mura and Naka-machi, the JCO accident area, indicated moderate opinions. It is the interesting results were obtained that the moderate tendency of opinion was in order JCO accident area, the nuclear power plants and the general cities. People's attitude toward nuclear energy related to their social values. Abstract of JCO accident, JCO structure, the effects of accident on the environment and news stories about the accident are reported. (S.Y.)

  13. Proceedings of the 4th seminar of R and D on advanced ORIENT 'strategy and technical requirement for new resource of noble metals in advanced atomic energy science'

    Energy Technology Data Exchange (ETDEWEB)

    Sasaki, Yuji; Koyama, Shinichi; Ozawa, Masaki [Japan Atomic Energy Agency, Nuclear Science and Engineering Directorate, Tokai, Ibaraki (Japan)

    2010-12-15

    The 4th Seminar of R and D on advanced ORIENT, 'Strategy and technical requirement for new resource of noble metals in advanced atomic energy science' was held in Swany hall, Rokkasho-Mura, on July 30th, 2010 organized by Japan Atomic Energy Agency. The first meeting of this seminar was held at Oarai, Ibaraki on May, 2007, the second seminar was held at Tokai, on November, 2008, and the third seminar was held at Sendai, on October, 2009. Spent nuclear fuel should be recognized as not only mass of radioactive elements but also potentially useful materials including platinum metals and rare earth elements. Taking the cooperation with universities related companies and research institutes, into consideration, we aimed at expanding and progressing the basic researches. In this seminar, there are many poster presentation included, and the useful discussion with many students are performed. This report records abstracts and figures submitted from the oral speakers in this seminar. (author)

  14. Comparative genomics study for the identification of drug and vaccine targets in Staphylococcus aureus: MurA ligase enzyme as a proposed candidate.

    Science.gov (United States)

    Ghosh, Soma; Prava, Jyoti; Samal, Himanshu Bhusan; Suar, Mrutyunjay; Mahapatra, Rajani Kanta

    2014-06-01

    Now-a-days increasing emergence of antibiotic-resistant pathogenic microorganisms is one of the biggest challenges for management of disease. In the present study comparative genomics, metabolic pathways analysis and additional parameters were defined for the identification of 94 non-homologous essential proteins in Staphylococcus aureus genome. Further study prioritized 19 proteins as vaccine candidates where as druggability study reports 34 proteins suitable as drug targets. Enzymes from peptidoglycan biosynthesis, folate biosynthesis were identified as candidates for drug development. Furthermore, bacterial secretory proteins and few hypothetical proteins identified in our analysis fulfill the criteria of vaccine candidates. As a case study, we built a homology model of one of the potential drug target, MurA ligase, using MODELLER (9v12) software. The model has been further selected for in silico docking study with inhibitors from the DrugBank database. Results from this study could facilitate selection of proteins for entry into drug design and vaccine production pipelines. Copyright © 2014 Elsevier B.V. All rights reserved.

  15. Implementasi Fatwa DSN-MUI Terhadap Praktik Pembiayaan Murabahah Bank Syariah Mandiri dan Bank Muamalat KCP Ponorogo

    Directory of Open Access Journals (Sweden)

    Abdul Latif

    2016-03-01

    Full Text Available Abstract: Mura>bah}ah is the flagship product of Bank Syariah Mandiri Branch Office Ponorogo and Bank Muamalat Indonesia Branch Office Ponorogo. Currently, the percentage of mura>bah}ah financing at Bank Syariah Mandiri and Bank Muamalat almost reaches an average of 60% -70% of the total financing. Mura>bah}ah helps customers to finance certain needs. This study examines the financing mechanism of mura>bah}ah at Bank Syariah Mandiri and Bank Muamalat Ponorogo, and how the implementation of the fatwa of the National Sharia Board of Indonesian Ulema Council (DSN-MUI on the practice of mura>bah}ah financing. The study concluded that the mura>bah}ah financing at Bank Syariah Mandiri and Bank Muamalat Ponorogo practices the finance of mura>bah{ah bi al-waka>lah or mura>bah{ah by proxy. Therefore, the identity of this transaction becomes unclear and ambiguous between sale and loans. That is because the products offered by the bank are not goods to purchase, but financing limit. As the result, the mura>bah{ah financing in Bank Syariah Mandiri Ponorogo and Bank Muamalat Indonesia Ponorogo are not fully in accordance with the fatwa  of DSN-MUI on mura>bah}ah. Abstrak: Akad mura>bah{ah menjadi produk unggulan di Bank Syariah Mandiri dan Bank Muamalat KCP Ponorogo. Saat ini prosentase pembiayaan mura>bah{ah di BSM dan Bank Muamalat hampir rata-rata mencapai 60%-70% dari pembiayaan lainnya. Pembiayaan mura>bah{ah ini umumnya bertujuan untuk membantu pembeli dalam pengadaan objek tertentu di mana pembeli tidak memiliki kemampuan keuangan yang cukup untuk melakukan pembiayaan secara tunai. Penelitian ini mengkaji mekanisme pembiayaan mura>bah{ahdi BSM dan BMI KCP Ponorogo, dan bagaimana implementasi fatwa DSN-MUI terhadapa praktik pembiayaan mura>bah}ah. Temuan dalam penelitian ini bahwa, praktik pembiayaan mura>bah{ah di Bank Syariah Mandiri dan Bank Muamalat KCP Ponorogo menggunakan pembiayaan mura>bah{ah bil wakalah{ atau dengan mura>bah{ah yang

  16. Chromosome aberration analysis in persons exposed to low-level radiation from the JCO criticality accident in Tokai-mura

    International Nuclear Information System (INIS)

    Sasaki, Masao S.; Hayata, Isamu; Kamada, Nanao; Kodama, Yoshiaki; Kodama, Seiji

    2001-01-01

    Chromosome aberrations were studied in peripheral blood lymphocytes of 43 persons who were exposed to low-level radiation of mixed neutrons and γ-rays resulting from the JCO criticality accident. When the age-adjusted frequencies of dicentric and ring chromosomes were compared with the dose calibration curve established in vitro for 60 Co γ-rays as a reference radiation, a significant correlation was observed between the chromosomally estimated doses and the documented doses evaluated by physical means. The regression coefficient of the chromosomal doses against the documented doses, 1.47±0.33, indicates that the relative biological effectiveness of fission neutrons at low doses is considerably higher than that currently adopted in the radiation protection standard. (author)

  17. Nuclear situation in Japan

    International Nuclear Information System (INIS)

    2006-01-01

    This analysis takes stock on the nuclear situation in Japan. It discusses the ambitious equipment program in collaboration with the France, the destabilization of the japanese nuclear industry following the accidents and the energy policy evolutions. It presents the projects of the japanese nuclear industry: the Monju reactor restart, the Pluthermal project, the reprocessing power plant of Rokkasho Mura, the new reactors, the russian weapons dismantling, the ITER site selection and the buy out of Westinghouse by Toshiba. (A.L.B.)

  18. Nuclear situation in Japan; La situation du nucleaire au Japon

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This analysis takes stock on the nuclear situation in Japan. It discusses the ambitious equipment program in collaboration with the France, the destabilization of the japanese nuclear industry following the accidents and the energy policy evolutions. It presents the projects of the japanese nuclear industry: the Monju reactor restart, the Pluthermal project, the reprocessing power plant of Rokkasho Mura, the new reactors, the russian weapons dismantling, the ITER site selection and the buy out of Westinghouse by Toshiba. (A.L.B.)

  19. Surveillance system using the CCTV at the fuel transfer pond in the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Hayakawa, T.; Fukuhara, J.; Ochiai, K.; Ohnishi, T.; Ogata, Y.; Okamoto, H.

    1991-01-01

    The Fuel Transfer Pond (FTP) in the Tokai Reprocessing Plant (TRP) is a strategic point for safeguards. Spent fuels, therefore, in the FTP have been surveyed by the surveillance system using the underwater CCTV. This system was developed through the improvement of devices composed of cameras and VCRs and the provision of tamper resistance function as one of the JASPAS (Japan Support Program for Agency Safeguards) program. The purpose of this program is to realize the continuous surveillance of the slanted tunnel through which the spent fuel on the conveyor is moved from the FTP to the Mechanical Processing Cell (MPC). This paper reports that, when this surveillance system is applied to an inspection device, the following requirements are needed: To have the ability of continuous and unattended surveillance of the spent fuel on the conveyor path from the FTP to the MPC; To have the tamper resistance function for continuous and unattended surveillance of the spent fuel

  20. Aspiration toward geothermal energy utilization in regional development plan. Part 6. ; Hydrothermal fluid utilization business in Matsuo-mura of Iwate prefecture. Chiiki keikaku ni okeru 'chinetsu riyo' eno hofu. 6. ; Iwateken Matsuomura no chinetsu nessui riyo jigyo

    Energy Technology Data Exchange (ETDEWEB)

    Otobe, Y; Furutate, E

    1992-10-31

    Twenty six years have passed since the first geothermal power station was constructed in Matsuo-mura of Iwate Prefecture, Japan. This paper describes the history, the present situation and the future conception of the geothermal energy utilization in this village. This village includes Hachimantai of a vantage ground in the center and has the gross area of 233.8km[sup 2], the annual average temperature of 8.3 centigrade and the continuous snow cover period of about 100 days. The hot water leading facility was cooperatively constructed by Japan Metals and Chemicals, Hachimantai Hot Spring Development and Matsuo-mura. The total working expense is 539.3 million yen. Hot water sources are the condensate from the condenser of geothermal power plant and hot spring. This mixed hot water of 4.3 t/min is led to respective facilities. The hot water supplying channel has the length of 12.8km from the power station through the Hachimantai hot spring resort, Kamiyogi to Takaishino. Respective total areas of greenhouses using hydrothermal fluid in both districts are 1,075ha and the inlet temperature of hot water is 60 centigrade and kinds of crop are 5 like green pepper and others. Takaishino agricultural park has selected flower and ornamental plant culture such as poppy anemone, stock and statice which are suitable for this district of low temperature and insufficient sunshine. The planted area is 10,700m[sup 2]. 2 refs., 9 figs., 4 tabs.

  1. Accidents and troubles in nuclear fuel facilities in fiscal year 1987

    International Nuclear Information System (INIS)

    1988-01-01

    The number of the accidents and troubles reported in fiscal year 1987 in relation to nuclear fuel facilities based on the stipulation of the law on the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors was two. In Tokai Works, Power Reactor and Nuclear Fuel Development Corp., on September 17, 1987, the conveyor for transporting spent fuel in the separation and refining shop of the reprocessing plant broke down, consequently, the operation of the reprocessing plant was stopped for about five months. In Tokai Testing Works, Mitsubishi Heavy Industries Ltd., on February 7, 1988, a worker who was putting up posters in the control area of the uranium experiment facilities fell from a stepladder, and required treatment by entering a hospital for about one month, suffering bone fracture. (K.I.)

  2. Report of the third seminar on nuclear physics at the energy region of the JAERI tandem-booster accelerator February 27-28, 1992, Tokai, Japan

    International Nuclear Information System (INIS)

    Iwamoto, Akira; Oshima, Masumi; Ikezoe, Hiroshi; Nagame, Yuichiro; Shinohara, Nobuo

    1992-09-01

    A seminar on new experiments to be studied and new experimental apparatus suitable for the JAERI tandem-booster accelerator being under construction was held at Tokai Research Establishment of JAERI in the period from February 27 to 28, 1992. Sixty eight participants from universities and from JAERI attended to discuss the following items: 1. Physics at low temperature, 2. Nuclear structure at high spin and at high excitation energy, 3. Application of unstable beam and their spectroscopy, 4. Nuclear reaction at intermediate energy, 5. New facilities. (author)

  3. Measurement of mean radon concentrations in the Tokai districts

    International Nuclear Information System (INIS)

    Iida, Takao; Ikebe, Yukimasa; Yamanishi, Hirokuni

    1989-01-01

    This paper describes an electrostatic integrating radon monitor designed for the environmental radon monitoring and longterm measurements of mean radon concentrations in outdoor and indoor air. The position of the collecting electrode within the monitor was determined based on the calculation of the internal electric field. The radon exchange rate between the monitor and the outside air through the filter was 0.75 h -1 . The exchange rate can make the radon concentration inside the monitor to follow thoroughly the outside concentration. Since the electrostatic collection of RaA + ( 218 Po + ) atoms depends on the humidity of the air, the inside of the monitor was dehumidified with a diphosphorus pentaoxide (P 2 O 5 ) drying agent which is powerful and dose not absorb radon gas. From the relationship between track density and radon exposure, the calibration factor was derived to be 0.52 ± 0.002 tracks cm -2 (Bq m -3 h) -1 . The detection limit of mean radon level is 1.2 Bq m -3 for an exposure time fo 2 months. The mean radon concentrations in various environments were measured through the year using the monitors this developed. The annual mean outdoor radon level in the Tokai districts was 7.0 Bq m -3 . The mean radon concentrations was found to vary from 3.5 to 11.7 Bq m -3 depending upon the geographical conditions even in this relatively small region. The annual indoor radon concentrations at Nagoya and Sapporo ranged from 6.4 to 11.9 Bq m -3 and from 15.5 to 121.1 Bq m -3 , respectively, with the type of building material and the ventilation rate. The mean radon concentrations in tightly built houses selected at Sapporo are about 10 times as high as those in drafty houses at Nagoya. (author)

  4. Monitoring of low-level radioactive liquid effluent in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Mizutani, Tomoko; Koarashi, Jun; Takeishi, Minoru

    2009-01-01

    The Tokai reprocessing plant (TRP), the first reprocessing plant in Japan, has discharged low-level liquid wastes to the Pacific Ocean since the start of its operation in 1977. We have performed liquid effluent monitoring to realize an appropriate radioactive discharge control. Comparing simple and rapid analytical methods with labor-intensive radiochemical analyses demonstrated that the gross-alpha and gross-beta activities agreed well with the total activities of plutonium isotopes ( 238 Pu and 239+240 Pu) and major beta emitters (e.g., 90 Sr and 137 Cs), respectively. The records of the radioactive liquid discharge from the TRP showed that the normalized discharges of all nuclides, except for 3 H, were three or four orders of magnitude lower than those from the Sellafield and La Hague reprocessing plants. This was probably due to the installation of multistage evaporators in the liquid waste treatment process in 1980. The annual public doses for a hypothetical person were estimated to be less than 0.2 μSv y -1 from the aquatic pathway. Plutonium radioactivity ratios ( 238 Pu/ 239+240 Pu) of liquid effluents were determined to be 1.3-3.7, while those of the seabed sediment samples collected around the discharge point were 0.003-0.059, indicating no remarkable accumulation of plutonium in the regional aquatic environment. Thus, we concluded that there were no significant radiological effects on the public and the aquatic environment during the past 30-year operation of the TRP. (author)

  5. Safety Assessment in the AREVA Group: Operating Experience from a Self-Assessment Tool

    International Nuclear Information System (INIS)

    Coye de Brunélis, T.; Mignot, E.; Sidaner, J.-F.

    2016-01-01

    The expression “safety culture” first appeared following analysis of the Chernobyl accident in 1986. It was first defined in INSAG-4 (International Nuclear Safety Advisory Group safety series) in 1991. Other events have occurred in nuclear facilities and during transportation since Chernobyl: Tokai Mura in 1999, Roissy Transport in 2002, Davis Besse in 2002, Thorp in 2005. These events show that the initial approach was too simplistic. Based on this observation, the definition of safety culture was supplemented by including concepts of cultural value (associated with the country and the company) and human and organizational factors, and was integrated in that form with the emergence and implementation of integrated management systems (IMS). Today, the concept of nuclear safety culture covers a wide set of factors such as safety, quality, corporate culture, defined processes and policies, organizations and related resources. Any assessment of people’s safety culture, particularly people directly involved in facility operations, is thus part of a comprehensive policy and contributes to a de facto demonstration of the priority which management assigns to safety.

  6. Climatic change and nuclear energy

    International Nuclear Information System (INIS)

    Schneider, M.

    2000-08-01

    The data presented in the different chapters lead to show that nuclear energy ids not a sustainable energy sources for the following reasons: investments in nuclear energy account financing that lacks to energy efficiency programmes. The nuclear programmes have negative effects such the need of great electric network, the need of highly qualified personnel, the freezing of innovation in the fields of supply and demand, development of small performing units. The countries resort to nuclear energy are among the biggest carbon dioxide emitters, because big size nuclear power plants lead to stimulate electric power consumption instead of inducing its rational use. Nuclear energy produces only electric power then a part of needs concerns heat (or cold) and when it is taken into account nuclear energy loses its advantages to the profit of cogeneration installations. Finally nuclear energy is a dangerous energy source, difficult to control as the accident occurring at Tokai MURA showed it in 1998. The problem of radioactive wastes is not still solved and the nuclear proliferation constitutes one of the most important threat at the international level. (N.C.)

  7. [Radioactive nuclides in the marine environment--distribution and behaviour of 95Zr, 95Nb originated from fallout].

    Science.gov (United States)

    Yamato, A; Miyagawa, N; Miyanaga, N

    1984-07-01

    To investigate behaviour of 95Zr, 95Nb in the marine environment, various samples have been collected and measured by means of Ge(Li) gamma-ray spectrometry and/or radiochemical analysis during a period from 1974 to 1982 at coastal area of Tokai-mura, Ibaraki prefecture. Concentration of the nuclides in seaweeds increased remarkably after atmospheric nuclear detonation by P.R. of China, and the activity ratio between the nuclides changed by time was not fit well by the transient decay equation. Concentration variation in sea water was smaller than that in sea weeds, and the minimum change in sea sediment. Increase of concentration in these environmental samples was observed in chronological order of sea water, sea weeds then sediment after detonations, suggesting that the uptake of the nuclides by these sea weeds from sea water is faster than that via root. Observed concentration factors on the nuclides by sea weeds were calculated from the observed concentrations in sea water and sea weeds. Maximum values on 95Zr and 95Nb were 2110, 2150, respectively for Ecklonia cava and Eisenia bicyclis.

  8. Demonstration of an automated electromanometer for measurement of solution volume in accountability vessels

    International Nuclear Information System (INIS)

    Suda, S.; Keisch, B.; Hayashi, M.; Onuma, T.; Fukuari, Y.

    1981-09-01

    A system for measuring the liquid volume in input and plutonium product accountability vessels, based upon a desktop-computer-controlled electromanometer, was installed at the Tokai-Mura reprocessing plant. In-tank temperatures, pressure measurements relating to volume and density, and load-cell weights are measured cyclically and recorded. The system feasibility was demonstrated through a series of tests including vessel calibration and the effects of thermal expansion, and through use during thirteen months of on-line plant operation. The value to the operator of the recording, display, replay, data handling, and report generation features of the system was demonstrated as was the enhanced precision of the electromanometer as compared to the conventional water-filled manometer system. The automated electromanometer system consists of a pneumatic scanner, a precision electromanometer, electronic scanner, a digital voltmeter, and a desktop computer with disc and tape mass storage, cathode-ray tube (CRT) graphics display, and printer output. The desktop computer is used to control the pneumatic and electronic scanners and the digital voltmeter and to log in the measurement data

  9. Verification of atmospheric diffusion models using data of long term atmospheric diffusion experiments

    International Nuclear Information System (INIS)

    Tamura, Junji; Kido, Hiroko; Hato, Shinji; Homma, Toshimitsu

    2009-03-01

    Straight-line or segmented plume models as atmospheric diffusion models are commonly used in probabilistic accident consequence assessment (PCA) codes due to cost and time savings. The PCA code, OSCAAR developed by Japan Atomic Energy Research Institute (Present; Japan Atomic Energy Agency) uses the variable puff trajectory model to calculate atmospheric transport and dispersion of released radionuclides. In order to investigate uncertainties involved with the structure of the atmospheric dispersion/deposition model in OSCAAR, we have introduced the more sophisticated computer codes that included regional meteorological models RAMS and atmospheric transport model HYPACT, which were developed by Colorado State University, and comparative analyses between OSCAAR and RAMS/HYPACT have been performed. In this study, model verification of OSCAAR and RAMS/HYPACT was conducted using data of long term atmospheric diffusion experiments, which were carried out in Tokai-mura, Ibaraki-ken. The predictions by models and the results of the atmospheric diffusion experiments indicated relatively good agreements. And it was shown that model performance of OSCAAR was the same degree as it of RAMS/HYPACT. (author)

  10. Preparedness for remote possibility of a nuclear emergency

    International Nuclear Information System (INIS)

    Fujishiro, Toshio

    2001-01-01

    Nuclear disaster prevention is fundamentally preparedness for emergency with extremely lower forming probability. In order to establish allowance of nuclear energy application from society, it is essential that it brings relief feelings with preparedness and without anxiety among everything. At a time when use of nuclear energy was begun, a consciousness that a nuclear facility was one highly considered on its safety faster than that in the other industries was large and intense, and then recognition of necessity for nuclear disaster prevention was extremely minute. However, the nuclear emergency of critical accident at the JCO fuel processing facility in Tokai-mura formed on September 30, 1999 gave Japanese extremely large impact so as fundamentally to change actual feelings against conventional nuclear disaster prevention. Here was introduced on efforts onto reinforcement of nuclear disaster prevention together with establishment of the special measure rule nuclear disaster prevention countermeasure as well as its advantages and progress, to investigate on a subject to do it for a preparedness with effectiveness for obtaining real safe feelings. (G.K.)

  11. Radioactive nuclides in the marine environment

    International Nuclear Information System (INIS)

    Yamato, Aiji; Miyagawa, Naoto; Miyanaga, Naotake

    1984-01-01

    To investigate behaviour of 95 Zr, 95 Nb in the marine environment, various samples have been collected and measured by means of Ge(Li) γ-ray spectrometry and/or radiochemical analysis during a period from 1974 to 1982 at coastal area of Tokai-mura, Ibaraki prefecture. Concentration of the nuclides in seaweeds increased remarkably after atmospheric nuclear detonation by P.R. of China, and the activity ratio between the nuclides changed by time was not fit well by the transient decay equation. Concentration variation in sea water was smaller than that in sea weeds, and the minimum change in sea sediment. Increase of concentration in these environmental samples was observed in chronological order of sea water, sea weeds then sediment after detonations, suggesting that the uptake of the nuclides by these sea weeds from sea water is faster than that via root. Observed concentration factors on the nuclides by sea weeds were calculated from the observed concentrations in sea water and sea weeds. Maximum values on 95 Zr and 95 Nb were 2110, 2150, respectively for Ecklonia cava and Eisenia bicyclis. (author)

  12. Initial medical management of criticality accident victim; Conduite a tenir aux victimes d'un accident de criticite

    Energy Technology Data Exchange (ETDEWEB)

    Miele, A; Bebaron-Jacobs, L

    2005-07-01

    The extremely severe criticality accidents known to this day, and the subsequent deaths recorded (Sarov 1997 and Tokai Mura 1999), demonstrate the need for sustained surveillance and constant adapted training for the teams in charge of irradiated and/or contaminated victims. The aim of this work group, composed of occupational health services and associated medical biology laboratories, is to present, in leaflet format, the essential data on the documentation and the conduct to be held when facing the victims of a criticality accident. The studies of this work group confirm the difficulties involved in managing this type of accident, both from the dosimetric evaluation point of view and from the therapeutic management point of view. That is why several research themes and perspectives are developed. During the different phases of victim triage, the recommendations given on these leaflets describe the operational conducts to be held. This work will have to be updated according to the evolution in knowledge and means: short and long term effects of exposure to neutrons, multi-competence hospital cooperation, expertise networks related to dosimetric reconstitution. (authors)

  13. Initial medical management of criticality accident victim; Conduite a tenir aux victimes d'un accident de criticite

    Energy Technology Data Exchange (ETDEWEB)

    Miele, A.; Bebaron-Jacobs, L

    2005-07-01

    The extremely severe criticality accidents known to this day, and the subsequent deaths recorded (Sarov 1997 and Tokai Mura 1999), demonstrate the need for sustained surveillance and constant adapted training for the teams in charge of irradiated and/or contaminated victims. The aim of this work group, composed of occupational health services and associated medical biology laboratories, is to present, in leaflet format, the essential data on the documentation and the conduct to be held when facing the victims of a criticality accident. The studies of this work group confirm the difficulties involved in managing this type of accident, both from the dosimetric evaluation point of view and from the therapeutic management point of view. That is why several research themes and perspectives are developed. During the different phases of victim triage, the recommendations given on these leaflets describe the operational conducts to be held. This work will have to be updated according to the evolution in knowledge and means: short and long term effects of exposure to neutrons, multi-competence hospital cooperation, expertise networks related to dosimetric reconstitution. (authors)

  14. The integral fast reactor and its role in a new generation of nuclear power plants, Tokai, Japan, November 19-21, 1986

    International Nuclear Information System (INIS)

    Smith, R.R.

