WorldWideScience

Sample records for 69-group kaeri wims

  1. Safeguards Implementation at KAERI

    International Nuclear Information System (INIS)

    The main objective of the safeguards implementation activities is to assure that there are no diversions of declared nuclear material and/or no undeclared activity. The purpose of safeguards implementation activities is the assistance facility operators to meet the safeguards criteria set forth by the Atomic Energy Safety Acts and Regulations. In addition, the nuclear material and technology control team has acted as a contact point for domestic and international safeguards inspection activities and for the relevant safeguards cooperation. Domestic inspections were successfully carried out at the KAERI nuclear facilities pursuant to the domestic laws and regulations in parallel with the IAEA safeguards inspections. It is expected that safeguards work will be increased due to the pyro-related facilities such as PRIDE, ACPF and DUPIC, for which the IAEA is making an effort to establish safeguards approach. KAERI will actively cope with the plan of the NSSC by changing its domestic inspection regulations on the accounting and control of nuclear materials

  2. Safeguards Implementation at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Juang; Lee, Sung Ho; Lee, Byung-Doo; Kim, Hyun-Sook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The main objective of the safeguards implementation activities is to assure that there are no diversions of declared nuclear material and/or no undeclared activity. The purpose of safeguards implementation activities is the assistance facility operators to meet the safeguards criteria set forth by the Atomic Energy Safety Acts and Regulations. In addition, the nuclear material and technology control team has acted as a contact point for domestic and international safeguards inspection activities and for the relevant safeguards cooperation. Domestic inspections were successfully carried out at the KAERI nuclear facilities pursuant to the domestic laws and regulations in parallel with the IAEA safeguards inspections. It is expected that safeguards work will be increased due to the pyro-related facilities such as PRIDE, ACPF and DUPIC, for which the IAEA is making an effort to establish safeguards approach. KAERI will actively cope with the plan of the NSSC by changing its domestic inspection regulations on the accounting and control of nuclear materials.

  3. Wim Lamboo fotoprojekt Kadriorus / Piret Lindpere

    Index Scriptorium Estoniae

    Lindpere, Piret, 1963-

    1998-01-01

    Hollandi fotograafi Wim Lamboo (1949) näitus 'Eesti kunstnike portreed 1997' 18. sept.-st Kastellaanimaja galeriis. Portreede seeria on osa projektist, mis esitab fotograafi silma läbi kunstnike elu ja tööd maades, mis kuulusid Nõukogude Liidu koosseisu.

  4. Pyroprocessing technology development at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Han Soo; Park, Geun Il; Kang, Kweon Ho; Hur, Jin Mok; Kim, Jeong Guk; Ahn, Do Hee; Cho, Yung Zun; Kim, Eung Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-08-15

    Pyroprocessing technology was developed in the beginning for metal fuel treatment in the US in the 1960s. The conventional aqueous process, such as PUREX, is not appropriate for treating metal fuel. Pyroprocessing technology has advantages over the aqueous process: less proliferation risk, treatment of spent fuel with relatively high heat and radioactivity, compact equipment, etc. The addition of an oxide reduction process to the pyroprocessing metal fuel treatment enables handling of oxide spent fuel, which draws a potential option for the management of spent fuel from the PWR. In this context, KAERI has been developing pyroprocessing technology to handle the oxide spent fuel since the 1990s. This paper describes the current status of pyroprocessing technology development at KAERI from the head-end process to the waste treatment. A unit process with various scales has been tested to produce the design data associated with the scale up. A performance test of