    1986-01-01

    This report presents information on the Integral Fast Reactor and its role in the future. Information is presented in the areas of: inherent safety; other virtues of sodium-cooled breeder; and solving LWR fuel cycle problems with IFR technologies

  15. The integral fast reactor and its role in a new generation of nuclear power plants, Tokai, Japan, November 19-21, 1986

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.R.

    1986-01-01

    This report presents information on the Integral Fast Reactor and its role in the future. Information is presented in the areas of: inherent safety; other virtues of sodium-cooled breeder; and solving LWR fuel cycle problems with IFR technologies. (JDB)

  16. Modelling of seismic reflection data for underground gas storage in the Pečarovci and Dankovci structures - Mura Depression

    Directory of Open Access Journals (Sweden)

    Andrej Gosar

    1995-12-01

    Full Text Available Two antiform structures in the Mura Depression were selected as the most promising in Slovenia for the construction of an underground gas storage facility in an aquifer. Seventeen reflection lines with a total length of 157km were recorded, and three boreholes were drilled. Structural models corresponding to two different horizons (the pre-Tertiary basement and the Badenian-Sarmatianboundary were constructed using the Sierra Mimic program. Evaluation of different velocity data (velocity analysis, sonic log, the down-hole method, and laboratory measurements on cores was carried out in order to perform correct timeto-depth conversion and to estabUsh lateral velocity variations. The porous rock in Pečarovci structure is 70m thick layer of dolomite, occurring at a depth of 1900m, whereas layers of marl, several hundred meter thick, represent the impermeable cap-rock. Due to faults, the Dankovci structure, at a depth of 1200m,where the reservoir rocks consist of thin layers of conglomerate and sandstone,was proved to be less reliable. ID synthetic seismograms were used to correlatethe geological and seismic data at the borehole locations, especially at intervals with thin layers. The raytracing method on 2D models (the Sierra Quik packagewas applied to confirm lateral continuity of some horizons and to improve the interpretation of faults which are the critical factor for gas storage.

  17. Measurements of 60Co in spoons activated by neutrons during the JCO criticality accident at Tokai-mura in 1999

    International Nuclear Information System (INIS)

    Gasparro, J.; Hult, M.; Komura, K.; Arnold, D.; Holmes, L.; Johnston, P.N.; Laubenstein, M.; Neumaier, S.; Reyss, J.-L.; Schillebeeckx, P.; Tagziria, H.; Van Britsom, G.; Vasselli, R.

    2004-01-01

    Neutron activated items from the vicinity of the place where the JCO criticality accident occurred have been used to determine the fluence of neutrons around the facility and in nearby residential areas. By using underground laboratories for measuring the activation products, it is possible to extend the study to also cover radionuclides with very low activities from long-lived radionuclides. The present study describes γ-ray spectrometry measurements undertaken in a range of underground laboratories for the purpose of measuring 60 Co more than 2 years after the criticality event. The measurements show that neutron fluence determined from 60 Co activity is in agreement with previous measurements using the short-lived radionuclides 51 Cr and 59 Fe. Limits on contamination of the samples with 60 Co are evaluated and shown to not greatly affect the utility of neutron fluence determinations using 60 Co activation

  18. Measurements of 60Co in spoons activated by neutrons during the JCO criticality accident at Tokai-mura in 1999.

    Science.gov (United States)

    Gasparro, J; Hult, M; Komura, K; Arnold, D; Holmes, L; Johnston, P N; Laubenstein, M; Neumaier, S; Reyss, J-L; Schillebeeckx, P; Tagziria, H; Van Britsom, G; Vasselli, R

    2004-01-01

    Neutron activated items from the vicinity of the place where the JCO criticality accident occurred have been used to determine the fluence of neutrons around the facility and in nearby residential areas. By using underground laboratories for measuring the activation products, it is possible to extend the study to also cover radionuclides with very low activities from long-lived radionuclides. The present study describes gamma-ray spectrometry measurements undertaken in a range of underground laboratories for the purpose of measuring (60)Co more than 2 years after the criticality event. The measurements show that neutron fluence determined from (60)Co activity is in agreement with previous measurements using the short-lived radionuclides (51)Cr and (59)Fe. Limits on contamination of the samples with (60)Co are evaluated and shown to not greatly affect the utility of neutron fluence determinations using (60)Co activation.

  19. Safeguards Analytical Laboratory evaluation program. Part 1. Resin bead mass spectrometry. Part 2. Results of a resin bead field experiment-Tastex-J

    International Nuclear Information System (INIS)

    Walker, R.L.; Smith, D.H.; Carter, J.A.; Musick, W.R.; Donohue, D.L.; Deron, S.; Asakura, Y.; Kagami, K.; Irinouchi, S.; Masui, J.

    1981-01-01

    The first part of this report covers background of resin bead spectrometry and the new batch resin bead method. In the original technique, about ten anion resin beads in the nitrate form were exposed to the diluted sample solution. The solution was adjusted to be a 8 M HNO 3 and to have about 1 μg U per bead. Up to 48 hours of static contact between beads and solution was required for adsorption of 1 to 3 ng Pu and U per bead to be achieved. Under these conditions, contamination was a problem at reprocessing facilities. The new batch techniques reduces the risk of contamination by handling one hundred times more U in the final diluted sample which is exposed to a proportionately larger number of beads. Moreover, it only requires ten minutes adsorption time to provide about 1000 purified samples for mass spectrometry. The amounts of Pu and U adsorbed versus time were determined and results are tabulated. The second part of this report briefly summarizes results of resin bead field tests completed at the Power Reactor and Nuclear Fuel Development Corporation (PNC) reprocessing plant in Tokai-mura, Japan. Both methods, the original small-sample resin bead and the batch technique, were investigated on spent fuel solutions. Beads were prepared at PNC and distributed to IAEA and ORNL along with dried residues for conventional mass spectrometric analysis at IAEA. Parallel measurements were made at PNC using their normal measuring routines. The U and Pu measurements of all resin and those of PNC are in excellent agreement for the batch method. Discrepancies were noted in the U measurements by the original method

  20. The nucleotide sequences of 5S rRNAs from a rotifer, Brachionus plicatilis, and two nematodes, Rhabditis tokai and Caenorhabditis elegans.

    Science.gov (United States)

    Kumazaki, T; Hori, H; Osawa, S; Ishii, N; Suzuki, K

    1982-11-11

    The nucleotide sequences of 5S rRNAs from a rotifer, Brachionus plicatilis, and two nematodes, Rhabditis tokai and Caenorhabditis elegans have been determined. The rotifer has two 5S rRNA species that are composed of 120 and 121 nucleotides, respectively. The sequences of these two 5S rRNAs are the same except that the latter has an additional base at its 3'-terminus. The 5S rRNAs from the two nematode species are both 119 nucleotides long. The sequence similarity percents are 79% (Brachionus/Rhabditis), 80% (Brachionus/Caenorhabditis), and 95% (Rhabditis/Caenorhabditis) among these three species. Brachionus revealed the highest similarity to Lingula (89%), but not to the nematodes (79%).

  1. Report of results of joint research using facilities in Japan Atomic Energy Research Institute in fiscal year 1987

    International Nuclear Information System (INIS)

    1988-06-01

    The total themes of the joint research in fiscal year 1987 were 127. These are shown being classified into the general joint research in Tokai and Takasaki, neutron diffraction research and cooperative research. The general joint research is the standard utilization form using research reactors JRR-2 and JRR-4, Co-60 gamma irradiation facilities in Tokai and Takasaki, an electron beam irradiation facility in Takasaki, an electron beam linear accelator and hot laboratories, which are opened for common utilization by Japan Atomic Energy Research Institute. The cooperative research is carried out by concluding research cooperation contracts between the researchers of universities and JAERI. In the general joint research, radioactivation analysis, radiation chemistry, irradiation effect, neutron diffraction and so on are the main themes, and in the cooperative research, reactor technology, reactor materials, nuclear physics measurement and others are the main themes. The total number of visitors was 2629 man-day, and decreased due to the stop of JRR-2. Also other activities are reported. The abstracts of respective reports are collected in this book. (Kako, I.)

  2. Design and fabrication of fuel for the prototype heavy water reactor Fugen

    International Nuclear Information System (INIS)

    Hasumi, Takashi; Yamanaka, Ryozi; Osawa, Masahide; Asami, Tomohiro; Kaziyama, Takashi

    1983-01-01

    For the advanced thermal reactor Fugen, 224 fuel assemblies were charged as the initial charge fuel, of which 96 were uranium-plutonium mixed oxide fuel, and 128 were uranium dioxide fuel. Since the full scale operation was started in March, 1979, fuel exchange was carried out five times, and 240 fuel assemblies were taken out, but fuel breaking was never found, and the fuel for Fugen has shown good result. For 16 mixed oxide fuel assemblies for the third exchange and thereafter, the domestically produced plutonium extracted in the Tokai reprocessing plant has been used, and for 15 UO 2 fuel assemblies for the fifth exchange, the enriched uranium produced in the Ningyo Pass plant was used. These fuels are burning in the core without causing trouble. The course of the development of the fuel is described as follows: trial manufacture, evaluation test outside the core, heat transferring flow characteristic test, irradiation test, design of fuel elements and fuel assemblies, production of fuel and quality assurance, and results of production and use. (Kako, I.)

  3. Results of Questionnaire for the member of JHPS concerning the criticality accident at Tokai

    International Nuclear Information System (INIS)

    2000-01-01

    During the investigation of the criticality accident at Tokai occurring on Sep. 30, 1999, the project team in Japan Health Physics Society (JHPS) carried out a questionnaire for the member on the accident and this paper summarized its results. The effective answer was obtained in 36% of members. Major questions (and frequent answers) were: media of information obtained (internet 33%, TV and radio 22%, and newspaper 19%); concerning actions done by Japanese and local governments, the recommendation on Sep. 30 at 15:00 of evacuation for people living in the area within the radius of 350 m (necessary 92%), timing of its release on Oct. 2 at 18:30 (appropriate 41% and too late 36%) and its information to the people (more information needed 60%) and the recommendation on Sep. 30 at 22:30 of in-door refuge within 10 km radius (unnecessary 43% and necessary 41%), timing of its release on Oct. 1 at 16:40 (too late 49%) and its information to the people (more information needed 63%); and safety declaration for food etc. on Oct. 2 at 18:30 (necessary 92%). Based on above results and free description on the questionnaire, JHPS considered the necessity of described systems of JHPS for emergency.(K.H.)

  4. Seismic ACROSS Transmitter Installed at Morimachi above the Subducting Philippine Sea Plate for the Test Monitoring of the Seismogenic Zone of Tokai Earthquake not yet to Occur

    Science.gov (United States)

    Kunitomo, T.; Kumazawa, M.; Masuda, T.; Morita, N.; Torii, T.; Ishikawa, Y.; Yoshikawa, S.; Katsumata, A.; Yoshida, Y.

    2008-12-01

    Here we report the first seismic monitoring system in active and constant operation for the wave propagation characteristics in tectonic region just above the subducting plate driving the coming catastrophic earthquakes. Developmental works of such a system (ACROSS; acronym for Accurately Controlled, Routinely Operated, Signal System) have been started in 1994 at Nagoya University and since 1996 also at TGC (Tono Geoscience Center) of JAEA promoted by Hyogoken Nanbu Earthquakes (1995 Jan.17, Mj=7.3). The ACROSS is a technology system including theory of signal and data processing based on the brand new concept of measurement methodology of Green function between a signal source and observation site. The works done for first generation system are reported at IWAM04 and in JAEA report (Kumazawa et al.,2007). The Meteorological Research Institute of JMA has started a project of test monitoring of Tokai area in 2004 in corporation with Shizuoka University to realize the practical use of the seismic ACROSS for earthquake prediction researches. The first target was set to Tokai Earthquake not yet to take place. The seismic ACROSS transmitter was designed so as to be appropriate for the sensitive monitoring of the deep active fault zone on the basis of the previous technology elements accumulated so far. The ground coupler (antenna) is a large steel-reinforced concrete block (over 20m3) installed in the basement rocks in order to preserve the stability. Eccentric moment of the rotary transmitter is 82 kgm at maximum, 10 times larger than that of the first generation. Carrier frequency of FM signal for practical use can be from 3.5 to 15 Hz, and the signal phase is accurately controlled by a motor with vector inverter synchronized with GPS clock with a precision of 10-4 radian or better. By referring to the existing structure model in this area (Iidaka et al., 2003), the site of the transmitting station was chosen at Morimachi so as to be appropriate for detecting the

  5. Improvement of INVS Measurement Uncertainty for Pu and U-Pu Nitrate Solution

    Energy Technology Data Exchange (ETDEWEB)

    Swinhoe, Martyn Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Menlove, Howard Olsen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Marlow, Johnna Boulds [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Makino, Risa [Japan Atomic Energy Agency (JAEA), Tokai (Japan); Nakamura, Hironbu [Japan Atomic Energy Agency (JAEA), Tokai (Japan)

    2017-04-27

    In the Tokai Reprocessing Plant (TRP) and the Plutonium Conversion Development Facility (PCDF), a large amount of plutonium nitrate solution which is recovered from light water reactor (LWR) and advanced thermal reactor (ATR), FUGEN are being stored. Since the solution is designated as a direct use material, the periodical inventory verification and flow verification are being conducted by Japan Safeguard Government Office (JSGO) and International Atomic Agency (IAEA).

  6. Proceedings of the seminar on the joint research project between JAERI and Universities. 'Actinide researches for 21st century - fusion between chemistry and engineering'. August 20-21, 1999, Japan Atomic Energy Research Inst., Tokai, Japan

    International Nuclear Information System (INIS)

    2000-06-01

    The Seminar on the Joint Research Project between JAERI and Universities was held in Tokai, August 20-21, 1999, to discuss future perspectives of the actinide researches for the nuclear fuel cycle. The papers related to the Joint Research Project on the Backend Chemistry were presented and discussed. The present report complies the papers contributed to the Seminar. (author)

  7. BAY‘ AL-MURABAHAH: Mendudukkan Kembali Posisinya dalam Perbankan Syari’ah

    Directory of Open Access Journals (Sweden)

    Luhur Prasetiyo

    2016-02-01

    Full Text Available BAY‘ AL-MURAbah}ah transaction becomes the most popular product which shari>’ah banking uses to sell its assets for amount of reasons. Total amount of shari>’ah banks store and transact their assets (fund in mura>bah}ah system. The reason is that this product has not only small risk but also ease to manage related to muz}a>rabah and musha>rakah system. In the other hand, Many people don’t understand mura>bah}ah mechanism precisely. They often think that mura>bah}ah mechanism is as credit as well. It is, in fact, that mura>bah}ah system is a cash transaction which shari>’ah banks have. This paper is to elaborate mura>bah}ah system as a product of shari>’ah banking.   Keywords: Perbankan Syariah, mura>bah}ah, margin keuntungan, kredit

  8. Measurements of {sup 60}Co in spoons activated by neutrons during the JCO criticality accident at Tokai-mura in 1999

    Energy Technology Data Exchange (ETDEWEB)

    Gasparro, J.; Hult, M. E-mail: mikael.hult@irmm.jrc.be; Komura, K.; Arnold, D.; Holmes, L.; Johnston, P.N.; Laubenstein, M.; Neumaier, S.; Reyss, J.-L.; Schillebeeckx, P.; Tagziria, H.; Van Britsom, G.; Vasselli, R

    2004-07-01

    Neutron activated items from the vicinity of the place where the JCO criticality accident occurred have been used to determine the fluence of neutrons around the facility and in nearby residential areas. By using underground laboratories for measuring the activation products, it is possible to extend the study to also cover radionuclides with very low activities from long-lived radionuclides. The present study describes {gamma}-ray spectrometry measurements undertaken in a range of underground laboratories for the purpose of measuring {sup 60}Co more than 2 years after the criticality event. The measurements show that neutron fluence determined from {sup 60}Co activity is in agreement with previous measurements using the short-lived radionuclides {sup 51}Cr and {sup 59}Fe. Limits on contamination of the samples with {sup 60}Co are evaluated and shown to not greatly affect the utility of neutron fluence determinations using {sup 60}Co activation.

  9. Proceedings of the seminar on the joint research project between JAERI and Universities. 'Actinide researches for 21st century - fusion between chemistry and engineering'. August 20-21, 1999, Japan Atomic Energy Research Inst., Tokai, Japan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-06-01

    The Seminar on the Joint Research Project between JAERI and Universities was held in Tokai, August 20-21, 1999, to discuss future perspectives of the actinide researches for the nuclear fuel cycle. The papers related to the Joint Research Project on the Backend Chemistry were presented and discussed. The present report complies the papers contributed to the Seminar. (author)

  10. Data logger system of Tokai (I) Nuclear Power Station, the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Machida, Akira; Chikahata, Kiyomitsu; Nakamura, Mamoru; Nanbu, Taketoshi; Kawakami, Hiroshi

    1977-01-01

    The Tokai(I) nuclear power station, the Japan Atomic Power Company, was commissioned in July, 1966. In this station, temperatures of about 700 points are monitored and recorded with a data logger. However, the logger was manufactured some 15 years ago, therefore it is now old-fashioned, and has caused frequent failures these 2 or 3 years. So it was decided to replace it with a new one, and the process control computer, U-300 system including CRT display, has been adopted considering the latest trend in U.K. The control and monitoring system in this station is not a centralized control system, but a distributed control system divided into three control rooms, namely main control room, turbine generator control room and fuel exchanger (cask machine) control room. Therefore for grasping the complete plant conditions at the main control room, the system has not been convenient, and the centralization of data processing has been desired from the viewpoint of operation. The new logger system is composed so as to facilitate the centralized monitoring in the main control room, considering the above requirement. It has been improved so as to have seven important functions in addition to the existing functions. Hardware and software of this system are briefly explained. The new system was started up in February 1977, and is now operating well, though some early failures were experienced. (Wakatsuki, Y.)

  11. Management of energy-save and environment on the boiler system

    International Nuclear Information System (INIS)

    Ishiyama, Toru; Asano, Naoki; Kawasaki, Ichio

    2010-02-01

    Tokai Utility Center (TUC) is the facility that products and feeds steam for Tokai Reprocessing Plant (TRP), Plutonium Fuel Production Facility (PFPF), etc. The boiler system needs the management based on the law of 'Industrial safety and Health Act' and 'Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors'. In this situation, activity of preservation of environment and energy-save are carried out by means of the improvement of steam generation process and the change of additive to water. Quality assurance procedure has been applied in order to improve the boiler operation continuously. This report describes about various activities of the management, the environment, the energy-saving, and a future action. (author)

  12. Nuclear regulatory challenges of who should we train and why - a regulatory perspective

    International Nuclear Information System (INIS)

    Furness, J.

    2000-01-01

    The understanding by the staff who design, construct, commission, operate and decommission our nuclear installations of the safety cases for the plants is crucial to nuclear safety. The lack of such understanding has been a major contributor to accidents at Windscale, Three Mile Island and Chernobyl, and may also have played a role in the recent criticality accident at Tokai-Mura. Competence is not only a matter of knowledge, but also of behaviour at the level of the individual and the organisation. It is also important for those in Government departments who sponsor or regulate nuclear power. The right competence is an essential ingredient in achieving a health safety culture at all levels. Staff turnover will be high over the next 5-10 years and the long experience of those who will be retiring must somehow be transferred to those who remain and who will be recruited. Competitive pressures may accelerate this process, increasing the stresses on the staff concerned. Plants are ageing and work-loads increasing, making safety culture all the more important. 'Soft skills' are as important as technical knowledge and should be included in training programmes at all levels. (author)

  13. Bulletin of the radioactivity. No. 83. January-December, 1999

    International Nuclear Information System (INIS)

    2001-01-01

    This report contains the result of observations by the Japan Meteorological Agency (JMA) of atmospheric and seawater radioactivity for the year 1999. The sampling, measurement methods and results of gross beta-radioactivity in precipitation, radioactivity in airborne dust, monthly mean 90 Sr concentration in airborne dust, gross beta-radioactivity in seawater, deposition of 89 Sr, 90 Sr and 137 Cs, natural background radioactivity and vertical distribution of atmospheric radioactivity are described. The results of special observations on the criticality accident at an uranium processing plant, Tokai-mura, Japan showed that gamma-ray spectrum analysis in airborne dust indicated Cs-137 ND (lower than detection limit) and I-131 ND in Sendai and Tokyo at sampling at 99/10/1. 09h-99/10/1,14h and in Tsukuba at sampling 99/09/30, 09h-99/10/01, 09h. Gross beta-radioactivity in precipitation showed 40 MBq/km 2 deposition in Hachijo-jima at sampling 99/09/30,09h-99/10/01, 09h, but no precipitation in Sendai, Akita, Tokyo and Wajima. Mean gamma-radiation dose rate in Wajima indicated 9.8 cps at monitoring 99/09/30-99/10/01,15h. (S.Y.)

  14. Activation measurements for thermal neutrons. Part F. 36Cl measurements in Japan

    International Nuclear Information System (INIS)

    Nagashima, Yasuo; Seki, Riki; Matsuhiro, Takeshi; Takahashi, Tsutomu; Sasa, Kimikazu; Usui, Toshihide; Sueki, Keisuke

    2005-01-01

    The development of the accelerator mass spectrometry (AMS) system at the Tandem Accelerator Center of the University of Tsukuba was started in 1995, using the university's own molecular pilot beam technique. Presently, it is the only facility in Japan used to measure 36 Cl (Nagashima et al. 2000). The sensitivity of the 36 Cl AMS system is around 10 -14 36 Cl/Cl atom ratio, which is enough to measure the natural level of the 36 Cl/Cl ratio. The system is characterized by long-term stability, enabling high-quality, continuous measurements over many hours. Our AMS system was used to measure 36 Cl produced in soil by neutrons released into the environment at the time of the JCO criticality accident in Tokai-mura in 1999 (Seki et al. 2003). At the beginning of 2001, our group joined the collaborative efforts to investigate and clarify the discrepancy observed between measurements and calculations of neutron activities induced by the atomic bombings in Hiroshima and Nagasaki. Using our AMS system, 36 Cl was measured in granite samples from Hiroshima exposed to atomic-bomb neutrons and in distant, unexposed samples. (author)

  15. Strange Particles and Heavy Ion Physics

    Energy Technology Data Exchange (ETDEWEB)

    Bassalleck, Bernd [Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Physics and Astronomy; Fields, Douglas [Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Physics and Astronomy

    2016-04-28

    This very long-running grant has supported many experiments in nuclear and particle physics by a group from the University of New Mexico. The gamut of these experiments runs from many aspects of Strangeness Nuclear Physics, to rare Kaon decays, to searches for exotic Hadrons such as Pentaquark or H-Dibaryon, and finally to Spin Physics within the PHENIX collaboration at RHIC. These experiments were performed at a number of laboratories worldwide: first and foremost at Brookhaven National Lab (BNL), but also at CERN, KEK, and most recently at J-PARC. In this Final Technical Report we summarize progress and achievements for this award since our last Progress Report, i.e. for the period of fall 2013 until the award’s termination on November 30, 2015. The report consists of two parts, representing our two most recent experimental efforts, participation in the Nucleon Spin Physics program of the PHENIX experiment at RHIC, the Relativistic Heavy Ion Collider at BNL – Task 1, led by Douglas Fields; and participation in several Strangeness Nuclear Physics experiments at J-PARC, the Japan Proton Accelerator Research Center in Tokai-mura, Japan – Task 2, led by Bernd Bassalleck.

  16. Replacement of the criticality accident alarm system in the Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Sanada, Yukihisa; Momose, Takumaro; Suzuki, Kei; Kawai, Keiichi

    2008-01-01

    A Criticality Accident Alarm System (CAAS) was installed as part of criticality safety management for use in reducing the radiation workers could be exposed to in the rare case of a criticality accident. The initial CAAS version was installed the Tokai Reprocessing Plant (TRP) in the 1980s. It includes units that can detect gamma-rays or neutron-rays released in criticality accidents (CADs), one of which consists of three plastic scintillation gamma detectors and three solid state neutron detectors with fissile material, and in being highly reliable utilizes the 2 out of 3 voting system. The purpose of this study is to give the design principles and procedures for determining the adequate relocation of the CADs within the TRP. The optimal places for the CADs to be relocated to were determined using a conservative evaluation method. Firstly, equipment needing to be monitored for criticality accidents was selected with consideration given to the risk of excessive exposure to workers. Secondly, the detection threshold of a minimum accident was set to be an increase in power of 10 15 fissions/s occurring within a rise-time of between 0.5 ms and 1 s. The sum of neutron and gamma doses of a minimum accident (10 15 fissions) was 0.3 Gy at an unshielded distance of 1 m. Finally, doses at where the CADs were installed were evaluated using parameters calculated with MCNP and ANISN. As a result, the alarm trip level of both the gamma detector and the neutron detector being set at 2.0 mGy/h enabled minimum criticality accidents to be conservatively detected. These results were then applied to the new CAD positions. (author)

  17. Corrosion evaluation of uranyl nitrate solution evaporator and denitrator in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Yamanaka, Atsushi; Hashimoto, Kowa; Uchida, Toyomi; Shirato, Yoji; Isozaki, Toshihiko; Nakamura, Yoshinobu

    2011-01-01

    The Tokai reprocessing plant (TRP) adopted the PUREX method in 1977 and has reprocessed spent nuclear fuel of 1140 tHM (tons of heavy metals) since then. The reprocessing equipment suffers from various corrosion phenomena because of high nitric acidity, solution ion concentrations, such as uranium, plutonium, and fission products, and temperature. Therefore, considering corrosion performance in such a severe environment, stainless steels, titanium steel, and so forth were employed as corrosion resistant materials. The severity of the corrosive environment depends on the nitric acid concentration and the temperature of the solution, and uranium in the solution reportedly does not significantly affect the corrosion of stainless steels and controls the corrosion rates of titanium steel. The TRP equipment that handles uranyl nitrate solution operates at a low nitric acid concentration and has not experienced corrosion problems until now. However, there is a report that corrosion rates of some stainless steels increase in proportion to rising uranium concentrations. The equipment that handles the uranyl nitrate solution in the TRP includes the evaporators, which concentrate uranyl nitrate to a maximum concentration of about 1000 gU/L (grams of uranium per liter), and the denitrator, where uranyl nitrate is converted to UO 3 powder at about 320degC. These equipments are therefore required to grasp the degree of the progress of corrosion to handle high-temperature and high-concentration uranyl nitrate. The evaluation of this equipment on the basis of thickness measurement confirmed only minor corrosion and indicated that the equipment would be fully adequate for future operation. (author)

  18. Feasibility study of plutonium recycling in light water reactors

    International Nuclear Information System (INIS)

    Tabuchi, Hideoto

    1979-01-01

    The feasibility of plutonium recycling in light water reactors has been studied by the Agency of Natural Resources and Energy, MITI. As the first step of the feasibility study, it was planned to charge two fuel assemblies, containing uranium-plutonium mixed oxide (MO 2 ), in the core of the Tsuruga nuclear power plant (BWR) for testing. The design of fuel the safety of these fuel and the operating characteristics of these special fuel assemblies were evaluated. The specifications of MO 2 fuel pin and fuel assembly are compared to those of present uranium oxide (UO 2 ) fuel. The weight of fissile plutonium in one MO 2 fuel assembly is 2.22 kg. The characteristics of MO 2 fuel assemblies, such as reactivity, control rod worth and power distribution can be kept similar to UO 2 fuel. The plutonium isotope ratio of the MO 2 fuel is assumed as that obtained in the fuel taken out of the Tokai No. 1 gas cooled reactor. The temperature distribution in the fuel pellets is shown, compared to that of UO 2 fuel. The linear power density is 440 w/cm at the beginning of the fuel life and 360 w/cm after the burn-up of 44,000 Mwd/t. The stress in the cladding tubes of MO 2 fuel is not different from that of UO 2 fuel. The pellet-cladding interaction (PCM1) was analyzed, utilizing the FEM code, FEAST. Concerning the calculation of resonance absorption, the space dependence of thermal neutron spectra and the nuclear behavior of hollow pellets the methods of design calculation were checked up. It was recognized that regarding the nuclear characteristics of MO 2 fuel, no special technical question remains. (Nakai, Y.)

  19. Operating document on management division waste management section in Tokai works in the 2003 fiscal year

    International Nuclear Information System (INIS)

    Kobayashi, Kentarou; Akutu, Shigeru; Sasayama, Yasuo; Nakanishi, Masahiro; Ozone, Takashi; Terunuma, Tomomi; Mogaki, Isao; Aizawa, Syuichi; Sugawara, Hiroyuki

    2005-07-01

    This document is announced about the task of Waste Management Section of Waste Management Division in 2003. Mainly, our tasks are fractionating, incinerating and storing low active solid waste and storing high active solid waste. In addition, we are performing required correspondence about management program of low level waste. We had treated and stored waste safely according to our plan. As a result, we have achieved following outcomes. (1) We incinerated the combustible low active solid waste that is generated by the operation of Tokai Reprocessing Plant and the recovery operation of incident at Low Active Liquid Waste Asphalt Solidification Facility. Waste of this recovery operation is stored in the 2nd Low Active Liquid Waste Asphalt Solidification Storage Facility. We incinerated 58 ton of wastes. (2) We stored low active solid waste 854 drums that accommodate 200L. According to the time of Low-Level Waste Treatment Facility completion, we will be able to avoid full of storage. (3) We stored high active solid waste of 148 drums that accommodate 200L. For the time being, there is no problem as regards the administration of storage facility. (4) We carried out the management program of low level solid waste according to plan. (author)

  20. Operating document on Management Division Waste Management Section in Tokai Works in the 2002 fiscal year

    International Nuclear Information System (INIS)

    Kobayashi, Kentarou; Isozaki, Kouei; Akutu, Shigeru; Nakanishi, Masahiro; Ozone, Takashi; Terunuma, Tomomi

    2004-05-01

    This document is announced about the task of Waste Management Section of Waste Management Division in 2004. Mainly, our tasks are fractionating, incinerating and storing low active solid waste and storing high active solid waste. In addition, we are performing required correspondence about management program of low level waste. We had treated and stored waste safely according to our plan. As a result, we have achieved following outcomes. (1) We incinerated the combustible low active solid waste that is generated by the operation of Tokai Reprocessing Plant and the recovery operation of incident at Low Active Liquid Waste Asphalt Solidification Facility. Waste of this recovery operation is stored in the 2nd Low Active Liquid Waste Asphalt Solidification Storage Facility. We incinerated 66.7 ton of wastes. (2) We stored low active solid waste 858 drums that accommodate 200L. According to the time of Low-Level Waste Treatment Facility completion, we will be able to avoid full of storage. (3) We stored high active solid waste of 154 drums that accommodate 200 L. For the time being, there is no problem as regards the administration of storage facility. (4) We carried out the management program of low level solid waste according to plan. (author)

  1. Proceedings of the 8th topical meeting on nuclear code development

    International Nuclear Information System (INIS)

    1993-03-01

    The 8th Topical Meeting on Nuclear Code Development, organized by Committee on Reactor Physics and Nuclear Codes Committee of Japan Atomic Energy Research Institute (JAERI), was held at Tokai Research Establishment of JAERI, on 11th and 12th of November, 1992. In the meeting, 14 papers were presented on the topics of (1) the next generation nuclear reactor design system and (2) advances of the nuclear fuel reprocessing safety analysis codes. These papers are compiled in this proceedings. (author)

  2. Model engineering for piping layout of boiling water reactor nuclear station

    International Nuclear Information System (INIS)

    Tsukada, Koji; Uchiyama, Masayuki; Wada, Takanao; Jibu, Noboru.

    1977-01-01

    A nuclear power station is made up of a wide variety of equipment, piping, ventilation ducts, conduits, and cable trays, etc. Even if equipment arrangement and piping layout are carefully planned on drawings, troubles such as interference often occur at field installation. Accordingly, it is thought very useful to make thorough examinations with plastic three-dimensional models in addition to drawings in reducing troubles at field, shortening the construction period, and improving economics. Examination with plastic models offers the following features: (1) It permits visual three-dimensional examination. (2) Group thinking and examination is possible. (3) Troubles due to failure to understand complicated drawings can be reduced drastically. Manufacturing a 1/20 scale model of the reactor building of the Tokai No. 2 Power Station of the Japan Atomic Power Co., Hitachi has performed model engineering-solution of interference troubles related to equipment and piping, securing of work space for in-service inspection (ISI), carry-in/installation of various equipment and piping, and determination of the piping route of which only the starting and terminating points were given under the complicated ambient conditions. Success with this procedure has confirmed that model engineering is an effective technique for future plant engineering. (auth.)

  3. A study of statistical tests for near-real-time materials accountancy using field test data of Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Ihara, Hitoshi; Nishimura, Hideo; Ikawa, Koji; Miura, Nobuyuki; Iwanaga, Masayuki; Kusano, Toshitsugu.

    1988-03-01

    An Near-Real-Time Materials Accountancy(NRTA) system had been developed as an advanced safeguards measure for PNC Tokai Reprocessing Plant; a minicomputer system for NRTA data processing was designed and constructed. A full scale field test was carried out as a JASPAS(Japan Support Program for Agency Safeguards) project with the Agency's participation and the NRTA data processing system was used. Using this field test data, investigation of the detection power of a statistical test under real circumstances was carried out for five statistical tests, i.e., a significance test of MUF, CUMUF test, average loss test, MUF residual test and Page's test on MUF residuals. The result shows that the CUMUF test, average loss test, MUF residual test and the Page's test on MUF residual test are useful to detect a significant loss or diversion. An unmeasured inventory estimation model for the PNC reprocessing plant was developed in this study. Using this model, the field test data from the C-1 to 85 - 2 campaigns were re-analyzed. (author)

  4. The status of graphite development for gas cooled reactors. Proceedings of a specialists` meeting held in Tokai, Japan, 9-12 September 1991

    Energy Technology Data Exchange (ETDEWEB)

    1993-02-01

    The meeting was convened by the IAEA on the recommendation of the International Working Group on Gas Cooled Reactors. It was attended by 61 participants from 6 countries. The meeting covered the following subjects: overview of national programs; design criteria, fracture mechanisms and component test; materials development and properties; non-destructive examination, inspection and surveillance. The participants presented 33 papers on behalf of their countries. A separate abstract was prepared for each of these papers. Refs, figs, tabs, photos and diagrams.

  5. Change in nuclear fuel material processing operation at Tokai Plant of Mitsubishi Atomic Fuel Co., Ltd. (report)

    International Nuclear Information System (INIS)

    1987-01-01

    This report, compiled by the Nuclear Safety Commission to be submitted to the Prime Minister, deals with studies on a proposed change in the operation of processing nuclear fuel substances at the Tokai Plant of Mitsubishi Atomic Fuel Co., Ltd. The conclusions of and principles for the examination and evaluation are described. It is concluded that part of the proposed change is appropriate with respect to required technical capability and that part of the change will not have adverse effects on the safety of the plant. The studies carried out are focused on the safety of the facilities. The study on the earthquake resistance reveals that anti-earthquake design for the new buildings is properly developed. The buildings are of fireproof construction and the systems and equipment to be installed are made of incomustible materials to ensure the prevention of fire and explosion. It is confirmed that criticality control (for each unit and for the group of units) will be performed appropriately and that the waste (gaseous waste, liquid waste, solid waste) treatment systems are designed appropriately. A study is also made on the radiation control methods (working condition control, individual exposure control, surrounding environment control). In addition accident evaluation is carried out to confirm the safety of the residents around the plant. (Nogami, K.)

  6. Change in nuclear fuel material processing operation at Tokai Plant of Mitsubishi Atomic Fuel Co. , Ltd. (report)

    Energy Technology Data Exchange (ETDEWEB)

    1987-09-01

    This report, compiled by the Nuclear Safety Commission to be submitted to the Prime Minister, deals with studies on a proposed change in the operation of processing nuclear fuel substances at the Tokai Plant of Mitsubishi Atomic Fuel Co., Ltd. The conclusions of and principles for the examination and evaluation are described. It is concluded that part of the proposed change is appropriate with respect to required technical capability and that part of the change will not have adverse effects on the safety of the plant. The studies carried out are focused on the safety of the facilities. The study on the earthquake resistance reveals that anti-earthquake design for the new buildings is properly developed. The buildings are of fireproof construction and the systems and equipment to be installed are made of incomustible materials to ensure the prevention of fire and explosion. It is confirmed that criticality control (for each unit and for the group of units) will be performed appropriately and that the waste (gaseous waste, liquid waste, solid waste) treatment systems are designed appropriately. A study is also made on the radiation control methods (working condition control, individual exposure control, surrounding environment control). In addition accident evaluation is carried out to confirm the safety of the residents around the plant. (Nogami, K.).

  7. The minimization of radioactive releases to the sea from the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Sugiyama, T.; Yoshikawa, K.; Ishii, T.

    1996-01-01

    The Tokai Reprocessing Plant (TRP) started hot operation in September 1977. The total amount of about 790 tU of spent fuel, generated in Japan, has been successfully reprocessed as of December 1994. Low-level liquid wastes have been treated safely with the low-level waste treatment process. The design of TRP was based on foreign technology. In the early stage of designing, the radioactivity released to the sea was estimated at approximately 2.6 TBq/day (70 Ci/day) for beta activity (except for tritium). Later, PNC added an evaporator to the process to reduce the level down to 1/100, i.e. 9.6 TBq/year (260 Ci/year) or 2.6 x 10 -2 TBq/day (0.7 Ci/day). In addition, under the supervision of the government, PNC started R and D to further decrease the radioactivity released to the sea in terms of ALARA. Aiming at reducing the activity from 9.6 TBq/year (260 Ci/year) to 1/10 of that value (i.e. 26 Ci/year), the release reduction technology development facility was added. This facility was incorporated into the low-level waste treatment process in 1980, before starting the regular operation of TRP. Since the fuel reprocessing commenced, total radioactivity discharged to the sea has been 1.9 x 10 -2 TBq (0.51 Ci) for beta activity, as of December 1994. Before incorporating the release reduction technology development facility, the yearly level was 3.7 x 10 -3 - 7.4 x 10 -3 TBq (0.1 - 0.2 Ci). After incorporation of the facility, radioactivity released to the sea was greatly decreased to non-detection levels in recent years, in spite of increasing annual reprocessing amounts. Although serious equipment failures have occurred such as the acid recovery evaporator and the dissolvers, there was no influence on radioactivity released to the sea. (author)

  8. Feasibility study on silicon doping using high temperature test engineering reactor

    International Nuclear Information System (INIS)

    Seki, Masaya; Takaki, Naoyuki; Goto, Minoru; Shimakawa, Satoshi

    2011-01-01

    The feasibility study on silicon doping using the High Temperature engineering Test Reactor (HTTR) is performed by numerical simulations. The HTTR is a High Temperature Gas-cooled Reactor (HTGR) situated at JAEA Oarai research and development center. It has a 30MW thermal power and the outlet coolant temperature is 950degC. The objective of this study is to evaluate the following issues, 1. The impact of loading Si-ingots into the core on the criticality, 2. The uniformity of the neutron capture reaction rate in Si-ingots, and 3. The production rate of silicon semiconductor. In this study, six Si-ingots are loaded into the irradiation area which is located in the peripheral region of the core. They are irradiated with rotation movement around the axial direction to obtain uniform neutron capture reaction rate in the radial direction. Additionally, the neutron filter, which is made of graphite containing boron, is used to obtain uniform neutron capture reaction rate in the axial direction. The evaluations were conducted by performing the HTTR whole core calculations with the Monte Carlo code MVP-2.0. In the calculations, several tally regions were defined on the Si-ingots to investigate the uniformity of the neutron capture reaction rate. As a result, loading the Si-ingots into the core causes negative reactivity by about 0.7%dk/k. Uniform neutron capture reaction rate of Si-ingot is obtained 98% in the radial and the axial direction. In case of the target of semiconductor resistivity is set to 50 Ωcm, the required irradiation time becomes 10 hours. The HTTR is able to produce silicon semiconductor of 540kg in one-time irradiation. This study was conducted as a joint research with JAEA, Nuclear Fuel Industries, LTD, Toyota Tsusho Corporation and Tokai University. (author)

  9. Dose evaluation on the basis of 24Na activity in the human body for the criticality accident at JCO Tokai nuclear fuel processing plant

    International Nuclear Information System (INIS)

    Momose, T.; Tsujimura, N.; Tasaki, T.; Kanai, K.; Hayashi, N.; Shinohara, K.

    2001-01-01

    24 Na in the human body, activated by neutrons emitted at the JCO criticality accident, was observed for 62 subjects, where 148 subjects were measured by the whole body counter of JNC Tokai Works. The 148 subjects, including JCO employees and the contractors, residents neighboring the site and emergency service officers, were measured by the whole-body counter. The neutron-energy spectrum around the facility was calculated using neutron transport codes (ANISN and MCNP), and the relation between an amount of activated sodium in human body and neutron dose was evaluated from the calculated neutron energy spectrum and theoretical neutron capture probability by the human body. The maximum 24 Na activity in the body was 7.7 kBq (83 Bq( 24 Na)/g( 23 Na)) and the relevant effective dose equivalent was 47 mSv. (author)

  10. Diversity of Concerns in Recovery after a Nuclear Accident: A Perspective from Fukushima.

    Science.gov (United States)

    Sato, Akiko; Lyamzina, Yuliya

    2018-02-16

    Since the 2011 Fukushima nuclear accident, tremendous resources have been devoted to recovery, and the Japanese Government is gradually lifting evacuation orders. However, public concerns remain prevalent, affecting some people's return to a normal life and threatening their well-being. This study reviews government reports, academic papers, newspaper articles and conference presentations with the aim of obtaining a better understanding of issues which relate to radiation concerns in the recovery process in the aftermath of the accident. It looks extensively at: (1) the current status of the post-accident operations and existing radiation issues in Fukushima, and (2) approaches taken to engage the public during recovery from five previous comparable nuclear and radiological events: Three Mile Island, Buenos Aires (RA-2 facility), Chernobyl, Goiânia and Tokai-mura. The findings indicate that the limitations and emerging challenges of the current recovery operations cause concerns about radiation exposure in various aspects of day-to-day life. Past experiences suggest that long-term management that take a holistic and cohesive approach is critical for restoration of sustainable livelihoods and for social re-integration. Not only actual risks but also public perceptions of risks should be carefully assessed and addressed in the process of environmental remediation.

  11. Diversity of Concerns in Recovery after a Nuclear Accident: A Perspective from Fukushima

    Directory of Open Access Journals (Sweden)

    Akiko Sato

    2018-02-01

    Full Text Available Since the 2011 Fukushima nuclear accident, tremendous resources have been devoted to recovery, and the Japanese Government is gradually lifting evacuation orders. However, public concerns remain prevalent, affecting some people’s return to a normal life and threatening their well-being. This study reviews government reports, academic papers, newspaper articles and conference presentations with the aim of obtaining a better understanding of issues which relate to radiation concerns in the recovery process in the aftermath of the accident. It looks extensively at: (1 the current status of the post-accident operations and existing radiation issues in Fukushima, and (2 approaches taken to engage the public during recovery from five previous comparable nuclear and radiological events: Three Mile Island, Buenos Aires (RA-2 facility, Chernobyl, Goiânia and Tokai-mura. The findings indicate that the limitations and emerging challenges of the current recovery operations cause concerns about radiation exposure in various aspects of day-to-day life. Past experiences suggest that long-term management that take a holistic and cohesive approach is critical for restoration of sustainable livelihoods and for social re-integration. Not only actual risks but also public perceptions of risks should be carefully assessed and addressed in the process of environmental remediation.

  12. Accidents, troubles and others in nuclear fuel facilities in fiscal year 1988

    International Nuclear Information System (INIS)

    1990-01-01

    The number of the accidents, troubles and others reported on the basis of the 'Law concerning the regulation of nuclear raw material substances, nuclear fuel substances and nuclear reactors' in fiscal year 1988 was one. On February 23, 1989, in the controlled area of the plutonium waste treatment development facilities in Tokai Works. Power Reactor and Nuclear Fuel Development Corp., when one worker entered from a corridor into the material store, he fell down by mistake and broke the left collarbone, which required the hospitalization for about one month. (K.I.)

  13. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 23, 2011, 6:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 23 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 23, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  14. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 22, 2011, 6:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 22 mars 2011 a 06 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 22, 2011, at 6:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  15. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 24, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 24 mars 2011 a 08 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 24, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  16. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 29, 2011, 12:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 29 mars 2011 a 12h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 29, 2011, at 12:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  17. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 21, 2011, 3:00 PM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 21 mars 2011 a 15 heures

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 21, 2011, at 3:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  18. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 25, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 25 mars a 08h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 25, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  19. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 26, 2011, 10:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 26 mars 2011 a 10h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 26, 2011, at 10:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  20. Nuclear facilities situation in Japan after the major earthquake of March 11, 2011. March 28, 2011, 8:00 AM status; Situation des installations nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du 28 mars 2011 a 08h00

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 28, 2011, at 8:00 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of all 6 reactors of the Fukushima I site (Dai-ichi) and of their spent fuel pools, as well as the situation of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  1. Situation of nuclear industry in Japan

    International Nuclear Information System (INIS)

    2004-03-01

    This document presents the situation of nuclear industry in Japan: cooperation with France in the domain of the fuel cycle (in particular the back-end) and of for the industrial R and D about fast reactors and nuclear safety; present day situation characterized by a series of incidents in the domain of nuclear safety and by an administrative reorganization of the research and safety organizations; power of local representatives, results of April 2003 elections, liberalization of the electric power sector, impact of the TEPCO affair (falsification of safety reports) on the nuclear credibility, re-start up of the Monju reactor delayed by judicial procedures, stopping of the program of MOX fuel loading in Tepco's reactors, discovery of weld defects in the newly built Rokkasho-mura reprocessing plant, an ambitious program of reactors construction, the opportunity of Russian weapons dismantling for the re-launching of sodium-cooled fast reactors; the competition between France and Japan for the setting up of ITER reactor and its impact of the French/Japanese partnership. (J.S.)

  2. Dose evaluation on the basis of {sup 24}Na activity in the human body for the criticality accident at JCO Tokai nuclear fuel processing plant

    Energy Technology Data Exchange (ETDEWEB)

    Momose, T.; Tsujimura, N.; Tasaki, T.; Kanai, K.; Hayashi, N.; Shinohara, K. [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

    2001-11-01

    {sup 24}Na in the human body, activated by neutrons emitted at the JCO criticality accident, was observed for 62 subjects, where 148 subjects were measured by the whole body counter of JNC Tokai Works. The 148 subjects, including JCO employees and the contractors, residents neighboring the site and emergency service officers, were measured by the whole-body counter. The neutron-energy spectrum around the facility was calculated using neutron transport codes (ANISN and MCNP), and the relation between an amount of activated sodium in human body and neutron dose was evaluated from the calculated neutron energy spectrum and theoretical neutron capture probability by the human body. The maximum {sup 24}Na activity in the body was 7.7 kBq (83 Bq({sup 24}Na)/g({sup 23}Na)) and the relevant effective dose equivalent was 47 mSv. (author)

  3. Field testing of near-real-time materials accountancy at the PNC-Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Miura, N.; Masui, J.; Komatsu, H.; Todokoro, A.; Iwanaga, M.; Kusano, T.; Komori, Y.; Lovett, J.

    1987-01-01

    In 1985 a decision was taken to conduct a joint PNC-IAEA field test under the JASPAS support programme during the 85-2 campaign. The purpose of the field test, as with the earlier internal field test work performed by PNC, was to demonstrate the practicality of near-real-time accountancy using the ten day detection time model and to collect meaningful real data (as contrasted with model data) to evaluate the potential effectiveness of near-real-time accountancy in IAEA safeguards. This report summarizes, discusses and evaluates the data collected, not only during the 85-2 joint field test, but also during all previous campaigns. Chapter 2 gives a description of near-real-time accountancy as it has developed at PNC-Tokai, although the reader is referred to (3) for a more complete description. Chapter 3 reviews the procedures followed in the collection of the data, in particular during the 85-2 campaign joint field test. Chapter 4 presents the ''raw'' data collected. Chapter 5 then presents what is here termed an ''Engineering Evaluation'' of the data. The discussion in Chapter 5 is directed at a technical understanding of the data and at the resolution of a few identified problems which otherwise limit the usefulness of the data, not at a mathematical evaluation of possible diversion detection. The discussion accordingly is largely qualitative and subjective. Chapter 5 also presents a brief analysis of the data in terms of the ''running book inventory'' concept which some have suggested would be simpler and at least adequately effective. Chapter 6 discusses a number of important questions regarding work load, effect of unmeasured inventory fluctuation, data requirement, verification and authentication, and effectiveness of NRTA. Finally, Chapter 7 summarizes the conclusions which can be drawn from the field test work

  4. Dose evaluation on the basis of {sup 24}Na activity in the human body for the criticality accident at JCO Tokai nuclear fuel processing plant

    Energy Technology Data Exchange (ETDEWEB)

    Momose, T.; Tsujimura, N.; Tasaki, T.; Kanai, K.; Hayashi, N.; Shinohara, K. [Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)

    2000-07-01

    Sodium-24({sup 24}Na) generated in human body due to neutron activation was measured by whole body counter (WBC) in JNC Tokai works. Total 148 persons (JCO employees and contractor, public member, fire fighters, etc.) were measured and {sup 24}Na was detected in the 62 persons. Neutron energy spectrum around the facility was calculated using ANISN and MCNP code and estimated mean capture probability {xi} of neutron for human body at this accident was around 0.25-0.28 at any distance from the center of the precipitation tank. Effective dose equivalent for the 62 persons were estimated based on the calculated conversion factors from {sup 24}Na specific activity to neutron dose. Maximum {sup 24}Na activity was 7.7 kBq (83 Bq({sup 24}Na)/g({sup 23}Na)) in total body and the evaluated effective dose equivalent was 47 mSv. (author)

  5. Good practice at Tokai No. 2 Power Station at the 2011 off the Pacific coast of Tohoku Earthquake

    International Nuclear Information System (INIS)

    Takeuchi, Kimihito

    2017-01-01

    At Tokai No. 2 Power Station, one of the three seawater pumps for cooling the emergency diesel generator (D/G) became unusable due to the tsunami caused by the 2011 off the Pacific coast of Tohoku Earthquake, and one of the functions of two residual heat removal systems was lost. However, due to the cooperation and accurate judgment of many power station staff, partner companies, and many stakeholders, cold shutdown was successfully achieved. This is the results of day-to-day power plant operation management and correct response to the tasks that occurred during response process. Good practice included the following items. (1) Continuous tsunami countermeasures: Although a serious accident was escaped by level raising work, the above mentioned seawater pump function loss occurred due to the incomplete part. (2) Judgment on core cooling at the time of D/G function loss. (3) Early securing of preliminary power and fuel. (4) Power securing for waste disposal system. (5) Reflection of precedent cases and experiences: Installation of seismic isolation building as emergency measures, fixation of fluorescent lamp louvers, and earthquake response drills at central control room. (6) Collaboration among departments: Arrangement of communicators other than operators, preparation of equipment/articles corresponding to large tsunami warnings, placement of monitoring personnel, placement of personnel for check of power interchange, and securing of a circulation bus for commuting. (A.O.)

  6. The second periodic safety review report of Tokai Reprocessing Plant [JAEA-Technology--2016-007-PT1

    International Nuclear Information System (INIS)

    Shirai, Nobutoshi; Miura, Yasushi; Tachibana, Ikuya; Omori, Satoru; Wake, Junichi; Fukuda, Kazuhito; Nakano, Takafumi; Nagasato, Yoshihiko

    2016-07-01

    The periodic safety review of Tokai Reprocessing Plant (TRP) is an activity to confirm the application of the safety activity implementation and to give effective additional measures for the facility safety and the improvement of its reliability. We implemented 4 items as follows; (1) evaluation of safety activity implementation, (2) evaluation of status of safety activities reflecting the latest technical knowledges, (3) technical evaluation about aging degradation, and (4) planning measures about a 10-years-plan that the operator shall implement in order to keep the facility condition. We summarized this report as the result of research and evaluation of above 4 items as the second periodic safety review at TRP. About (1), we researched about the 8 items that are QA activities, operation management, maintenance management, etc. We confirmed the result that we are adequately expanding its safety activities by preparing the necessary documents and schemes, and so on. About (2), we researched them in view point of safety research results and technology development results and confirmed that we reflect latest knowledges into our facility and make efforts for improvement of safety and reliability. About (3), we can keep the safety of the facilities important to safety and the sea discharge line, under assumption of the present maintenance till the next aging evaluation, because no 'focuses for aging degradation' exist which we cannot deny the gap between the initial prediction and actual condition, by measurements and technical view. About (4), by the technical results of aging degradation evaluation, we found no additional safety plans into maintenance strategies. (author)

  7. Dynamic design load of type 2 water-flow capsule in Nuclear Safety Research Reactor in Tokai Research Establishment of Japan Atomic Energy Research Institute, and its reuse test

    International Nuclear Information System (INIS)

    1981-01-01

    A report by the Nuclear Safety Bureau of the Science and Technology Agency to the Nuclear Safety Commission was presented on the validity of the dynamic design load of type 2 water-flow capsule and the method of its reuse test. The safety in both aspects of the capsule was confirmed. The Nuclear Safety Research Reactor (NSRR), in which the water-flow capsule is set, is a swimming pool type reactor, fueled with enriched uranium, having heat output of 300 kW in normal operation and maximum instantaneous heat output of 23,000 MW in pulse operation. The type 2 water-flow capsule, with the initial conditions simulating a power generating LWR plant and being appropriately set, is used to acquire the data on fuel behavior and destructive power in pulse irradiation. (J.P.N.)

  8. Dynamic design load of type 2 water-flow capsule in Nuclear Safety Research Reactor in Tokai Research Establishment of Japan Atomic Energy Research Institute, and its reuse test

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    A report by the Nuclear Safety Bureau of the Science and Technology Agency to the Nuclear Safety Commission was presented on the validity of the dynamic design load of type 2 water-flow capsule and the method of its reuse test. The safety in both aspects of the capsule was confirmed. The Nuclear Safety Research Reactor (NSRR), in which the water-flow capsule is set, is a swimming pool type reactor, fueled with enriched uranium, having heat output of 300 kW in normal operation and maximum instantaneous heat output of 23,000 MW in pulse operation. The type 2 water-flow capsule, with the initial conditions simulating a power generating LWR plant and being appropriately set, is used to acquire the data on fuel behavior and destructive power in pulse irradiation.

  9. Wind power development field test project at Rokkasho-mura, Aomori prefecture. Close survey on wind conditions; Aomoriken Rokkashomura ni okeru furyoku kaihatsu field test jigyo (fukyo seisa) hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    A survey was made on wind conditions in Rokkasho-mura, Kamikita-gun, Aomori prefecture, on the assumption that a wind power generation system was installed therein. The survey period was one year from Oct., 1998 to Sept., 1999. The observations were carried out on the average wind velocity, average wind direction, standard deviation of velocity, and the maximum instantaneous wind velocity. With a fixed point observation at 20 m above ground, and with the minimum observation time unit of 10 minutes, an average value during the 10 minutes was determined as the measurement of each category. However, the maximum instantaneous wind velocity was determined on the measurement with the minimum observation time unit of 2 seconds. The annual average wind velocity was 4.6 m/s, the maximum wind velocity during the period was 26.0 m/s, the prevailing wind direction was NW (20.8%), WNW (18.0%), and SE (13.5%), and the total occurrence rate of wind direction at the wind axis of NW-SE was 75.7%. The intensity of turbulence was 0.25 at a wind velocity of 2.0 m/s or above and was 0.21 at 4.0 m/s or above. An estimated annual operation rate of a windmill was 59-72% using the rated value of a 150 kW, 300 kW and 750 kW class windmills. (NEDO)

  10. Effort to grapple with improvement of security and reliability of nuclear power plant. Actions of the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Ishiguma, Kazuo

    2012-01-01

    Following the Great Tohoku Earthquake in 2011, Tokai No.2 reactor was shut down automatically. Three of emergency diesel generators worked automatically at loss-of-offsite-power and began to work the cooling system of reactor. The reactor could be kept stable and safe in cold state by management of power from the gas turbine electric generator and power source car. Actions of Japan Atomic Power Company (JAPC) for cold shutdown and Tsunami were stated. Inspection results after the earthquake and testimony of staff was described. Countermeasure of improvement of safety of nuclear power station is explained by ensuring of power source and water supply, crisis management system, countermeasure of accident, ensuring, and training of workers, and action for better understanding of reliance. (S.Y.)

  11. Some aspects of dose evaluation, 1

    International Nuclear Information System (INIS)

    Sumiya, Misako

    1979-01-01

    Survey on leaf vegetable and milk consumptions was carried out on infants and children under school age in Tokai-mura in order to pick up critical path in relation to the release of iodine-131 into the air. In our country, cows are mostly fed on imported assorted feed. So cow's milk is not always a reflex of the atmospheric release of the nuclide. As far as this survey goes, infants are fed on mother's milk. Therefore attention must be paid to the chain of leaf vegetable-nursing mother-mother's milk-infant. It may be said that leaf vegetable should be actually a critical path for children after the weaning period. It is well-known that the transfer rate of iodine-131 to thyroid is influenced by the ingestion of stable iodine. In general, we Japanese take considerable amount of stable iodine through marine food, specifically through algae. So survey on marine food consumption was carried out in order to estimate daily intake of the nuclide. Results obtained are more than 700 μg, 1.5 mg and 2.2 mg for children of 0.5 - 1.5, 1.5 - 3 and 3 - 5 years old, respectively. It is conjectured that infants fed on mother's milk take about 200 μg of the nuclide every day. (author)

  12. Accumulation of radiocesium and trace elements in mushrooms collected from Japanese forests

    International Nuclear Information System (INIS)

    Yoshida, S.; Muramatsu, Y.; Ban-Nai, T.

    1996-01-01

    Concentrations of 137 Cs, 134 Cs and 40 K for 124 mushroom species (284 samples) collected from Japanese forests during 1989 to 1991 were studied. The levels of 137 Cs m mushrooms varied very widely ranging from 40 K were relatively constant. The median concentrations of 137 Cs and 40 K were 53 and 1180 Bq/kg (dry wt), respectively. The 134 Cs discharged through the Chernobyl accident was detected only in 33 mushroom samples. The proportions of 137 Cs originating from the Chernobyl accident m these mushrooms were in the range 137 Cs concentrations in mycorrhizal fungi tended to be higher than those in saprophytes. The concentrations in many mushrooms reflected the layers m which their mycelia were growing. In addition to the radionuclides, many stable elements including stable Cs in mushroom and soil samples were determined. A good correlation between 137 Cs and stable Cs was observed for 33 mushrooms collected from a pine forest on sandy soil near coast in Tokai-mura, Ibaraki, indicating that mushroom available Cs is recycling in the pine forest with the constant 137 Cs/stable Cs ratio. Accumulations from soil to mushrooms were observed for Cd, Rb, Zn, Cu. Cs, K, Mg, Mn, Ni and Tl. Through cultivation experiments in flasks using radiotracers, 137 Cs, 65 Zn and 54 Mn were observed to be accumulated in mushrooms. (author)

  13. Studies on the characteristics of the separated type heat pipe system with non-condensible gas for the use of the passive decay heat removal in reactor systems

    International Nuclear Information System (INIS)

    Hayashi, Takao; Iigaki, Kazuhiko; Ohashi, Kazutaka; Hayakawa, Hitoshi; Yamada, Masao.

    1995-01-01

    This study is the fundamental research by experiments to aim at the development of the complete passive decay heat removal system on the modular reactor systems by the form of the separated type of heat pipe system utilizing the features of both the big latent heat for vaporization from water to steam and easy transportation characteristics. Special intention in our study on the fundamental experiments is to look for the effects in such a separated type of heat pipe system to introduce non-condensible gas such as nitrogen gas together with the working fluid of water. Many interesting findings have been obtained so far on the experiments for the variable conductance heat pipe characteristics from viewpoint of the actual application on the aim said above. This study has been carried out by the joint study between Tokai University and Fuji Electric Co., Ltd. and this paper is made up from the several papers presented so far at both the national and international symposiums under the name of joint study of the both bodies. (author)

  14. Comparison of activation cross section measurements and experimental techniques for fusion reactor technology. Summary report of the IAEA specialists' meeting held in St. Petersburg, Russia, 7 to 9 September 1994

    International Nuclear Information System (INIS)

    Pashchenko, A.B.

    1995-02-01

    The report contains the Summary of the IAEA Specialists' Meeting on ''Comparison of Activation Cross Section Measurements and Experimental Techniques for Fusion Reactor Technology''. The meeting was organized by the IAEA Nuclear Data Section (NDS) with co-operation and assistance of local organizers from the V.G. Khlopin Radium Institute, KRI, and held in St. Petersburg, Russia, from 7 to 9 September 1994. The aim of the meeting was to discuss and evaluate the preliminary results of the researches carried out in the framework of the international programme on Comparison of Activation Cross Section Measurements and Experimental Techniques for Fusion Reactor Technology coordinated by the IAEA Nuclear Data Section and to identify further measurements and actions of participating laboratories. The detailed conclusions and recommendations of the meeting are presented in Attachment 1 of the summary report. It was confirmed that for further comparison of experimental techniques the experimental groups at JAERI (Tokai, Japan), KRI (St. Petersburg, Russia), IPPE (Obninsk, Russia) and IEP (Debrecen, Hungary) will join in a collaborative program on comparing their measurement techniques and do measurements for reactions where discrepancies between their previous measurements exist. In cases where the JAERI results are the only existing data or deviate strongly from previous measurements, collaboration between KRI, IEP, IPPE and other institutions can consider measurements of these cross sections in order to clarify the situation. (author)

  15. Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

    Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

  16. Reactor core in FBR type reactor

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

    1989-01-01

    In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

  17. Concerning change in nuclear fuel material processing business at Tokai plant of Japan Nuclear Fuel Conversion Co., Ltd. Report to Prime Minister

    International Nuclear Information System (INIS)

    1988-01-01

    The Nuclear Safety Committee of Japan on April 7, 1988, directed the Nuclear Safety Expert Group to make a study concerning the proposed changes in the nuclear fuel material processing business at the Tokai plant of Japan Nuclear Fuel Conversion Co., Ltd., and after receiving and reviewing the report from the Group, concluded that the proposed changes should be approved. The conclusions together with results of the study were reported to the Prime Minister on June 9. 1988. The proposed plan included changes in the maximum processing capacity of the No.2 processing facilities; construction of a new powder warehouse and changes in the maximum capacity of the No.3 powder storage room and No.2 powder warehouse; reuse of No.1 powder warehouse as No.3 solid waste warehouse; and abolition of UF 6 dispensing equipment installed at the No.1 processing facilities and changes in procedures for criticality control of the hydrolysis facilities. The safety of these facilities were studied in terms of resistance to earthquakes, prevention of fire and explosion, criticality control, operations of waste processing, and radiation management. Exposure doses expected during normal operations were also examined to confirm that the possible exposure doses to the public would be sufficiently small. (N.K.)

  18. Reference data for the medical treatment by 'Yayoi'

    International Nuclear Information System (INIS)

    1976-12-01

    ''Yayoi'' is the nickname for the fast neutron reactor of the University of Tokyo and reached to the critical range in April, 1970 for the first time. It is an air cooled type fast reactor for condensed uranium installed in Tokai Village, Ibaraki Prefecture with thermal powers of 2 Kw (steady working), 200 Kw (unsteady working) or 1 Gw (reactive pulse working). There were submitted to explain about summaries of irradiation equipment and medical irradiation field, and technical capacity of irradiation treatment by ''Yayoi''. Additional data were also prepared explaining the purpose of medical treatment, expected dose, counterplans for security, minimization of general exposed dose radiation control and in emergency cases. (Kobatake, H.)

  19. Reactor core and initially loaded reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Koyama, Jun-ichi; Aoyama, Motoo.

    1989-01-01

    In BWR type reactors, improvement for the reactor shutdown margin is an important characteristic condition togehter with power distribution flattening . However, in the reactor core at high burnup degree, the reactor shutdown margin is different depending on the radial position of the reactor core. That is , the reactor shutdown margin is smaller in the outer peripheral region than in the central region of the reactor core. In view of the above, the reactor core is divided radially into a central region and as outer region. The amount of fissionable material of first fuel assemblies newly loaded in the outer region is made less than the amount of the fissionable material of second fuel assemblies newly loaded in the central region, to thereby improve the reactor shutdown margin in the outer region. Further, the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower portion of the first fuel assemblies is made smaller than the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower region of the second fuel assemblies, to thereby obtain a sufficient thermal margin in the central region. (K.M.)

  20. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    Baeten, P.

    2006-01-01

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  1. Reactor core of FBR type reactor

    International Nuclear Information System (INIS)

    Hayashi, Hideyuki; Ichimiya, Masakazu.

    1994-01-01

    A reactor core is a homogeneous reactor core divided into two regions of an inner reactor core region at the center and an outer reactor core region surrounding the outside of the inner reactor core region. In this case, the inner reactor core region has a lower plutonium enrichment degree and less amount of neutron leakage in the radial direction, and the outer reactor core region has higher plutonium enrichment degree and greater amount of neutron leakage in the radial direction. Moderator materials containing hydrogen are added only to the inner reactor core fuels in the inner reactor core region. Pins loaded with the fuels with addition of the moderator materials are inserted at a ratio of from 3 to 10% of the total number of the fuel pins. The moderator materials containing hydrogen comprise zirconium hydride, titanium hydride, or calcium hydride. With such a constitution, fluctuation of the power distribution in the radial direction along with burning is suppressed. In addition, an absolute value of the Doppler coefficient can be increased, and a temperature coefficient of coolants can be reduced. (I.N.)

  2. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

    After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

  3. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

    1987-01-01

    Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

  4. Wind effect on currents in a thin surface layer of coastal waters faced open-sea

    International Nuclear Information System (INIS)

    Nakano, Masanao; Isozaki, Hisaaki; Isozaki, Tokuju; Nemoto, Masashi; Hasunuma, Keiichi; Kitamura, Takashi

    2009-01-01

    Two-years of continuous observation of wind and current were carried out to investigate the relationship between them in the coastal waters off Tokai-mura, Ibaraki prefecture. Three instruments to measure the current were set in a thin surface layer of 3 m above the strong pycnocline, which is a common feature in coastal waters. Both of the power spectra of wind and currents showed very similar features, an outstanding high peak at 24-hour period and a range of high peaks longer than several-days period. The long term variation of the wind field always contained north-wind component, which contributed to forming the southward current along the shore throughout the year. A high correlation coefficient (0.64) was obtained between the wind and the current at a depth of 0.5 m on the basis of the two-year observation. Harmonic analysis revealed that an outstanding current with 24-hour period was the S 1 component (meteorological tide), and was driven by land and sea breezes. These breezes also contained solar tidal components such as K 1 , P 1 and S 2 . These wind components added their own wind driven currents on the original tidal currents. This meant that land and sea breezes generated wind driven currents with solar tidal periods which behaved like astronomical tidal currents. As result, coastal currents contained pseudo tidal currents which behaved like astronomical tidal currents. (author)

  5. Benchmarking of the FENDL-3 Neutron Cross-Section Data Library for Fusion Applications

    International Nuclear Information System (INIS)

    Fischer, U.; Kondo, K.; Angelone, M.; Batistoni, P.; Villari, R.; Bohm, T.; Sawan, M.; Walker, B.; Konno, C.

    2014-03-01

    This report summarizes the benchmark analyses performed in a joint effort of ENEA (Italy), JAEA (Japan), KIT (Germany), and the University of Wisconsin (USA) with the objective to test and qualify the neutron induced general purpose FENDL-3.0 data library for fusion applications. The benchmark approach consisted of two major steps including the analysis of a simple ITER-like computational benchmark, and a series of analyses of benchmark experiments conducted previously at the 14 MeV neutron generator facilities at ENEA Frascati, Italy (FNG) and JAEA, Tokai-mura, Japan (FNS). The computational benchmark revealed a modest increase of the neutron flux levels in the deep penetration regions and a substantial increase of the gas production in steel components. The comparison to experimental results showed good agreement with no substantial differences between FENDL-3.0 and FENDL-2.1 for most of the responses analysed. There is a slight trend, however, for an increase of the fast neutron flux in the shielding experiment and a decrease in the breeder mock-up experiments. The photon flux spectra measured in the bulk shield and the tungsten experiments are significantly better reproduced with FENDL-3.0 data. In general, FENDL-3, as compared to FENDL-2.1, shows an improved performance for fusion neutronics applications. It is thus recommended to ITER to replace FENDL-2.1 as reference data library for neutronics calculation by FENDL-3.0. (author)

  6. Organizational factors and reoccurrence protection on the JCO nuclear critical accident

    International Nuclear Information System (INIS)

    Takano, Kenichi

    2000-01-01

    A nuclear critical accident formed at a nuclear fuel conversion factory in Tokai-mura on September, 1999 became gradually clear not to be a simple human error formed at a level of workmen but to be an organizational error or accident relating to various organizational factors. As a nuclear power facility adopts a depth protection system fundamentally, a large accident with serious danger would not form only by a single trouble and a human error and unless some factors overlaps. By reviewing recent serious accidents and troubles, all of them seem to have a keyword of 'organizational factor'. In the JCO accident, there are some organizational factors such as a climate deviating from a manual, insufficient and loose check against change of procedure, reduction of operators from a reason of profit priority, attitude on priority of working efficiency, and so forth, which are partially common to the Chernobyl accident. Recently, accidents and troubles impossible to make them a cause of simple human error by a person but to have to say an organizational error, have increased. This trend seems to depend upon not only complication and scale-up of technology system but also graduate change of social and management systems operating them. Therefore, it seems to be necessary to introduce a concept of depth protection (multiple protection) in order to keep its reliability and safety when complicating and scaling-up of system. (G.K.)

  7. A study of the modifications of nuclear instrumentation systems for JRR-2

    International Nuclear Information System (INIS)

    Azim, Mohammad; Horiki, Ooichiro; Sato, Mitsugu

    1978-04-01

    In this report a comparative study has been carried out between the original A.M.F. design and the modified design for the nuclear instrumentation systems of the Research Reactor JRR-2, at the Tokai Research Establishment of JAERI. Due to a fire accident in the control room, in July 1968, the originally designed nuclear instrumentation systems, using conventional vacuum tube circuits, were destroyed and were replaced by the modified design, incorporating solid state linear integrated circuits as basic circuit components. The results of the reactor instrumentation systems modification at JRR-2 are very encouraging as the operating efficiency of the Reactor registered an improvement of 43%. Moreover the safety aspects have been fully taken care of in the new design and the reactor is well guarded against all possible instrument failures and human errors. This report presents the basic theory of operation of the two designs alongwith a comparative safety analysis. (auth.)

  8. Outline of facility for studying high level radioactive materials (CPF) and study programmes

    International Nuclear Information System (INIS)

    Sakamoto, Motoi

    1983-01-01

    The Chemical Processing Facility for studying high level radioactive materials in Tokai Works of Power Reactor and Nuclear Fuel Development Corp. is a facility for fundamental studies centering around hot cells, necessary for the development of fuel recycle techniques for fast breeder reactors, an important point of nuclear fuel cycle, and of the techniques for processing and disposing high level radioactive liquid wastes. The operation of the facility was started in 1982, for both the system A (the test of fuel recycle for fast breeder reactors) and the system B (the test of vitrification of high level liquid wastes). In this report, the outline of the facility, the contents of testings and the reflection of the results are described. For the fuel recycle test, the hot test of the spent fuel pins of JOYO MK-1 core was started, and now the uranium and plutonium extraction test is underway. The scheduled tests are fuel solubility, the confirmation of residual properties in fuel melting, the confirmation of extracting conditions, the electrolytic reduction of plutonium, off-gas behaviour and the test of material reliability. For the test of vitrification of high level liquid wastes, the fundamental test on the solidifying techniques for the actual high level wastes eluted from the Tokai reprocessing plant has been started, and the following tests are programmed: Assessment of the properties of actual liquid wastes, denitration and concentration test, vitrification test, off-gas treatment test, the test of evaluating solidified wastes, and the test of storing solidified wastes. These test results are programmed to be reflected to the safety deliberation and the demonstration operation of a vitrification pilot plant. (Wakatsuki, Y.)

  9. Nuclear reactor construction with bottom supported reactor vessel

    International Nuclear Information System (INIS)

    Sharbaugh, J.E.

    1987-01-01

    This patent describes an improved liquid metal nuclear reactor construction comprising: (a) a nuclear reactor core having a bottom platform support structure; (b) a reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core; (c) a containment structure surrounding the reactor vessel and having a sidewall spaced outwardly from the reactor vessel side wall and having a base mat spaced below the reactor vessel bottom end wall; (d) a central small diameter post anchored to the containment structure base mat and extending upwardly to the reactor vessel to axially fix the bottom end wall of the reactor vessel and provide a center column support for the lower end of the reactor core; (e) annular support structure disposed in the reactor vessel on the bottom end wall and extending about the lower end of the core; (f) structural support means disposed between the containment structure base mat and bottom end of the reactor vessel wall and cooperating for supporting the reactor vessel at its bottom end wall on the containment structure base mat to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event; (g) a bed of insulating material disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall; freely expand radially from the central post as it heats up while providing continuous support thereof; (h) a deck supported upon the wall of the containment vessel above the top open end of the reactor vessel; and (i) extendible and retractable coupling means extending between the deck and the top open end of the reactor vessel and flexibly and sealably interconnecting the reactor vessel at its top end to the deck

  10. Comparison of neutron dose measured by Albedo TLD and etched tracks detector at PNC plutonium fuel facilities

    International Nuclear Information System (INIS)

    Tsujimura, N.; Momose, T.; Shinohara, K.; Ishiguro, H.

    1996-01-01

    Power Reactor and Nuclear Fuel Development Corporation (PNC) has fabricated Plutonium and Uranium Mixed OXide (MOX) fuel for FBR MONJU at Tokai works. In this site, PNC/Panasonic albedo TLDs/1/ are used for personnel neutron monitoring. And a part of workers wore Etched Tracks Detector (ETD) combined with TLD in order to check the accuracy of the neutron dose estimated by albedo TLD. In this paper, the neutron dose measured by TLD and ETD in the routine monitoring is compared at PNC plutonium fuel facilities. (author)

  11. Current state of the communications program concerning nuclear energy following the JCO accident

    International Nuclear Information System (INIS)

    Mitsui, Rie

    2001-01-01

    Full text: Public trust in nuclear energy was significantly affected by a criticality accident that occurred in September 1999 at JCO's uranium re-conversion plant in Tokai-mura Village, Ibaraki Prefecture, some 120 kilometres north-east of Tokyo. An opinion survey was taken with local citizens in December that year, asking them how their views on nuclear energy changed after the accident. The survey findings indicate a grave fact that the citizens, who had lived in harmony with nuclear energy for the past 40 years, lost their confidence in this energy source because of the accident. The mishap also led to severer public opinion on nuclear energy at the nation-wide level, bringing forth a serious impediment to such projects as the siting of new nuclear power plants, the use of plutonium in light water reactors, intermediate storage of spent nuclear fuel, and the promotion of high-level radioactive waste disposal. Japan Atomic Energy Relations Organisation analysed the critical situation surrounding nuclear energy development in the country. Based on the analysis results, JAERO is now actively promoting an interactive, participatory program that meets people's needs, in an effort to regain public trust in nuclear energy. We, at JAERO, believe that greater importance should be attached to the offer of relevant information to the rising generation that will play a leading role in future society. The most typical of JAERO activities for junior and senior high school students include an Essay Content launched in 1968 in commemoration of Atomic Energy Day on October 26 every year and a Radiation Workshop established in 1978. Through more than 11,000 essays collected from junior and senior high school students across the county, this report discusses how these young people think of the JCO criticality accident and what they expect of nuclear energy development in the years ahead. Amid growing public concern with radiation following the JCO accident, the report also

  12. Generation IV reactors: reactor concepts

    International Nuclear Information System (INIS)

    Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

    2003-01-01

    Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

  13. Estimation of radiation exposed area by the nuclear accident occurred at Tokai village using ESR measurements of household sugar

    International Nuclear Information System (INIS)

    Kuzuya, Masayuki; Kondo, Shinichi; Ito, Kousuke; Sawa, Takashi

    2001-01-01

    The area of radiation exposure by the nuclear accident occurred at Tokai village in 1999 was estimated by the ESR measurement of 95 household sugar samples collected from the accident area. These samples were roughly classified into three types of sugar, fine white sugar, fine brown sugar and coarse brown sugar. The control fine white sugar showed no radical in the ESR spectrum, while those of fine brown sugar and coarse brown sugar showed the presence of a small amount of radicals. It was also shown that, among these three kinds of sugar, the radical concentration of fine white sugar sampled from wooden houses at the area similar to each other did not vary much with the samples, while those of fine brown sugar and coarse brown sugar varied to a considerable extent. Thus, the fine white sugar is considered to be more suitable for the estimation of the level of radiation exposure. The radical concentration of each fine white sugar sample was plotted against the distance from the site of the nuclear accident with a correction of the difference in the shielding effect between concrete houses and wooden houses. The samples obtained at more than 2 km north of the site of nuclear accident showed no ESR spectral signal to a detectable extent. On the other hand, the ESR spectra were observed from the samples obtained within 10 km south and 4 km west of the accident site. These results suggest that the radiation exposure by the contaminant blown by the northeast wind blowing on the day of the accident may occur at the south and west areas. (author)

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

    Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

  15. The CAREM reactor and present currents in reactor design

    International Nuclear Information System (INIS)

    Ordonez, J.P.

    1990-01-01

    INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author) [es

  16. Risk management and role of schools of the Tokai-village radiation accident in 1999. Safety education and risk management before and during the radiation accident from the standpoint of school nurse teachers

    International Nuclear Information System (INIS)

    Akisaka, Masafumi; Nakamura, Tomoko; Satake, Tsuyoshi

    2002-01-01

    The purpose of this study is to evaluate safety education and risk management in the neighborhood schools before and during the radiation accident in the Tokai-village in 1999 from the standpoint of school nurse teachers. Eighty-six school nurse teachers from 44 elementary, 25 junior-high, 14 high and 3 handicapped children's schools were surveyed within neighboring towns and villages. The main results were as follows: There had been few risk management systems against the potential radiation accidents including safety education, radiological monitoring and protection in all of the neighboring schools. There were no significant difference in risk management systems among the schools before the accident, though the anxiety rates of school children were significantly higher in the schools nearest to the accident site. Some radiation risk management systems must be established in neighboring schools including safety education, radiological monitoring and protection. (author)

  17. Neutron behavior, reactor control, and reactor heat transfer. Volume four

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant)

  18. Outline of the Chemical Processing Facility (CPF)

    International Nuclear Information System (INIS)

    Arita, Katsuhiko

    1978-01-01

    Concerning the Chemical Processing Facility (CPF), a high level radioactive material research facility, to be installed in Tokai Works of Power Reactor and Nuclear Fuel Development Corporation (PNC), the detailed design and the governmental safety inspection were finished. The construction has been already started, and it will be completed in 1980. Under the national policy of establishing a nuclear fuel cycle, PNC is now carrying out the development of its downstream technology. The objects of the Chemical Processing Facility are the researches of the treatment techniques of high level radioactive liquid wastes from fuel reprocessing and of the reprocessing of fast reactor fuel. The following matters are described: purpose of the CPF, i.e. fast reactor fuel reprocessing and high-level liquid waste treatment; construction of the CPF, i.e. buildings, cells and an exhaust stack; test systems, i.e. fuel reprocessing and liquid waste vitrification; and facility safety. (Mori, K.)

  19. Building good relationships with neighbors of Japan's oldest plant, Tsuruga

    International Nuclear Information System (INIS)

    Hata, Emi

    1992-01-01

    Since its establishment in 1957 as a pioneer company of nuclear power development in Japan, the Japan Atomic Power Company (JAPC) has gained a great deal of experience with construction and operation of four nuclear power plants - one gas-cooled reactor, two boiling water reactors (BWRs), and one pressurized water reactor (PWR) - at two sites, Tsuruga and Tokai. To gain the understanding and cooperation of the local community, the Tsuruga station must keep running. Each employee is encouraged to make every possible effort not only to ensure the safe and reliable operation of the two units, but also to ensure conscientious coexistence and coprosperity within the local community. The Tsuruga office in the city and the Public Relations (PR) Pavilion (visitor's center) at the site work together as an open window of communication with the local community. Under these basic philosophies, various good neighbor activities are developed and carried out

  20. Reactor science and technology: operation and control of reactors

    International Nuclear Information System (INIS)

    Qiu Junlong

    1994-01-01

    This article is a collection of short reports on reactor operation and research in China in 1991. The operation of and research activities linked with the Heavy Water Research Reactor, Swimming Pool Reactor and Miniature Neutron Source Reactor are briefly surveyed. A number of papers then follow on the developing strategies in Chinese fast breeder reactor technology including the conceptual design of an experimental fast reactor (FFR), theoretical studies of FFR thermo-hydraulics and a design for an immersed sodium flowmeter. Reactor physics studies cover a range of topics including several related to work on zero power reactors. The section on reactor safety analysis is concerned largely with the assessment of established, and the presentation of new, computer codes for use in PWR safety calculations. Experimental and theoretical studies of fuels and reactor materials for FBRs, PWRs, BWRs and fusion reactors are described. A final miscellaneous section covers Mo-Tc isotope production in the swimming pool reactor, convective heat transfer in tubes and diffusion of tritium through plastic/aluminium composite films and Li 2 SiO 3 . (UK)

  1. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  2. Evaluation of Neutron Response of Criticality Accident Alarm System Detector to Quasi-Monoenergetic 24 keV Neutrons

    Science.gov (United States)

    Tsujimura, Norio; Yoshida, Tadayoshi; Yashima, Hiroshi

    The criticality accident alarm system (CAAS), which was recently developed and installed at the Japan Atomic Energy Agency's Tokai Reprocessing Plant, consists of a plastic scintillator combined with a cadmium-lined polyethylene moderator and thereby responds to both neutrons and gamma rays. To evaluate the neutron absorbed dose rate response of the CAAS detector, a 24 keV quasi-monoenergetic neutron irradiation experiment was performed at the B-1 facility of the Kyoto University Research Reactor. The detector's evaluated neutron response was confirmed to agree reasonably well with prior computer-predicted responses.

  3. Evaluation of neutron response of criticality accident alarm system detector to quasi-monoenergetic 24 keV neutrons

    International Nuclear Information System (INIS)

    Tsujimura, Norio; Yoshida, Tadayoshi; Yashima, Hiroshi

    2016-01-01

    The criticality accident alarm system (CAAS), which was recently developed and installed at the Japan Atomic Energy Agency's Tokai Reprocessing Plant, consists of a plastic scintillator combined with a cadmium-lined polyethylene moderator and thereby responds to both neutrons and gamma rays. To evaluate the neutron absorbed dose rate response of the CAAS detector, a 24 keV quasi-monoenergetic neutron irradiation experiment was performed at the B-1 facility of the Kyoto University Research Reactor. The detector's evaluated neutron response was confirmed to agree reasonably well with prior computer-predicted responses. (author)

  4. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  5. Roles of plasma neutron source reactor in development of fusion reactor engineering: Comparison with fission reactor engineering

    International Nuclear Information System (INIS)

    Hirayama, Shoichi; Kawabe, Takaya

    1995-01-01

    The history of development of fusion power reactor has come to a turning point, where the main research target is now shifting from the plasma heating and confinement physics toward the burning plasma physics and reactor engineering. Although the development of fusion reactor system is the first time for human beings, engineers have experience of development of fission power reactor. The common feature between them is that both are plants used for the generation of nuclear reactions for the production of energy, nucleon, and radiation on an industrial scale. By studying the history of the development of the fission reactor, one can find the existence of experimental neutron reactors including irradiation facilities for fission reactor materials. These research neutron reactors played very important roles in the development of fission power reactors. When one considers the strategy of development of fusion power reactors from the points of fusion reactor engineering, one finds that the fusion neutron source corresponds to the neutron reactor in fission reactor development. In this paper, the authors discuss the roles of the plasma-based neutron source reactors in the development of fusion reactor engineering, by comparing it with the neutron reactors in the history of fission power development, and make proposals for the strategy of the fusion reactor development. 21 refs., 6 figs

  6. Reactor physics aspects of CANDU reactors

    International Nuclear Information System (INIS)

    Critoph, E.

    1980-01-01

    These four lectures are being given at the Winter Course on Nuclear Physics at Trieste during 1978 February. They constitute part of the third week's lectures in Part II: Reactor Theory and Power Reactors. A physical description of CANDU reactors is given, followed by an overview of CANDU characteristics and some of the design options. Basic lattice physics is discussed in terms of zero energy lattice experiments, irradiation effects and analytical methods. Start-up and commissioning experiments in CANDU reactors are reviewed, and some of the more interesting aspects of operation discussed - fuel management, flux mapping and control of the power distribution. Finally, some of the characteristics of advanced fuel cycles that have been proposed for CANDU reactors are summarized. (author)

  7. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  8. Comparison between TRU burning reactors and commercial fast reactor

    International Nuclear Information System (INIS)

    Fujimura, Koji; Sanda, Toshio; Ogawa, Takashi

    2001-03-01

    Research and development for stabilizing or shortening the radioactive wastes including in spent nuclear fuel are widely conducted in view point of reducing the environmental impact. Especially it is effective way to irradiate and transmute long-lived TRU by fast reactors. Two types of loading way were previously proposed. The former is loading relatively small amount of TRU in all commercial fast reactors and the latter is loading large amount of TRU in a few TRU burning reactors. This study has been intended to contribute to the feasibility studies on commercialized fast reactor cycle system. The transmutation and nuclear characteristics of TRU burning reactors were evaluated and compared with those of conventional transmutation system using commercial type fast reactor based upon the investigation of technical information about TRU burning reactors. Major results are summarized as follows. (1) Investigation of technical information about TRU burning reactors. Based on published reports and papers, technical information about TRU burning reactor concepts transmutation system using convectional commercial type fast reactors were investigated. Transmutation and nuclear characteristics or R and D issue were investigated based on these results. Homogeneously loading of about 5 wt% MAs on core fuels in the conventional commercial type fast reactor may not cause significant impact on the nuclear core characteristics. Transmutation of MAs being produced in about five fast reactors generating the same output is feasible. The helium cooled MA burning fast reactor core concept propose by JAERI attains criticality using particle type nitride fuels which contain more than 60 wt% MA. This reactor could transmute MAs being produced in more than ten 1000 MWe-LWRs. Ultra-long life core concepts attaining more than 30 years operation without refueling by utilizing MA's nuclear characteristics as burnable absorber and fertile nuclides were proposed. Those were pointed out that

  9. Nuclear reactor types

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

  10. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    Kouts, H.

    1986-01-01

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

  11. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  12. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  13. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  14. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

    Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

  15. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  16. Research reactor standards and their impact on the TRIGA reactor community

    International Nuclear Information System (INIS)

    Richards, W.J.

    1980-01-01

    The American Nuclear Society has established a standards committee devoted to writing standards for research reactors. This committee was formed in 1971 and has since that time written over 15 standards that cover all aspects of research reactor operation. The committee has representation from virtually every group concerned with research reactors and their operation. This organization includes University reactors, National laboratory reactors, Nuclear Regulatory commission, Department of Energy and private nuclear companies and insurers. Since its beginning the committee has developed standards in the following areas: Standard for the development of technical specifications for research reactors; Quality control for plate-type uranium-aluminium fuel elements; Records and reports for research reactors; Selection and training of personnel for research reactors; Review of experiments for research reactors; Research reactor site evaluation; Quality assurance program requirements for research reactors; Decommissioning of research reactors; Radiological control at research reactor facilities; Design objectives for and monitoring of systems controlling research reactor effluents; Physical security for research reactor facilities; Criteria for the reactor safety systems of research reactors; Emergency planning for research reactors; Fire protection program requirements for research reactors; Standard for administrative controls for research reactors. Besides writing the above standards, the committee is very active in using communications with the nuclear regulatory commission on proposed rules or positions which will affect the research reactor community

  17. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  18. Improved nuclear reactor construction with bottom supported reactor vessel

    International Nuclear Information System (INIS)

    Sharbaugh, J.E.

    1987-01-01

    An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding liquid metal coolant and housing the core within the pool. A generally cylindrical concrete containment structure surrounds the reactor vessel and a central support pedestal is anchored to the containment structure base mat and supports the bottom wall of the reactor vessel and the reactor core. The periphery of the reactor vessel bore is supported by an annular structure which allows thermal expansion but not seismic motion of the vessel, and a bed of thermally insulating material uniformly supports the vessel base whilst allowing expansion thereof. A guard ring prevents lateral seismic motion of the upper end of the reactor vessel. The periphery of the core is supported by an annular structure supported by the vessel base and keyed to the vessel wall so as to be able to expand but not undergo seismic motion. A deck is supported on the containment structure above the reactor vessel open top by annular bellows, the deck carrying the reactor control rods such that heating of the reactor vessel results in upward expansion against the control rods. (author)

  19. Reactor as furnace and reactor as lamp

    International Nuclear Information System (INIS)

    Goldanskii, V.I.

    1992-01-01

    There are presented general characteristics of the following ways of transforming of nuclear energy released in reactors into chemical : ordinary way (i.e. trough the heat, mechanical energy and electricity); chemonuclear synthesis ; use of high-temperature fuel elements (reactor as furnace); use of the mixed nγ-radiation of reactors; use of the radiation loops; radiation - photochemical synthesis (reactor as lamp). Advantage and disadvantages of all above variants are compared. The yield of the primary product of fixation of nitrogen (nitric oxide NO) in reactor with the high-temperature (above ca. 1900degC) fuel elements (reactor-furnace) can exceed W ∼ 200 kg per gram of burned uranium. For the latter variant (reactor-lamp) the yield of chemical products can reach W ∼ 60 kg. per gram of uranium. Such values of W are close to or even strongly exceed the yields of chemical products for other abovementioned variants and - what is particularly important - are not connected to the necessity of archscrupulous removal of radioactive contamination of products. (author)

  20. Development of Reactor Console Simulator for PUSPATI TRIGA Reactor

    International Nuclear Information System (INIS)

    Mohd Idris Taib; Izhar Abu Hussin; Mohd Khairulezwan Abdul Manan; Nufarhana Ayuni Joha; Mohd Sabri Minhat

    2012-01-01

    The Reactor Console Simulator will be an interactive tool for operator training and teaching of PUSPATI TRIGA Reactor. Behaviour and characteristic for reactor console and reactor itself can be evaluated and understand. This Simulator will be used as complement for actual present reactor console. Implementation of man-machine interface is using computer screens, keyboard and mouse. Multiple screens are used to match the physical of present reactor console. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate the estimated reactor console parameters. (author)

  1. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  2. Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

    International Nuclear Information System (INIS)

    Greneche, D.

    2014-01-01

    This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

  3. Control of reactor coolant flow path during reactor decay heat removal

    International Nuclear Information System (INIS)

    Hunsbedt, A.N.

    1988-01-01

    This patent describes a sodium cooled reactor of the type having a reactor hot pool, a slightly lower pressure reactor cold pool and a reactor vessel liner defining a reactor vessel liner flow gap separating the hot pool and the cold pool along the reactor vessel sidewalls and wherein the normal sodium circuit in the reactor includes main sodium reactor coolant pumps having a suction on the lower pressure sodium cold pool and an outlet to a reactor core; the reactor core for heating the sodium and discharging the sodium to the reactor hot pool; a heat exchanger for receiving sodium from the hot pool, and removing heat from the sodium and discharging the sodium to the lower pressure cold pool; the improvement across the reactor vessel liner comprising: a jet pump having a venturi installed across the reactor vessel liner, the jet pump having a lower inlet from the reactor vessel cold pool across the reactor vessel liner and an upper outlet to the reactor vessel hot pool

  4. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

    Barral, J.C.; Zaetta, A.; Johner, J.; Mathoniere, G.

    2000-01-01

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  5. Reactor noise analysis of experimental fast reactor 'JOYO'

    International Nuclear Information System (INIS)

    Ohtani, Hideji; Yamamoto, Hisashi

    1980-01-01

    As a part of dynamics tests in experimental fast reactor ''JOYO'', reactor noise tests were carried out. The reactor noise analysis techniques are effective for study of plant characteristics by determining fluctuations of process signals (neutron signal, reactor inlet temperature signals, etc.), which are able to be measured without disturbances for reactor operations. The aims of reactor noise tests were to confirm that no unstable phenomenon exists in ''JOYO'' and to gain initial data of the plant for reference of the future data. Data for the reactor noise tests treated in this paper were obtained at 50 MW power level. Fluctuations of process signals were amplified and recorded on analogue tapes. The analysis was performed using noise code (NOISA) of digital computer, with which statistical values of ASPD (auto power spectral density), CPSD (cross power spectral density), and CF (coherence function) were calculated. The primary points of the results are as follows. 1. RMS value of neutron signal at 50 MW power level is about 0.03 MW. This neutron fluctuation is not disturbing reactor operations. 2. The fluctuations of A loop reactor inlet temperatures (T sub(AI)) are larger than the fluctuations of B loop reactor inlet temperature (T sub(BI)). For this reason, the major driving force of neutron fluctuations seems to be the fluctuations of T sub(AI). 3. Core and blanket subassemblies can be divided into two halves (A and B region), with respect to the spacial motion of temperature in the reactor core. A or B region means the region in which sodium temperature fluctuations in subassembly are significantly affected by T sub(AI) or T sub(BI), respectively. This phenomenon seems to be due to the lack of mixing of A and B loop sodium in lower plenum of reactor vessel. (author)

  6. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  7. Accelerators and the Midwestern Universities Research Association in the 1950s

    International Nuclear Information System (INIS)

    Kerst, D.W.

    1989-01-01

    The birth of the cooperative research group, the Midwestern Universities Research Association (MURA) is documented in this article, following the promise high energy particles heralded by the invention of alternating-gradient focusing. Regular meetings were established and theoretical research work concentrated on orbits, with the help of the new digital computers. Space charge effects for charge distributions in the beam and the radio frequency ''knock out'' diagnostic technique were also studied. Experimental work on the Cosmotron confirmed the findings and also led to the discovery and use of the fixed-field alternating gradient (FFAG) magnet for direct-current operation which occupied much of MURA's future activities. FFAG accelerators with direct current ring magnets were invented with greatly increased beam intensities. These in turn made colliding beam machines possible. The MURA group later built a 50MeV electron model of a colliding-beam FFAG synchrotron, later used for beam stacking. (UK)

  8. Reactor water spontaneous circulation structure in reactor pressure vessel

    International Nuclear Information System (INIS)

    Takahashi, Kazumi

    1998-01-01

    The gap between the inner wall of a reactor pressure vessel of a BWR type reactor and a reactor core shroud forms a down comer in which reactor water flows downwardly. A feedwater jacket to which feedwater at low temperature is supplied is disposed at the outer circumference of the pressure vessel just below a gas/water separator. The reactor water at the outer circumferential portion just below the air/water separator is cooled by the feedwater jacket, and the feedwater after cooling is supplied to the feedwater entrance disposed below the feedwater jacket by way of a feedwater introduction line to supply the feedwater to the lower portion of the down comer. This can cool the reactor water in the down comer to increase the reactor water density in the down comer thereby forming strong downward flows and promote the recycling of the reactor water as a whole. With such procedures, the reactor water can be recycled stably only by the difference of the specific gravity of the reactor water without using an internal pump. In addition, the increase of the height of the pressure vessel can be suppressed. (I.N.)

  9. Regulated programmed lysis of recombinant Salmonella in host tissues to release protective antigens and confer biological containment.

    Science.gov (United States)

    Kong, Wei; Wanda, Soo-Young; Zhang, Xin; Bollen, Wendy; Tinge, Steven A; Roland, Kenneth L; Curtiss, Roy

    2008-07-08

    We have devised and constructed a biological containment system designed to cause programmed bacterial cell lysis with no survivors. We have validated this system, using Salmonella enterica serovar Typhimurium vaccines for antigen delivery after colonization of host lymphoid tissues. The system is composed of two parts. The first component is Salmonella typhimurium strain chi8937, with deletions of asdA and arabinose-regulated expression of murA, two genes required for peptidoglycan synthesis and additional mutations to enhance complete lysis and antigen delivery. The second component is plasmid pYA3681, which encodes arabinose-regulated murA and asdA expression and C2-regulated synthesis of antisense asdA and murA mRNA transcribed from the P22 P(R) promoter. An arabinose-regulated c2 gene is present in the chromosome. chi8937(pYA3681) exhibits arabinose-dependent growth. Upon invasion of host tissues, an arabinose-free environment, transcription of asdA, murA, and c2 ceases, and concentrations of their gene products decrease because of cell division. The drop in C2 concentration results in activation of P(R), driving synthesis of antisense mRNA to block translation of any residual asdA and murA mRNA. A highly antigenic alpha-helical domain of Streptococcus pneumoniae Rx1 PspA was cloned into pYA3681, resulting in pYA3685 to test antigen delivery. Mice orally immunized with chi8937(pYA3685) developed antibody responses to PspA and Salmonella outer membrane proteins. No viable vaccine strain cells were detected in host tissues after 21 days. This system has potential applications with other Gram-negative bacteria in which biological containment would be desirable.

  10. Studies on the dissolution of mixed oxide spent fuel from FBR

    International Nuclear Information System (INIS)

    Nemoto, Shin-ichi; Shibata, Atsuhiro; Shioura, Takao; Okamoto, Fumitoshi; Tanaka, Yasumasa

    1995-01-01

    At the Chemical Processing Facility(CPF) in the Tokai Works of the Power Reactor and Nuclear Fuel Development Corporation(PNC), since 1982 Laboratory scale hot experiments have been carried out on the development of reprocessing technology for FBR mixed oxide fuel. The spent fuel pins which have been used in out experiments were irradiated in Experimental Fast Reactor 'Joyo' Phenix (France) and DFR(UK). Burn-up of the fuel pins were 4,400-100,000 MWd/t. This paper Summarizes a dissolution study that have been performed to define the Key parameters affecting dissolution rate such as concentration of nitric acid, burn-up, and temperature. And this paper also discusses about the character of releasing 85 Kr in chopping and dissolution process, and about the amount of insoluble residue. (author)

  11. Proceedings of the 2005 symposium on nuclear data

    International Nuclear Information System (INIS)

    Tahara, Yoshihisa; Fukahori, Tokio

    2006-11-01

    The 2005 Symposium on Nuclear Data was held at Nuclear Science Research Institute in Tokai Research and Development Center, Japan Atomic Energy Agency (JAEA), on 2nd and 3rd of February 2006. Japanese Nuclear Data Committee and Nuclear Data Center, JAEA organized this symposium. In the oral sessions, presented were 16 papers on topics of nuclear data for the innovative reactor development and upgrade of current light water reactor, the past and future of nuclear data research, capability of the latest evaluated nuclear data files, and recent cross section measurements. In the poster session, presented were 21 papers concerning experiments, evaluations, benchmark tests, applications and so on. A part of those presented papers are compiled in this proceedings. The 36 of the presented papers are indexed individually. (J.P.N.)

  12. Reactor

    International Nuclear Information System (INIS)

    Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

    1979-01-01

    Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

  13. Study on efficient methods for removal and treatment of graphite blocks in a gas cooled reactor

    International Nuclear Information System (INIS)

    Fujii, S.; Shirakawa, M.; Murakami, T.

    2001-01-01

    Tokai Power Station (GCR, 166 MWe) started its commercial operation on July 1966 and ceased activities at the end of March 1998 after 32 years of operation. The decommissioning plans are being developed, to prepare for near future dismantling. In the study, the methods for removal of the graphite blocks of about 1,600 ton have been developed to carrying it out safely and in a short period of time, and the methods of treatment of graphite have also been developed. All technological items have been identified for which R and D work will be required for removal from the core and treatment for disposal. (1) In order to reduce the programme required for the dismantling of reactor internals, an efficient method for removal of the graphite blocks is necessary. For this purpose the design of a dismantling machine has been investigated which can extract several blocks at a time. The conceptual design has being developed and the model has been manufactured and tested in a mock-up facility. (2) In order to reduce disposal costs, it will be necessary to segment the graphite blocks, maximising the packing density available in the disposal containers. Some of the graphite blocks will be cut into pieces longitudinally by a remote machine. Relevant technical matters have been identified, such as graphite cutting methods, the nature of fine particles arising from the cutting operation, the treatment of fine particles for disposal, and the method of mortar filling inside the waste container. (author)

  14. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  15. FBR type reactor

    International Nuclear Information System (INIS)

    Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

    1994-01-01

    In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

  16. RB Research nuclear reactor RB reactor, Annual report for 2000

    International Nuclear Information System (INIS)

    Milosevic, M.

    2000-12-01

    Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

  17. Reactor container

    International Nuclear Information System (INIS)

    Kato, Masami; Nishio, Masahide.

    1987-01-01

    Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

  18. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  19. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  20. Nuclear public acceptance and 'imaginary and reality

    International Nuclear Information System (INIS)

    Seki, Yoshinobu

    2000-01-01

    Recently, anti-nuclear movement is going down, and couple reactor construction has been seemed to be accepted. Even Uranium production will be coming down, Plutonium, fast reactor and nuclear fusion reactor will coming in future. An unfortunate reactivity accident in a nuclear fuel factory in Tokai village has occurred by lack of the very essential nuclear technology which is not believable. This comes the reality has been included in an imaginary region in the brain. So picking up the reality from the imaginary region in brain is due to knowing the separation of the reality from the imaginary region by knowledge on the very essential nuclear technology. A man knowing the very essential nuclear technology can avoid this kind of accident. For the most people does not like to meet with the problems of atomic bomb and hi-radiation level waste. There two problems will be understood by knowing the reality point the imaginary area. It is easily understandable, if it is the essential nuclear technology. (author)

  1. Health physics in JAERI, No.39. (April 1, 1996 - March 31, 1997)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    In the annual report No.39 (fiscal 1996) are described the activities of health physics in Tokai Research Establishment, Naka Fusion Research Establishment, Takasaki Radiation Chemistry Research Establishment, Oarai Research Establishment, Kansai Research Establishment and Mutsu Establishment. In all the establishments, radiation monitoring in nuclear facilities, individual monitoring, environmental monitoring and maintenance of monitoring instruments were carried out as in the previous years. There were no occupational exposure exceeding the effective dose equivalent limit and no release of radioactive gaseous and liquid wastes beyond the release limits specified in the regulations. In the environment, no abnormal radioactivity was detected except for a slight amount of radioactive cesium in a dust sample at Oarai Research Establishment attributable to the fire and explosion (March 11, 1997) at the Asphalt Bituminization Treatment Facility at the Tokai Works of Power Reactor and Nuclear Fuel Development Corporation. Technology developments were made as in the previous years for improving the techniques and methods of monitoring of individuals, facilities and environment, and also radiation measurement instrumentation. The research works were carried out in various fields such as radiation dosimetry, environmental monitoring, and so forth. (author)

  2. Factors used for the estimation of radioactive nuclide intake through foodstuffs by inhabitants in coastal area of Ibaraki prefecture, (4)

    International Nuclear Information System (INIS)

    Sumiya, Misako; Ohmomo, Yoichiro

    1976-01-01

    The consumption of marine foods such as fish, cephalopod, crustacea, shellfish, algae and processed was surveyed on three kinds of families in Kuji town and Tokai village. The average daily intake through a year was 224 g/d/p for fisherman's families in Kuji, 131 g/d/p for native's families in Tokai and 89 g/d/p for immigrant's families from city to Tokai village, respectively. Fish accounted for about one-half of whole consumption of marine foods. Fisherman's families showed the highest consumption of all kinds of marine foods except algae through a year. Algae was consumed much by the natives in Tokai. (auth.)

  3. Computer system of radiation control at PNC Tokai Works

    International Nuclear Information System (INIS)

    Kanamori, Masashi; Ebana, Minoru; Seki, Akio

    1984-01-01

    In the Power Reactor and Nuclear Fuel Development Corporation (PNC), the operation of the fuel reprocessing plant started in January, 1981, the high level radioactive substance research facility (CPF) was completed in 1982, and the plutonium conversion technique development facility started the actual operation in September, 1983. In this situation, PNC introduced computer systems for radiation control to increase efficiency and to save labor: concretely computer systems were introduced for the continuous monitoring system in CPF in September, 1982, and for the plutonium conversion technique development facility in April, 1983. In this review, radiation control items in CPF are shown. The stationary monitors for continuous monitoring are employed for area monitors and exhaust monitors, while off-line input processing is adopted for batch measurement every week, such as iodine with an off-gas monitor. Batch data processing includes routine smear survey for working environment and shield wall survey. Other area monitors are criticality alarm systems which are designed with 2 out of 3 redundancy. In the second half of the review, the data processing system is described on each item of hardware and software, system configuration, data acquisition and demand input, processing, alarm functions, data recording and CRT display. In the review, also the system evaluation and future problems are described. (Wakatsuki, Y.)

  4. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

    This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

  5. Nuclear reactor, reactor core thereof, and device for constituting the reactor

    International Nuclear Information System (INIS)

    Takiyama, Masashi.

    1994-01-01

    A reactor core is constituted by charging coolants (light water) in a reactor pressure vessel and distributing fuel assemblies, reflecting material sealing pipes, moderator (heavy water and helium gas) sealing pipes, and gas sealing pipes therein. A fuel guide tube is surrounded by a cap and the gap therebetween is made hollow and filled with coolant steams. The cap is supported by a baffle plate. The moderator sealing pipe is disposed in a flow channel of coolants in adjacent with the cap. The position of the moderator sealing tube in the reactor core is controlled by water stream from a hydraulic pump with a guide tube extending below the baffle plate being as a guide. Then, the position of the moderator sealing tube is varied to conduct power control, burnup degree compensation, and reactor shut down. With such procedures, moderator cooling facility is no more necessary to simplify the structure. Further, heat generated from the moderator is transferred to the coolants thereby improving heat efficiency of the reactor. (I.N.)

  6. Slurry reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuerten, H; Zehner, P [BASF A.G., Ludwigshafen am Rhein (Germany, F.R.)

    1979-08-01

    Slurry reactors are designed on the basis of empirical data and model investigations. It is as yet not possible to calculate the flow behavior of such reactors. The swarm of gas bubbles and cluster formations of solid particles and their interaction in industrial reactors are not known. These effects control to a large extent the gas hold-up, the gas-liquid interface and, similarly as in bubble columns, the back-mixing of liquids and solids. These hydrodynamic problems are illustrated in slurry reactors which constructionally may be bubble columns, stirred tanks or jet loop reactors. The expected effects are predicted by means of tests with model systems modified to represent the conditions in industrial hydrogenation reactors. In his book 'Mass Transfer in Heterogeneous Catalysis' (1970) Satterfield complained of the lack of knowledge about the design of slurry reactors and hence of the impossible task of the engineer who has to design a plant according to accepted rules. There have been no fundamental changes since then. This paper presents the problems facing the engineer in designing slurry reactors, and shows new development trends.

  7. Optimal reactor strategy for commercializing fast breeder reactors

    International Nuclear Information System (INIS)

    Yamaji, Kenji; Nagano, Koji

    1988-01-01

    In this paper, a fuel cycle optimization model developed for analyzing the condition of selecting fast breeder reactors in the optimal reactor strategy is described. By dividing the period of planning, 1966-2055, into nine ten-year periods, the model was formulated as a compact linear programming model. With the model, the best mix of reactor types as well as the optimal timing of reprocessing spent fuel from LWRs to minimize the total cost were found. The results of the analysis are summarized as follows. Fast breeder reactors could be introduced in the optimal strategy when they can economically compete with LWRs with 30 year storage of spent fuel. In order that fast breeder reactors monopolize the new reactor market after the achievement of their technical availability, their capital cost should be less than 0.9 times as much as that of LWRs. When a certain amount of reprocessing commitment is assumed, the condition of employing fast breeder reactors in the optimal strategy is mitigated. In the optimal strategy, reprocessing is done just to meet plutonium demand, and the storage of spent fuel is selected to adjust the mismatch of plutonium production and utilization. The price hike of uranium ore facilitates the commercial adoption of fast breeder reactors. (Kako, I.)

  8. Computerized reactor monitor and control for nuclear reactors

    International Nuclear Information System (INIS)

    Buerger, L.

    1982-01-01

    The analysis of a computerized process control system developed by Transelektro-KFKI-Videoton (Hangary) for a twenty-year-old research reactor in Budapest and or a new one in Tajura (Libya) is given. The paper describes the computer hardware (R-10) and the implemented software (PROCESS-24K) as well as their applications at nuclear reactors. The computer program provides for man-machine communication, data acquisition and processing, trend and alarm analysis, the control of the reactor power, reactor physical calculations and additional operational functions. The reliability and the possible further development of the computerized systems which are suitable for application at reactors of different design are also discussed. (Sz.J.)

  9. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  10. Control of reactor coolant flow path during reactor decay heat removal

    Science.gov (United States)

    Hunsbedt, Anstein N.

    1988-01-01

    An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

  11. Reactor operations Brookhaven medical research reactor, Brookhaven high flux beam reactor informal monthly report

    International Nuclear Information System (INIS)

    Hauptman, H.M.; Petro, J.N.; Jacobi, O.

    1995-04-01

    This document is the April 1995 summary report on reactor operations at the Brookhaven Medical Research Reactor and the Brookhaven High Flux Beam Reactor. Ongoing experiments/irradiations in each are listed, and other significant operations functions are also noted. The HFBR surveillance testing schedule is also listed

  12. Reactor core for FBR type reactor

    International Nuclear Information System (INIS)

    Fujita, Tomoko; Watanabe, Hisao; Kasai, Shigeo; Yokoyama, Tsugio; Matsumoto, Hiroshi.

    1996-01-01

    In a gas-sealed assembly for a FBR type reactor, two or more kinds of assemblies having different eigen frequency and a structure for suppressing oscillation of liquid surface are disposed in a reactor core. Coolant introduction channels for introducing coolants from inside and outside are disposed in the inside of structural members of an upper shielding member to form a shielding member-cooling structure in the reactor core. A structure for promoting heat conduction between a sealed gas in the assembly and coolants at the inner side or the outside of the assembly is disposed in the reactor core. A material which generates heat by neutron irradiation is disposed in the assembly to heat the sealed gases positively by radiation heat from the heat generation member also upon occurrence of power elevation-type event to cause temperature expansion. Namely, the coolants flown out from or into the gas sealed-assemblies cause differential fluctuation on the liquid surface, and the change of the capacity of a gas region is also different on every gas-sealed assemblies thereby enabling to suppress fluctuation of the reactor power. Pressure loss is increased by a baffle plate or the like to lower the liquid surface of the sodium coolants or decrease the elevating speed thereof thereby suppressing fluctuation of the reactor power. (N.H.)

  13. Space-time reactor kinetics for heterogeneous reactor structure

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1969-11-15

    An attempt is made to formulate time dependent diffusion equation based on Feinberg-Galanin theory in the from analogue to the classical reactor kinetic equation. Parameters of these equations could be calculated using the existing codes for static reactor calculation based on the heterogeneous reactor theory. The obtained kinetic equation could be analogues in form to the nodal kinetic equation. Space-time distribution of neutron flux in the reactor can be obtained by solving these equations using standard methods.

  14. Nuclear Reactor RA Safety Report, Vol. 4, Reactor

    International Nuclear Information System (INIS)

    1986-11-01

    RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices [sr

  15. Feasible reactor power cutback logic development for an integral reactor

    International Nuclear Information System (INIS)

    Han, Soon-Kyoo; Lee, Chung-Chan; Choi, Suhn; Kang, Han-Ok

    2013-01-01

    Major features of integral reactors that have been developed around the world recently are simplified operating systems and passive safety systems. Even though highly simplified control system and very reliable components are utilized in the integral reactor, the possibility of major component malfunction cannot be ruled out. So, feasible reactor power cutback logic is required to cope with the malfunction of components without inducing reactor trip. Simplified reactor power cutback logic has been developed on the basis of the real component data and operational parameters of plant in this study. Due to the relatively high rod worth of the integral reactor the control rod assembly drop method which had been adapted for large nuclear power plants was not desirable for reactor power cutback of the integral reactor. Instead another method, the control rod assembly control logic of reactor regulating system controls the control rod assembly movements, was chosen as an alternative. Sensitivity analyses and feasibility evaluations were performed for the selected method by varying the control rod assembly driving speed. In the results, sensitivity study showed that the performance goal of reactor power cutback system could be achieved with the limited range of control rod assembly driving speed. (orig.)

  16. Report of the joint seminar on solid state physics, atomic and molecular physics, and materials science in the energy region of tandem accelerators

    International Nuclear Information System (INIS)

    Kazumata, Yukio

    1993-01-01

    The joint seminar on Solid State Physics, Atomic and Molecular Physics and Materials Science in the Energy Region of Tandem Acceleration was held at Tokai Research Establishment of JAERI, for two days from January 22 to 23, 1991. About 60 physicists and material scientists participated and 18 papers were presented in this seminar. The topics presented in this seminar included lattice defects in semiconductors, ion-solid collisions, atomic collisions by high energy particles, radiation effects on high T c superconducting materials and FCC metals, radiation effects on materials of space and fusion reactors, uranium compounds and superlattice. (J.P.N.)

  17. RA Reactor

    International Nuclear Information System (INIS)

    1978-02-01

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation [sr

  18. H Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

  19. Reactor container

    International Nuclear Information System (INIS)

    Naruse, Yoshihiro.

    1990-01-01

    The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

  20. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  1. Nuclear research reactors

    International Nuclear Information System (INIS)

    1985-01-01

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

  2. Strategic planning for research reactors. Guidance for reactor managers

    International Nuclear Information System (INIS)

    2001-04-01

    The purpose of this publication is to provide guidance on how to develop a strategic plan for a research reactor. The IAEA is convinced of the need for research reactors to have strategic plans and is issuing a series of publications to help owners and operators in this regard. One of these covers the applications of research reactors. That report brings together all of the current uses of research reactors and enables a reactor owner or operator to evaluate which applications might be possible with a particular facility. An analysis of research reactor capabilities is an early phase in the strategic planning process. The current document provides the rationale for a strategic plan, outlines the methodology of developing such a plan and then gives a model that may be followed. While there are many purposes for research reactor strategic plans, this report emphasizes the use of strategic planning in order to increase utilization. A number of examples are given in order to clearly illustrate this function

  3. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

  4. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

  5. Multiregion reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The study of reflected reactors can be done employing the multigroup diffusion method. The neutron conservation equations, inside the intervals, can be written by fluxes and group constants. A reflected reactor (one and two groups) for a slab geometry is studied, aplying the continuity of flux and current in the interface. At the end, the appropriated solutions for a infinite cylindrical reactor and for a spherical reactor are presented. (Author) [pt

  6. Reactor building

    International Nuclear Information System (INIS)

    Maruyama, Toru; Murata, Ritsuko.

    1996-01-01

    In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    Garabedian, G.

    1988-01-01

    A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

  8. Reactor physics challenges in GEN-IV reactor design

    Energy Technology Data Exchange (ETDEWEB)

    Driscoll, Michael K.; Hejzlar, Pavel [Massachusetts Institute of Technology, MA (United States)

    2005-02-15

    An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources.

  9. Reactor physics challenges in GEN-IV reactor design

    International Nuclear Information System (INIS)

    Driscoll, Michael K.; Hejzlar, Pavel

    2005-01-01

    An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources

  10. Reactor Vessel Surveillance Program for Advanced Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

    2008-10-15

    This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

  11. Current status of irradiation facilities in JRR-3 and JRR-4

    International Nuclear Information System (INIS)

    Hori, Naohiko; Wada, Shigeru; Sasajima, Fumio; Kusunoki, Tsuyoshi

    2006-01-01

    The Department of Research Reactor has operated two research reactors, JRR-3 and JRR-4. These reactors were constructed in the Tokai Research Establishment. Many researchers and engineers use these joint-use facilities. JRR-3 is a light water moderated and cooled, pool type research reactor using low-enriched silicide fuel. JRR-3's maximum thermal power is 20MW. JRR-3 has nine vertical irradiation holes for RI production, nuclear fuels and materials irradiation at reactor core area. JRR-3 has many kinds of irradiation holes in a heavy water tank around the reactor core. These are two hydraulic rabbit irradiation facilities, two pneumatic rabbit irradiation facilities, one activation analysis irradiation facilities, one uniform irradiation facility, one rotating irradiation facility and one capsule irradiation facility. JRR-3 has nine horizontal experimental holes, that are used by many kinds of neutron beam experimental facilities using these holes. JRR-4 is a light water moderated and cooled, swimming pool type research reactor using low-enriched silicide fuel. JRR-4's maximum thermal power is 3.5MW. JRR-4 has five vertical irradiation tubes at reactor core area, three capsule irradiation facilities, one hydraulic rabbit irradiation facility, and one pneumatic rabbit irradiation facility. JRR-4 has a neutron beam hole, and it has used neutron beam experiments, irradiations for activation analysis and medical neutron irradiations. (author)

  12. The nuclear reactor strategy between fast breeder reactors and advanced pressurized water reactors

    International Nuclear Information System (INIS)

    Seifritz, W.

    1983-01-01

    A nuclear reactor strategy between fast breeder reactors (FBRs) and advanced pressurized water reactors (APWRs) is being studied. The principal idea of this strategy is that the discharged plutonium from light water reactors (LWRs) provides the inventories of the FBRs and the high-converter APWRs, whereby the LWRs are installed according to the derivative of a logistical S curve. Special emphasis is given to the dynamics of reaching an asymptotic symbiosis between FBRs and APWRs. The main conclusion is that if a symbiotic APWR-FBR family with an asymptotic total power level in the terawatt range is to exist in about half a century from now, we need a large number of FBRs already in an early phase

  13. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

    Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

  14. Tokamak reactor studies

    International Nuclear Information System (INIS)

    Baker, C.C.

    1981-01-01

    This paper presents an overview of tokamak reactor studies with particular attention to commercial reactor concepts developed within the last three years. Emphasis is placed on DT fueled reactors for electricity production. A brief history of tokamak reactor studies is presented. The STARFIRE, NUWMAK, and HFCTR studies are highlighted. Recent developments that have increased the commercial attractiveness of tokamak reactor designs are discussed. These developments include smaller plant sizes, higher first wall loadings, improved maintenance concepts, steady-state operation, non-divertor particle control, and improved reactor safety features

  15. Computerized reactor monitor and control for research reactors

    International Nuclear Information System (INIS)

    Buerger, L.; Vegh, E.

    1981-09-01

    The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

  16. Calculation of low-energy reactor neutrino spectra reactor for reactor neutrino experiments

    Energy Technology Data Exchange (ETDEWEB)

    Riyana, Eka Sapta; Suda, Shoya; Ishibashi, Kenji; Matsuura, Hideaki [Dept. of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Kyushu (Japan); Katakura, Junichi [Dept. of Nuclear System Safety Engineering, Nagaoka University of Technology, Nagaoka (Japan)

    2016-06-15

    Nuclear reactors produce a great number of antielectron neutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may take part in special weak interactions. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectrum from a typical pressurized water reactor (PWR) reactor core. To calculate neutrino spectra, we need information about all generated nuclides that emit neutrinos. They are mainly fission fragments, reaction products and trans-uranium nuclides that undergo negative beta decay. Information in relation to trans-uranium nuclide compositions and its evolution in time (burn-up process) were provided by a reactor code MVP-BURN. We used typical PWR parameter input for MVP-BURN code and assumed the reactor to be operated continuously for 1 year (12 months) in a steady thermal power (3.4 GWth). The PWR has three fuel compositions of 2.0, 3.5 and 4.1 wt% {sup 235}U contents. For preliminary calculation we adopted a standard burn-up chain model provided by MVP-BURN. The chain model treated 21 heavy nuclides and 50 fission products. The MVB-BURN code utilized JENDL 3.3 as nuclear data library. We confirm that the antielectron neutrino flux in the low energy region increases with burn-up of nuclear fuel. The antielectron-neutrino spectrum in low energy region is influenced by beta emitter nuclides with low Q value in beta decay (e.g. {sup 241}Pu) which is influenced by burp-up level: Low energy antielectron-neutrino spectra or emission rates increase when beta emitters with low Q value in beta decay accumulate. Our result shows the flux of low energy reactor neutrinos increases with burn-up of nuclear fuel.

  17. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

    An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

  18. Reactor. Mind picture of the future Jules-Horowitz Reactor (RHJ)

    International Nuclear Information System (INIS)

    Eustache, S.

    1999-01-01

    This paper gives information about the future research reactor, named Reactor Jules-Horowitz (RJH). This irradiation reactor will be placed at industrialists disposal, for research concerning the competitiveness and the safety french electro-nuclear park. Principles and innovations are detailed. This reactor will respect the ALARA principle (as low as reasonably achievable). (A.L.B.)

  19. The analysis for inventory of experimental reactor high temperature gas reactor type

    International Nuclear Information System (INIS)

    Sri Kuntjoro; Pande Made Udiyani

    2016-01-01

    Relating to the plan of the National Nuclear Energy Agency (BATAN) to operate an experimental reactor of High Temperature Gas Reactors type (RGTT), it is necessary to reactor safety analysis, especially with regard to environmental issues. Analysis of the distribution of radionuclides from the reactor into the environment in normal or abnormal operating conditions starting with the estimated reactor inventory based on the type, power, and operation of the reactor. The purpose of research is to analyze inventory terrace for Experimental Power Reactor design (RDE) high temperature gas reactor type power 10 MWt, 20 MWt and 30 MWt. Analyses were performed using ORIGEN2 computer code with high temperatures cross-section library. Calculation begins with making modifications to some parameter of cross-section library based on the core average temperature of 570 °C and continued with calculations of reactor inventory due to RDE 10 MWt reactor power. The main parameters of the reactor 10 MWt RDE used in the calculation of the main parameters of the reactor similar to the HTR-10 reactor. After the reactor inventory 10 MWt RDE obtained, a comparison with the results of previous researchers. Based upon the suitability of the results, it make the design for the reactor RDE 20MWEt and 30 MWt to obtain the main parameters of the reactor in the form of the amount of fuel in the pebble bed reactor core, height and diameter of the terrace. Based on the main parameter or reactor obtained perform of calculation to get reactor inventory for RDE 20 MWT and 30 MWT with the same methods as the method of the RDE 10 MWt calculation. The results obtained are the largest inventory of reactor RDE 10 MWt, 20 MWt and 30 MWt sequentially are to Kr group are about 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq, for group I are 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq and for groups Cs are 2,20E+16 Bq, 2,40E+16 Bq, 2,60E+16 Bq. Reactor inventory will then be used to calculate the reactor source term and it

  20. FBR type reactors

    International Nuclear Information System (INIS)

    Suzuoki, Akira; Yamakawa, Masanori.

    1985-01-01

    Purpose: To enable safety and reliable after-heat removal from a reactor core. Constitution: During ordinary operation of a FBR type reactor, sodium coolants heated to a high temperature in a reactor core are exhausted therefrom, collide against the reactor core upper mechanisms to radially change the flowing direction and then enter between each of the guide vanes. In the case if a main recycling pump is failed and stopped during reactor operation and the recycling force is eliminated, the swirling stream of sodium that has been resulted by the flow guide mechanism during normal reactor operation is continuously maintained within a plenum at a high temperature. Accordingly, the sodium recycling force in the coolant flow channels within the reactor vessel can surely be maintained for a long period of time due to the centrifugal force of the sodium swirling stream. In this way, since the reactor core recycling flow rate can be secured even after the stopping of the main recycling pump, after-heat from the reactor core can safely and surely be removed. (Seki, T.)

  1. FBR type reactor

    International Nuclear Information System (INIS)

    Hayase, Tamotsu.

    1991-01-01

    The present invention concerns an FBR type reactor in which transuranium elements are eliminated by nuclear conversion. There are loaded reactor core fuels being charged with mixed oxides of plutonium and uranium, and blanket fuels mainly comprising depleted uranium. Further, liquid sodium is used as coolants. As transuranium elements, isotope elements of neptunium, americium and curium contained in wastes taken out from light water reactors or the composition thereof are used. The reactor core comprises a region with a greater mixing ratio and a region with a less mixing ratio of the transuranium elements. The mixing ratio of the transuranium elements is made greater for the fuels in the reactor core region at the boundary with the blanket of great neutron leakage. With such a constitution, since the positive reactivity value at the reactor core central portion is small in the Na void reactivity distribution in the reactor core, the positive reactivity is small upon Na boiling in the reactor core central region upon occurrence of imaginable accident, to attain reactor safety. (I.N.)

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

    A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

  3. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  4. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-07-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  5. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

  6. Thai research reactor

    International Nuclear Information System (INIS)

    Aramrattana, M.

    1987-01-01

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  7. Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Poore, III, Willis P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Moe, Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-03-01

    This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

  8. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

    The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

  9. Reactor System Design

    International Nuclear Information System (INIS)

    Chi, S. K.; Kim, G. K.; Yeo, J. W.

    2006-08-01

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  10. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1983-01-01

    Purpose : To flatten the radial power distribution in the reactor core thereby improve the thermal performance of the reactor core by making the moderator-fuel ratio of fuel assemblies different depending on their position in the reactor core. Constitution : The volume of fuels disposed in the peripheral area of the reactor core is decreased by the increase of the volume of moderators in fuel assemblies disposed in the peripheral area of the reactor core to thereby make the moderator-fuel volume greater in the peripheral area than that in the central area. The moderator-fuel ratio adjustment is attained by making the number of water rods greater, decreasing the diameter of fuel pellets or decreasing the number of fuel pins in fuel assemblies disposed at the peripheral area of the reactor core as compared with fuel assemblies disposed at the central area of the reactor core. In this way, the infinite multiplication factors of fuels can be increased to thereby improve the reactor core performance. (Aizawa, K.)

  11. Prevention device for rapid reactor core shutdown in BWR type reactors

    International Nuclear Information System (INIS)

    Koshi, Yuji; Karatsu, Hiroyuki.

    1986-01-01

    Purpose: To surely prevent rapid shutdown of a nuclear reactor upon partial load interruption due to rapid increase in the system frequency. Constitution: If a partial load interruption greater than the sum of the turbine by-pass valve capacity and the load setting bias portion is applied in a BWR type power plant, the amount of main steams issued from the reactor is decreased, the thermal input/output balance of the reactor is lost, the reactor pressure is increased, the void is collapsed, the neutron fluxes are increased and the reactor power rises to generate rapid reactor shutdown. In view of the above, the turbine speed signal is compared with a speed setting value in a recycling flowrate control device and the recycling pump is controlled to decrease the recycling flowrate in order to compensate the increase in the neutron fluxes accompanying the reactor power up. In this way, transient changes in the reactor core pressure and the neutron fluxes are kept within a setting point for the rapid reactor shutdown operation thereby enabling to continue the plant operation. (Horiuchi, T.)

  12. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

    1994-01-01

    In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

  13. High-temperature and breeder reactors - economic nuclear reactors of the future

    International Nuclear Information System (INIS)

    Djalilzadeh, A.M.

    1977-01-01

    The thesis begins with a review of the theory of nuclear fission and sections on the basic technology of nuclear reactors and the development of the first generation of gas-cooled reactors applied to electricity generation. It then deals in some detail with currently available and suggested types of high temperature reactor and with some related subsidiary issues such as the coupling of different reactor systems and various schemes for combining nuclear reactors with chemical processes (hydrogenation, hydrogen production, etc.), going on to discuss breeder reactors and their application. Further sections deal with questions of cost, comparison of nuclear with coal- and oil-fired stations, system analysis of reactor systems and the effect of nuclear generation on electricity supply. (C.J.O.G.)

  14. Heterogeneous reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

  15. Nuclear reactor neutron shielding

    Science.gov (United States)

    Speaker, Daniel P; Neeley, Gary W; Inman, James B

    2017-09-12

    A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

  16. Fast breeder reactors

    International Nuclear Information System (INIS)

    Heinzel, V.

    1975-01-01

    The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

  17. Reactor container

    International Nuclear Information System (INIS)

    Shibata, Satoru; Kawashima, Hiroaki

    1984-01-01

    Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

  18. Reactor technology: power conversion systems and reactor operation and maintenance

    International Nuclear Information System (INIS)

    Powell, J.R.

    1977-01-01

    The use of advanced fuels permits the use of coolants (organic, high pressure helium) that result in power conversion systems with good thermal efficiency and relatively low cost. Water coolant would significantly reduce thermal efficiency, while lithium and salt coolants, which have been proposed for DT reactors, will have comparable power conversion efficiencies, but will probably be significantly more expensive. Helium cooled blankets with direct gas turbine power conversion cycles can also be used with DT reactors, but activation problems will be more severe, and the portion of blanket power in the metallic structure will probably not be available for the direct cycle, because of temperature limitations. A very important potential advantage of advanced fuel reactors over DT fusion reactors is the possibility of easier blanket maintenance and reduced down time for replacement. If unexpected leaks occur, in most cases the leaking circuit can be shut off and a redundant cooling curcuit will take over the thermal load. With the D-He 3 reactor, it appears practical to do this while the reactor is operating, as long as the leak is small enough not to shut down the reactor. Redundancy for Cat-D reactors has not been explored in detail, but appears feasible in principle. The idea of mobile units operating in the reactor chamber for service and maintenance of radioactive elements is explored

  19. Fusion-fission hybrid reactors

    International Nuclear Information System (INIS)

    Greenspan, E.

    1984-01-01

    This chapter discusses the range of characteristics attainable from hybrid reactor blankets; blanket design considerations; hybrid reactor designs; alternative fuel hybrid reactors; multi-purpose hybrid reactors; and hybrid reactors and the energy economy. Hybrid reactors are driven by a fusion neutron source and include fertile and/or fissile material. The fusion component provides a copious source of fusion neutrons which interact with a subcritical fission component located adjacent to the plasma or pellet chamber. Fissile fuel and/or energy are the main products of hybrid reactors. Topics include high F/M blankets, the fissile (and tritium) breeding ratio, effects of composition on blanket properties, geometrical considerations, power density and first wall loading, variations of blanket properties with irradiation, thermal-hydraulic and mechanical design considerations, safety considerations, tokamak hybrid reactors, tandem-mirror hybrid reactors, inertial confinement hybrid reactors, fusion neutron sources, fissile-fuel and energy production ability, simultaneous production of combustible and fissile fuels, fusion reactors for waste transmutation and fissile breeding, nuclear pumped laser hybrid reactors, Hybrid Fuel Factories (HFFs), and scenarios for hybrid contribution. The appendix offers hybrid reactor fundamentals. Numerous references are provided

  20. Reactor protection systems for the Replacement Research Reactor, ANSTO

    International Nuclear Information System (INIS)

    Morris, C.R.

    2003-01-01

    The 20-MW Replacement Research Reactor Project which is currently under construction at ANSTO will have a combination of a state of the art triplicated computer based reactor protection system, and a fully independent, and diverse, triplicated analogue reactor protection system, that has been in use in the nuclear industry, for many decades. The First Reactor Protection System (FRPS) consists of a Triconex triplicated modular redundant system that has recently been approved by the USNRC for use in the USA?s power reactor program. The Second Reactor Protection System is a hardwired analogue system supplied by Foxboro, the Spec 200 system, which is also Class1E qualified. The FRPS is used to drop the control rods when its safety parameter setpoints have been reached. The SRPS is used to drain the reflector tank and since this operation would result in a reactor poison out due to the time it would take to refill the tank the FRPS trip setpoints are more limiting. The FRPS and SRPS have limited hardwired indications on the control panels in the main control room (MCR) and emergency control centre (ECC), however all FRPS and SRPS parameters are capable of being displayed on the reactor control and monitoring system (RCMS) video display units. The RCMS is a Foxboro Series I/A control system which is used for plant control and monitoring and as a protection system for the cold neutron source. This paper will provide technical information on both systems, their trip logics, their interconnections with each other, and their integration into the reactor control and monitoring system and control panels. (author)

  1. Reactor container

    International Nuclear Information System (INIS)

    Fukazawa, Masanori.

    1991-01-01

    A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

  2. Annual report of nuclear technology and education center. April 1, 2002 - March 31, 2003

    International Nuclear Information System (INIS)

    2003-10-01

    This report summarizes the activities of Nuclear Technology and Education Center (NuTEC) in Japan Atomic Energy Research Institute in FY 2002. It includes the domestic educational activities in Tokyo Education Center in Komagome Tokyo for RI and radiation engineers and Tokai Education Center in Tokai for nuclear engineers, and the international training activities for Asia-Pacific region which were planned and administrated by International Technology Transfer Division. The new course so called 'Introductory Course for the Use and the Experiment of Neutron' was started with good appreciation by the participants. All scheduled course plan in Tokyo Education Center and Tokai Education Center was accomplished and the total number of the trainee of both Center was 1,297. The courses for RI and radiation engineers implemented in Tokyo Education Center were closed in this FY and transferred to Tokai Establishment in next FY where the course will be integrated with the ones at Tokai Education Center. The land of Tokyo Education Center will be returned to land-owner by the end of FY 2003 after dismantlement of the facilities. The equipments and instruments used in Tokyo Education Center were transferred to Tokai Education Center after finishing all courses in Tokyo in this FY. The improvement and re-arrangement of the facilities in Tokyo Education Center were proceeded to prepare the courses from Tokyo Education Center. (author)

  3. A multi-purpose reactor

    International Nuclear Information System (INIS)

    Changwen Ma

    2000-01-01

    An integrated natural circulation self pressurized reactor can be used for sea water desalination, electrogeneration, ship propulsion and district or process heating. The reactor can be used for ship propulsion because it has following advantages: it is a integrated reactor. Whole primary loop is included in a size limited pressure vessel. For a 200 MW reactor the diameter of the pressure vessel is about 5 m. It is convenient to arranged on a ship. Hydraulic driving facility of control rods is used on the reactor. It notably decreases the height of the reactor. For ship propulsion, smaller diameter and smaller height are important. Besides these, the operation reliability of the reactor is high enough, because there is no rotational machine (for example, circulating pump) in safety systems. Reactor systems are simple. There are no emergency water injection system and boron concentration regulating system. These features for ship propulsion reactor are valuable. Design of the reactor is based on existing demonstration district heating reactor design. The mechanic design principles are the same. But boiling is introduced in the reactor core. Several variants to use the reactor as a movable seawater desalination plant are presented in the paper. When the sea water desalination plant is working to produce fresh water, the reactor can supply electricity at the same time to the local electricity network. Some analyses for comprehensive application of the reactor have been done. Main features and parameters of the small (Thermopower 200 MW) reactor are given in the paper. (author)

  4. TU Electric reactor physics model verification: Power reactor benchmark

    International Nuclear Information System (INIS)

    Willingham, C.E.; Killgore, M.R.

    1988-01-01

    Power reactor benchmark calculations using the advanced code package CASMO-3/SIMULATE-3 have been performed for six cycles of Prairie Island Unit 1. The reload fuel designs for the selected cycles included gadolinia as a burnable absorber, natural uranium axial blankets and increased water-to-fuel ratio. The calculated results for both startup reactor physics tests (boron endpoints, control rod worths, and isothermal temperature coefficients) and full power depletion results were compared to measured plant data. These comparisons show that the TU Electric reactor physics models accurately predict important measured parameters for power reactors

  5. Supercritical Water Reactors

    International Nuclear Information System (INIS)

    Bouchter, J.C.; Dufour, P.; Guidez, J.; Latge, C.; Renault, C.; Rimpault, G.

    2014-01-01

    The supercritical water reactor (SCWR) is one of the 6 concepts selected for the 4. generation of nuclear reactors. SCWR is a new concept, it is an attempt to optimize boiling water reactors by using the main advantages of supercritical water: only liquid phase and a high calorific capacity. The SCWR requires very high temperatures (over 375 C degrees) and very high pressures (over 22.1 MPa) to operate which allows a high conversion yield (44% instead of 33% for a PWR). Low volumes of coolant are necessary which makes the neutron spectrum shift towards higher energies and it is then possible to consider fast reactors operating with supercritical water. The main drawbacks of supercritical water is the necessity to use very high pressures which has important constraints on the reactor design, its physical properties (density, calorific capacity) that vary strongly with temperatures and pressures and its very high corrosiveness. The feasibility of the concept is not yet assured in terms of adequate materials that resist to corrosion, reactor stability, reactor safety, and reactor behaviour in accidental situations. (A.C.)

  6. Tank type reactor

    International Nuclear Information System (INIS)

    Otsuka, Fumio.

    1989-01-01

    The present invention concerns a tank type reactor capable of securing reactor core integrity by preventing incorporation of gases to an intermediate heat exchanger, thgereby improving the reliability. In a conventional tank type reactor, since vortex flows are easily caused near the inlet of an intermediate heat exchanger, there is a fear that cover gases are involved into the coolant main streams to induce fetal accidents. In the present invention, a reactor core is suspended by way of a suspending body to the inside of a reactor vessel and an intermediate heat exchanger and a pump are disposed between the suspending body and the reactor vessel, in which a vortex current preventive plate is attached at the outside near the coolant inlet on the primary circuit of the intermediate heat exchanger. In this way vortex or turbulence near the inlet of the intermediate heata exchanger or near the surface of coolants can be prevented. Accordingly, the cover gases are no more involved, to insure the reactor core integrity and obtain a tank type nuclear reactor of high reliability. (I.S.)

  7. New about research reactors

    International Nuclear Information System (INIS)

    Egorenkov, P.M.

    2001-01-01

    The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

  8. Evaluation of Pressure Changes in HANARO Reactor Hall after a Reactor Shutdown

    International Nuclear Information System (INIS)

    Han, Geeyang; Han, Jaesam; Ahn, Gukhoon; Jung, Hoansung

    2013-01-01

    The major objective of this work is intended to evaluate the characteristics of the thermal behavior regarding how the decay heat will be affected by the reactor hall pressure change and the increase of pool water temperature induced in the primary coolant after a reactor shutdown. The particular reactor pool water temperature at the surface where it is evaporated owing to the decay heat resulting in the local heat transfer rate is related to the pressure change response in the reactor hall associated with the primary cooling system because of the reduction of the heat exchanger to remove the heat. The increase in the pool water temperature is proportional to the heat transfer rate in the reactor pool. Consequently, any limit on the reactor pool water temperature imposes a corresponding limit on the reactor hall pressure. At HANARO, the decay heat after a reactor shutdown is mainly removed by the natural circulation cooling in the reactor pool. This paper is written for the safety feature of the pressure change related leakage rate from the reactor hall. The calculation results show that the increase of pressure in the reactor hall will not cause any serious problems to the safety limits although the reactor hall pressure is slightly increased. Therefore, it was concluded that the pool water temperature increase is not so rapid as to cause the pressure to vary significantly in the reactor hall. Furthermore, the mathematical model developed in this work can be a useful analytical tool for scoping and parametric studies in the area of thermal transient analysis, with its proper representation of the interaction between the temperature and pressure in the reactor hall

  9. Design guide for Category III reactors: pool type reactors

    International Nuclear Information System (INIS)

    Brynda, W.J.; Lobner, P.R.; Powell, R.W.; Straker, E.A.

    1978-11-01

    The Department of Energy (DOE) in the ERDA Manual requires that all DOE-owned reactors be sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate consideration to health and safety factors. Specific guidance pertinent to the safety of DOE-owned reactors is found in Chapter 0540 of the ERDA Manual. The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC). This Design Guide deals principally with the design and functional requirement of Category III reactor structures, components, and systems

  10. The computerized reactor period measurement system for China fast burst reactor-II

    International Nuclear Information System (INIS)

    Zhao Wuwen; Jiang Zhiguo

    1996-01-01

    The article simply introduces the hardware, principle, and software of the computerized reactor period measurement system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between fission yield and pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computerized measurement system makes the reactor period measurement into automatical and intelligent and also improves the speed and precision of period data on-line process

  11. Computer measurement system of reactor period for China fast burst reactor-II

    International Nuclear Information System (INIS)

    Zhao Wuwen; Jiang Zhiguo

    1997-01-01

    The author simply introduces the hardware, principle, and software of the reactor period computer measure system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between Fission yield and Pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computer measure system makes the reactor period measurement into automation and intellectualization and also improves the speed and precision of period data process on-line

  12. Reactor safety method

    International Nuclear Information System (INIS)

    Vachon, L.J.

    1980-01-01

    This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature

  13. Small propulsion reactor design based on particle bed reactor concept

    International Nuclear Information System (INIS)

    Ludewig, H.; Lazareth, O.; Mughabghab, S.; Perkins, K.; Powell, J.R.

    1989-01-01

    In this paper Particle Bed Reactor (PBR) designs are discussed which use 233 U and /sup 242m/Am as fissile materials. A constant total power of 100MW is assumed for all reactors in this study. Three broad aspects of these reactors is discussed. First, possible reactor designs are developed, second physics calculations are outlined and discussed and third mass estimates of the various candidates reactors are made. It is concluded that reactors with a specific mass of 1 kg/MW can be envisioned of 233 U is used and approximately a quarter of this value can be achieved if /sup 242m/Am is used. If this power level is increased by increasing the power density lower specific mass values are achievable. The limit will be determined by uncertainties in the thermal-hydraulic analysis. 5 refs., 5 figs., 6 tabs

  14. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    Baeten, Peter

    2006-01-01

    This course gives an introduction to Nuclear Reactor Physics. The first chapter explains the most important parameters and concepts in nuclear reactor physics such as fission, cross sections and the effective multiplication factor. Further on, in the second chapter, the flux distributions in a stationary reactor are derived from the diffusion equation. Reactor kinetics, reactor control and reactor dynamics (feedback effects) are described in the following three chapters. The course concludes with a short description of the different types of existing and future reactors. (author)

  15. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    2010-03-01

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  16. Inspection and repair in JRR-3 after the 2011 off the Pacific coast of Tohoku Earthquake

    International Nuclear Information System (INIS)

    Hosoya, Toshiaki; Nagadomi, Hideki; Torii, Yoshiya

    2014-01-01

    In the 2011 off the Pacific Coast of Tohoku Earthquake, seismic intensity of 6 lower was observed at Tokai Village. However, the maximum acceleration of ground motion that was observed in the JRR-3 reactor facilities had exceeded the maximum response acceleration at the time of design. Therefore, to confirm whether the predetermined performance of the facility equipment of the reactor facilities had been maintained after the earthquake, soundness confirmation inspection was carried out. In the inspection, the soundness of equipment and facilities was evaluated from the results of the equipment inspection and seismic impact assessment, and the repair work was applied when necessary. As a result, it was confirmed that after the earthquake, the equipment of JRR-3 reactor facilities maintained the predetermined performance, and was possible to resume operation. The following item are reported here: (1) overview of JRR-3, (2) conditions of JRR-3 reactor facilities while earthquake occurrence, (3) basic principle for soundness evaluation of facilities, (4) soundness confirmation of buildings and structures, (5) contents of repair, and (6) soundness verification and comprehensive evaluation of each facility and equipment. (A.O.)

  17. Guide to power reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

    The IAEA's major first scientific publication is the Directory of Power Reactors now in operation or under construction in various parts of the world. The purpose of the directory is to present important details of various power projects in such a way as to provide a source of easy reference for anyone interested in the development of the peaceful uses of atomic energy, either at the technical or management level. Six pages have been devoted to each reactor the first of which contains general information, reactor physics data and information about the core. The second and third contain sketches of the fuel element or of the fuel element assembly, and of the horizontal and vertical sections of the reactor. On the fourth page information is grouped under the following heads: fuel element, core heat transfer, control, reactor vessel and over-all dimensions, and fluid flow. The fifth page shows a simplified flow diagram, while the sixth provides information on reflector and shielding, containment and turbo generator. Some information has also been given, when available, on cost estimates and operating staff requirements. Remarks and a bibliography constitute the last part of the description of each reactor. Reactor projects included in this directory are pressurized light water cooled power reactors. Boiling light water cooled power reactors, heavy water cooled power reactors, gas cooled power reactors, organic cooled power reactors liquid metal cooled power reactors and liquid metal cooled power reactors

  18. Analysis of dynamic stability and safety of reactor system by reactor simulator

    International Nuclear Information System (INIS)

    Raisic, N.

    1963-11-01

    In order to enable qualitative analysis of dynamic properties of reactors RA and RB, mathematical models of these reactors were formulated and adapted for solution on analog computer. This report contains basic assessments for creating the model and complete equations for each reactor. Model was used to analyse three possible accidents at the RA reactor and possible hypothetical accidents at the RB reactor

  19. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

  20. Sodium-cooled nuclear reactor

    International Nuclear Information System (INIS)

    Hammers, H.W.

    1982-01-01

    The invention concerns a sodium-cooled nuclear reactor, whose reactor tank contains the primary circuit, shielding surrounding the reactor core and a primary/secondary heat exchanger, particularly a fast breeder reactor on the module principle. In order to achieve this module principle it is proposed to have electromagnetic circulating pumps outside the reactor tank, where the heat exchanger is accomodated in an annular case above the pumps. This case has several openings at the top end to the space above the reactor core, some smaller openings in the middle to the same space and is connected at the bottom to an annular space between the tank wall and the reactor core. As a favoured variant, it is proposed that the annular electromagnetic pumps should be arranged concentrically to the reactor tank, where there is an annual duct on the inside of the reactor tank. In this way the sodium-cooled nuclear reactor is made suitable as a module with a large number of such elements. (orig.) [de

  1. Atomic reactor thermal engineering

    International Nuclear Information System (INIS)

    Kim, Gwang Ryong

    1983-02-01

    This book starts the introduction of atomic reactor thermal engineering including atomic reaction, chemical reaction, nuclear reaction neutron energy and soon. It explains heat transfer, heat production in the atomic reactor, heat transfer of fuel element in atomic reactor, heat transfer and flow of cooler, thermal design of atomic reactor, design of thermodynamics of atomic reactor and various. This deals with the basic knowledge of thermal engineering for atomic reactor.

  2. Argentinean integrated small reactor design and scale economy analysis of integrated reactor

    International Nuclear Information System (INIS)

    Florido, P. C.; Bergallo, J. E.; Ishida, M. V.

    2000-01-01

    This paper describes the design of CAREM, which is Argentinean integrated small reactor project and the scale economy analysis results of integrated reactor. CAREM project consists on the development, design and construction of a small nuclear power plant. CAREM is an advanced reactor conceived with new generation design solutions and standing on the large experience accumulated in the safe operation of Light Water Reactors. The CAREM is an indirect cycle reactor with some distinctive and characteristic features that greatly simplify the reactor and also contribute to a highly level of safety: integrated primary cooling system, self pressurized, primary cooling by natural circulation and safety system relying on passive features. For a fully doupled economic evaluation of integrated reactors done by IREP (Integrated Reactor Evaluation Program) code transferred to IAEA, CAREM have been used as a reference point. The results shows that integrated reactors become competitive with power larger than 200MWe with Argentinean cheapest electricity option. Due to reactor pressure vessel construction limit, low pressure drop steam generator are used to reach power output of 200MWe for natural circulation. For forced circulation, 300MWe can be achieved. (author)

  3. Fast reactors

    International Nuclear Information System (INIS)

    Vasile, A.

    2001-01-01

    Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

  4. Reactor power measuring device

    International Nuclear Information System (INIS)

    Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

    1993-01-01

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  5. Reactor container

    International Nuclear Information System (INIS)

    Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

    1997-01-01

    In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

  6. Study on Reactor Performance of Online Power Monitoring in PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

    Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

    2014-01-01

    The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on reactor performance of online power monitoring based on various parameter of reactor such as log power, linear power, period, Fuel and coolant temperature and reactivity parameter with using neutronic and other instrumentation system of reactor. Methodology of online power estimation and monitoring is to evaluate and analysis of reactor power which is important of reactor safety and control. Neutronic instrumentation system will use to estimate power measurement, differential of log and linear power and period during reactor operation .This study also focus on noise fluctuation from fission chamber during reactor operation .This work will present result of online power monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that optimization of online power monitoring will improved the reactor control and safety parameter of reactor during operation. (author)

  7. Nuclear power reactors: reactor safety and military and civil defence

    International Nuclear Information System (INIS)

    Hvinden, T.

    1976-01-01

    The formation of fission products and plutonium in reactors is briefly described, followed by a short general discussion of reactor safety. The interaction of reactor safety and radioactive release considerations with military and civil defence is thereafter discussed. Reactors and other nuclear plants are factors which must be taken into account in the defence of the district around the site, and as potential targets of both conventional and guerilla attacks and sabotage, requiring special defence. The radiological hazards arising from serious damage to a power reactor by conventional weapons are briefly discussed, and the benefits of underground siting evaluated. Finally the author discusses the significance of the IAEA safeguards work as a preventive factor. (JIW)

  8. LWR-plants. Their evolutionary progress in the last half-century. (4) The start of the nuclear power generation in Japan

    International Nuclear Information System (INIS)

    Ishikawa, Hiroshi

    2008-01-01

    Evolutionary progress of the LWR plants in the last half-century was reviewed in series. The start of the nuclear power generation in Japan was reviewed in this article. The Japan Atomic Energy Research Institute (JAERI) promoted nuclear power research and development and introduced the Japan Power Demonstration Reactor (JPDR)-a 12.5 MWe natural circulation BWR, which began operation in 1965. In 1969 its power uprate modifications to a forced circulation BWR (JPDR-II) began and attained operation in 1972. During 50% power test, primary coolant leakage was observed at reactor core spray pipes in 1972. In 1975 the operation resumed and faults observed at condenser tubes in 1976. Primary coolant leakage from in-core flux monitor guide tubes at the bottom of reactor pressure vessel in 1979 led to its permanent shutdown. The nuclear ship Mutsu was put into service in 1970 and during rising power test radiation leakage due to fast neutron streaming was observed in 1974. After modifications of shielding experimental voyage was made in 1991. The first commercial nuclear power reactor, Tokai-1-a 166 MWe gas-cooled (Magnox) reactor, began operation in 1966 and continued until 1998. The LWR plants became the mainstay in Japan. (T. Tanaka)

  9. Nuclear technologies

    International Nuclear Information System (INIS)

    Toyama, Makoto; Hamasaki, Manabu; Kobayashi, Masahiko; Hoshide, Akihiko; Katayama, Kimio; Nozawa, H.; Karigome, Satoshi

    2010-01-01

    In recent days, energy security is becoming a major global concern and it has been recognized that a major reduction in greenhouse-gas emissions is required to combat climate change. Considerable expansion and new introduction of nuclear power generation are currently being planned and considered for the further in various parts of the world. Nuclear technologies of the latest 10 years in Japan were reviewed with their characteristics, advancement and future perspective. Steady efforts have been made to construct new nuclear power stations with computer-aided engineering system and modular and prefabricated structures, extend the interval of periodic inspections under the new inspection system that should improve both safety and reliability, implement advanced measures against aging and develop the next-generation light water reactors including a medium small reactor. Export of nuclear power plants has been promoted with international business alliance or cooperation. Activities to close nuclear fuel cycle to ensure sustainable nuclear energy utilization have been promoted. Decommissioning technologies for Tokai power station have been developed and accumulated know-how will be utilized in light water reactors. (T. Tanaka)

  10. Current status of JRR-3. After the 3.11 earthquake

    International Nuclear Information System (INIS)

    Arai, Masaji; Murayama, Yoji; Wada, Shigeru

    2012-01-01

    JRR-3 at Tokai site of JAEA was in its regular maintenance period, when the Great East Japan Earthquake was taken place on 11th March 2011. The reactor building with their solid foundations and the equipment important to safety survived the earthquake without serious damage and no radioactive leakage has been occurred. Recovery work is planned to be completed by the end of this March. At the same time, check and test of the integrity of all components and seismic assessment to show resistance with the 3.11 earthquake have been carried out. JRR-3 will restart its operation after completing above mentioned procedures. (author)

  11. Development and operational experiences of an automated remote inspection system for interior of primary containment vessel of a BWR

    International Nuclear Information System (INIS)

    Ozaki, N.; Chikara, S.; Fumio, T.; Katsuhiro, M.; Katsutoshi, S.; Ken-Ichiro, S.; Masaaki, F.; Masayoshi, S.

    1983-01-01

    A prototype was developed for an automated remote inspection system featuring continuous monitoring of the working status of major components inside the primary containment vessel of a boiling water reactor. This inspection system consists of four units, or vehicles, which are towed by a trolley chain along a monorail; a complex coaxial cable for data transmission and for power supply; and an operator's console. A TV camera, microphone, thermometer, hygrometer, and ionization chamber are mounted on the various units. After several months' testing under high-ambient temperature, the system was installed in the Tokai-2 power station of Japan Atomic Power Company for in situ tests

  12. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Carlos Ruben Calabrese

    1999-01-01

    Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

  13. To the analysis of reactor noise in boiling water reactors

    International Nuclear Information System (INIS)

    Seifritz, W.

    1972-01-01

    The paper contains some basic thoughts on the problem of neutron flux oscillations in power reactors. The advantages of self-powered detectors and their function are explained. In addition, noise measurements of the boiling water reactors at Lingen and Holden are described, and the possibilities of an employment of vanadium detectors for the analysis of reactor noise are discussed. The final pages of the paper contain a complete list of the author's publications in the field of reactor noise analysis. (RW/AK) [de

  14. The CEA research reactors

    International Nuclear Information System (INIS)

    Schwartz, J.P.

    1993-01-01

    Two main research reactors, specifically designed, PEGASE reactor and Laue-Langevin high flux reactor, are presented. The PEGASE reactor was designed at the end of the 50s for the study of the gas cooled reactor fuel element behaviour under irradiation; the HFR reactor, was designed in the late 60s to serve as a high yield and high level neutron source. Historical backgrounds, core and fuel characteristics and design, flux characteristics, etc., are presented. 5 figs

  15. State space modeling of reactor core in a pressurized water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ashaari, A.; Ahmad, T.; M, Wan Munirah W. [Department of Mathematical Science, Faculty of Science, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Shamsuddin, Mustaffa [Institute of Ibnu Sina, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Abdullah, M. Adib [Swinburne University of Technology, Faculty of Engineering, Computing and Science, Jalan Simpang Tiga, 93350 Kuching, Sarawak (Malaysia)

    2014-07-10

    The power control system of a nuclear reactor is the key system that ensures a safe operation for a nuclear power plant. However, a mathematical model of a nuclear power plant is in the form of nonlinear process and time dependent that give very hard to be described. One of the important components of a Pressurized Water Reactor is the Reactor core. The aim of this study is to analyze the performance of power produced from a reactor core using temperature of the moderator as an input. Mathematical representation of the state space model of the reactor core control system is presented and analyzed in this paper. The data and parameters are taken from a real time VVER-type Pressurized Water Reactor and will be verified using Matlab and Simulink. Based on the simulation conducted, the results show that the temperature of the moderator plays an important role in determining the power of reactor core.

  16. Virtual nuclear reactor for education of nuclear reactor physics

    International Nuclear Information System (INIS)

    Tsuji, Masashi; Narabayashi, Takashi; Shimazu, Youichiro

    2008-01-01

    As one of projects that were programmed in the cultivation program for human resources in nuclear engineering sponsored by the Ministry of Economy, Trade and Industry, the development of a virtual reactor for education of nuclear reactor physics started in 2007. The purpose of the virtual nuclear reactor is to make nuclear reactor physics easily understood with aid of visualization. In the first year of this project, the neutron slowing down process was visualized. The data needed for visualization are provided by Monte Carlo calculations; The flights of the respective neutrons generated by nuclear fissions are traced through a reactor core until they disappear by neutron absorption or slow down to a thermal energy. With this visualization and an attached supplement textbook, it is expected that the learners can learn more clearly the physical implication of neutron slowing process that is mathematically described by the Boltzmann neutron transport equation. (author)

  17. Reactor physics and reactor strategy investigations into the fissionable material economy of the thorium and uranium cycle in fast breeder reactors and high temperature reactors

    International Nuclear Information System (INIS)

    Schikorr, W.M.

    In this work the properties governing the fissionable material economy of the uranium and thorium cycles are investigated for the advanced reactor types currently under development - the fast breeder reactor (FBR) and the high temperature reactor (HTR) - from the point of view of the optimum utilization of the available nuclear fuel reserves and the continuance of supply of these reserves. For this purpose, the two reactor types are first of all considered individually and are subsequently discussed as a complementary overall system

  18. Reactor core

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

    In a BWR type reactor, a great number of pipes (spectral shift pipes) are disposed in the reactor core. Moderators having a small moderating cross section (heavy water) are circulated in the spectral shift pipes to suppress the excess reactivity while increasing the conversion ratio at an initial stage of the operation cycle. After the intermediate stage of the operation cycle in which the reactor core reactivity is lowered, reactivity is increased by circulating moderators having a great moderating cross section (light water) to extend the taken up burnup degree. Further, neutron absorbers such as boron are mixed to the moderator in the spectral shift pipe to control the concentration thereof. With such a constitution, control rods and driving mechanisms are no more necessary, to simplify the structure of the reactor core. This can increase the fuel conversion ratio and control great excess reactivity. Accordingly, a nuclear reactor core of high conversion and high burnup degree can be attained. (I.N.)

  19. A state-of-the art on decommissioning of nuclear facilities in Japan

    International Nuclear Information System (INIS)

    Park, Seung Kook; Kim, Hee Reyoung; Chung, Un Soo; Jung, Ki Jung

    2002-05-01

    While proceeding the KRR-1 and 2 decommissioning project, we are carried out study for the state of the art on decommissioning of nuclear facilities in Japan. Also, we are studied for the research reactors and commercial power plant that has the object of decommissioning, and for the government and the organization related on decommissioning operation. We are investigated for decommissioning activities of nuclear facilities achieved by JAERI, and collected the information and data for decommissioning techniques and computational system through the JPDR(Japan Power Demonstration Reactor) decommissioning activities. Such techniques are applying for Tokai Power Station began the decommissioning project from last year, and for Fugen Nuclear Power Station to be planned the decommissioning from 2003. Recent techniques for decommissioning was acquired by direct contact. The status of the treatment for decommissioning waste and the disposal facility for the very low-level radioactive concrete wastes was grasped

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Batheja, P.; Huber, R.; Rau, P.

    1985-01-01

    Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

  1. Report on the observation of IAEA international emergency response exercise ConvEx-3(2008)

    International Nuclear Information System (INIS)

    Yamamoto, Kazuya; Sumiya, Akihiro

    2009-02-01

    The International Atomic Energy Agency IAEA carried out a large-scale international emergency response exercise under the designated name of ConvEx-3(2008), accompanying the national exercise of Mexico in July 2008. This review report summarizes two simultaneous observations of the exercises in Mexico and the IAEA headquarter during ConvEx-3(2008). Mexico has established a very steady nuclear emergency response system based on that of US, while only two BWR nuclear power units have been operated yet. The Mexican nuclear emergency response system and the emergency response activities of the Incident and Emergency Centre of the IAEA headquarter impressed important knowledge on observers that is helpful for enhancement of Japanese nuclear emergency response system in the future, e.g. establishment of Emergency Action Level and of implementation of long time exercise and enhancement of prompt protective actions. Japan had established the Act on Special Measures Concerning Nuclear Emergency Preparedness and has developed the nuclear disaster prevention system since the JCO Criticality Accident in Tokai-mura. Now is the new stage to enhance the system on the view point of prevention of a nuclear disaster affecting the neighboring countries' or prevention of a nuclear disaster which arise from the neighboring countries'. The ConvEx-3(2008) suggested key issues about nuclear disaster prevention related to the neighboring countries, e.g. establishment of much wider environmental monitoring and of international assistance system against a foreign nuclear disaster. The observations of the IAEA ConvEx-3(2008) exercise described in this review report were funded by the MEXT (Ministry of Education, Culture, Sports, Science and Technology). (author)

  2. Performance improvement of the Annular Core Pulse Reactor for reactor safety experiments

    International Nuclear Information System (INIS)

    Reuscher, J.A.; Pickard, P.S.

    1976-01-01

    The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past several years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. The new features of the improvements are described

  3. Identification of nuclear reactor characteristics by the reactor noise analysis

    International Nuclear Information System (INIS)

    Yashima, Hideyuki

    1980-01-01

    Reactor noise analysis method was applied to TRIGA II Research Reactor (Atomic Research Laboratory, Musashi Institute of Technology) and computed power spectral density (PSD) from the CIC current record. PSD has provided many valuable informations regarding to the reactor kinetics, including the effect of control rods vibration. Another information of neutron physics parameters were obtained and this result was compared with the parameter which was formerly measured by the Feynman-α experiment. Through these experiments we could find overall frequency characteristics of TRIGA II Reactor. (author)

  4. Geodetic monitoring of suspended particles in rivers

    Science.gov (United States)

    Kamnik, Rok; Maksimova, Daria; Kovačič, Boštjan

    2017-10-01

    There is a trend in modern approach to the management of space of collecting the spatial data, in order to obtain useful information. In this paper a research of suspended particles in the river Drava and Mura will be introduced. The goal is to connect different fields of water management in countries where the rivers Drava and Mura flows in purpose of water management sustainability. The methods such as GNSS for mapping cross sections of the river, the use of ADCP (Acoustic Doppler Current Profiler) measurement system and water sampling to monitor sediment in the water will be presented.

  5. Research on the reactor physics and reactor safety of VVER reactors. AER Symposium 2016

    Energy Technology Data Exchange (ETDEWEB)

    Kliem, S.

    2017-09-15

    The selected paperscan be attributed to the following main subjects: Reactor start-up tests and use of corresponding data for code validation, code development and application, approaches for safety analyses, closure of nuclear fuel cycle, prospective reactor concepts.

  6. The fast breeder reactor

    International Nuclear Information System (INIS)

    Collier, J.

    1990-01-01

    The arguments for and against the fast breeder reactor are debated. The case for the fast reactor is that the world energy demand will increase due to increasing population over the next forty years and that the damage to the global environment from burning fossil fuels which contribute to the greenhouse effect. Nuclear fission is the only large scale energy source which can achieve a cut in the use of carbon based fuels although energy conservation and renewable sources will also be important. Fast reactors produce more energy from uranium than other types of (thermal) reactors such as AGRs and PWRs. Fast reactors would be important from about 2020 onwards especially as by then many thermal reactors will need to be replaced. Fast reactors are also safer than normal reactors. The arguments against fast reactors are largely economic. The cost, especially the capital cost is very high. The viability of the technology is also questioned. (UK)

  7. Reactor feedwater system

    International Nuclear Information System (INIS)

    Kagaya, Hiroyuki; Tominaga, Kenji.

    1993-01-01

    In a simplified water type reactor using a gravitationally dropping emergency core cooling system (ECCS), the present invention effectively prevents remaining high temperature water in feedwater pipelines from flowing into the reactor upon occurrence of abnormal events. That is, (1) upon LOCA, if a feedwater pipeline injection valve is closed, boiling under reduced pressure of the remaining high temperature water occurs in the feedwater pipelines, generated steams prevent the remaining high temperature water from flowing into the reactor. Accordingly, the reactor is depressurized rapidly. (2) The feedwater pipeline injection valve is closed and a bypassing valve is opened. Steams generated by boiling under reduced pressure of the remaining high temperature water in the feedwater pipelines are released to a condensator or a suppression pool passing through bypass pipelines. As a result, the remaining high temperature water is prevented from flowing into the reactor. Accordingly, the reactor is rapidly depressurized and cooled. It is possible to accelerate the depressurization of the reactor by the method described above. Further, load on the depressurization valve disposed to a main steam pipe can be reduced. (I.S.)

  8. Neutron transport. Physics and calculation of nuclear reactors with applications to pressurized water reactors and fast neutron reactors. 2 ed.

    International Nuclear Information System (INIS)

    Bussac, J.; Reuss, P.

    1985-01-01

    This book presents the main physical bases of neutron theory and nuclear reactor calculation. 1) Interactions of neutrons with matter and basic principles of neutron transport; 2) Neutron transport in homogeneous medium and the neutron field: kinetic behaviour, slowing-down, resonance absorption, diffusion equation, processing methods; 3) Theory of a reactor constituted with homogeneous zones: critical condition, kinetics, separation of variables, calculation and neutron balance of the fundamental mode, one-group and multigroup theories; 4) Study of heterogeneous cell lattices: fast fission factor, resonance absorption, thermal output factor, diffusion coefficient, computer codes; 5) Operation and control of reactors: perturbation theory, reactivity, fuel properties evolution, poisoning by fission products, calculation of a reactor and fuel management; 6) Study of some types of reactors: PWR and fast breeder reactors, the main reactor types of the present French program [fr

  9. Ulysse, mentor reactor

    International Nuclear Information System (INIS)

    Bouquin, B.; Rio, I.; Safieh, J.

    1997-01-01

    On July 23, 1961, the ULYSSE reactor began its first power rise. Designed at that time to train nuclear engineering students and reactor operators, this reactor still remains an indispensable tool for nuclear teaching and a choice instrument for scientists. (author)

  10. Siting of research reactors

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose of this document is to develop criteria for siting and the site-related design basis for research reactors. The concepts presented in this document are intended as recommendations for new reactors and are not suggested for backfitting purposes for facilities already in existence. In siting research reactors serious consideration is given to minimizing the effects of the site on the reactor and the reactor on the site and the potential impact of the reactor on the environment. In this document guidance is first provided on the evaluation of the radiological impact of the installation under normal reactor operation and accident conditions. A classification of research reactors in groups is then proposed, together with a different approach for each group, to take into account the relevant safety problems associated with facilities of different characteristics. Guidance is also provided for both extreme natural events and for man-induced external events which could affect the safe operation of the reactor. Extreme natural events include earthquakes, flooding for river or coastal sites and extreme meteorological phenomena. The feasibility of emergency planning is finally considered for each group of reactors

  11. Experience in using a research reactor for the training of power reactor operators

    International Nuclear Information System (INIS)

    Blotcky, A.J.; Arsenaut, L.J.

    1972-01-01

    A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

  12. Reactor transients tests for SNR fuel elements in HFR reactor

    International Nuclear Information System (INIS)

    Plitz, H.

    1989-01-01

    In HFR reactor, fuel pins of LMFBR reactors are putted in irradiation specimen capsules cooled with sodium for reactor transients tests. These irradiation capsules are instrumented and the experiences realized until this day give results on: - Fuel pins subjected at a continual variation of power - melting fuel - axial differential elongation of fuel pins

  13. Nuclear reactor coolant channels

    International Nuclear Information System (INIS)

    Macbeth, R.V.

    1978-01-01

    A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

  14. Training reactor deployment. Advanced experimental course on designing new reactor cores

    International Nuclear Information System (INIS)

    Skoda, Radek

    2009-01-01

    Czech Technical University in Prague (CTU) operating its training nuclear reactor VR1, in cooperation with the North West University of South Africa (NWU), is applying for accreditation of the experimental training course ''Advanced experimental course on designing the new reactor core'' that will guide the students, young nuclear engineering professionals, through designing, calculating, approval, and assembling a new nuclear reactor core. Students, young professionals from the South African nuclear industry, face the situation when a new nuclear reactor core is to be build from scratch. Several reactor core design options are pre-calculated. The selected design is re-calculated by the students, the result is then scrutinized by the regulator and, once all the analysis is approved, physical dismantling of the current core and assembling of the new core is done by the students, under a close supervision of the CTU staff. Finally the reactor is made critical with the new core. The presentation focuses on practical issues of such a course, desired reactor features and namely pedagogical and safety aspects. (orig.)

  15. Three-dimensional reactor dynamics code for VVER type nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kyrki-Rajamaeki, R. [VTT Energy, Espoo (Finland)

    1995-10-01

    A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.).

  16. Three-dimensional reactor dynamics code for VVER type nuclear reactors

    International Nuclear Information System (INIS)

    Kyrki-Rajamaeki, R.

    1995-10-01

    A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.)

  17. Reactor performances and microbial communities of biogas reactors: effects of inoculum sources.

    Science.gov (United States)

    Han, Sheng; Liu, Yafeng; Zhang, Shicheng; Luo, Gang

    2016-01-01

    Anaerobic digestion is a very complex process that is mediated by various microorganisms, and the understanding of the microbial community assembly and its corresponding function is critical in order to better control the anaerobic process. The present study investigated the effect of different inocula on the microbial community assembly in biogas reactors treating cellulose with various inocula, and three parallel biogas reactors with the same inoculum were also operated in order to reveal the reproducibility of both microbial communities and functions of the biogas reactors. The results showed that the biogas production, volatile fatty acid (VFA) concentrations, and pH were different for the biogas reactors with different inocula, and different steady-state microbial community patterns were also obtained in different biogas reactors as reflected by Bray-Curtis similarity matrices and taxonomic classification. It indicated that inoculum played an important role in shaping the microbial communities of biogas reactor in the present study, and the microbial community assembly in biogas reactor did not follow the niche-based ecology theory. Furthermore, it was found that the microbial communities and reactor performances of parallel biogas reactors with the same inoculum were different, which could be explained by the neutral-based ecology theory and stochastic factors should played important roles in the microbial community assembly in the biogas reactors. The Bray-Curtis similarity matrices analysis suggested that inoculum affected more on the microbial community assembly compared to stochastic factors, since the samples with different inocula had lower similarity (10-20 %) compared to the samples from the parallel biogas reactors (30 %).

  18. The fast reactor

    International Nuclear Information System (INIS)

    1980-02-01

    The subject is discussed as follows: brief description of fast reactors; advantage in conserving uranium resources; experience, in UK and elsewhere, in fast reactor design, construction and operation; safety; production of plutonium, security aspects; consideration of future UK fast reactor programme. (U.K.)

  19. PUSPATI TRIGA Reactor

    International Nuclear Information System (INIS)

    Masood, Z.

    2016-01-01

    The PUSPATI TRIGA Reactor is the only research reactor in Malaysia. This 1 MW TRIGA Mk II reactor first reached criticality on 28 June 1982 and is located at the Malaysian Nuclear Agency premise in Bangi, Malaysia. This reactor has been mainly utilised for research, training and education and isotope production. Over the years several systems have been refurbished or modernised to overcome ageing and obsolescence problems. Major achievements and milestones will also be elaborated in this paper. (author)

  20. Fast Spectrum Reactors

    CERN Document Server

    Todd, Donald; Tsvetkov, Pavel

    2012-01-01

    Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...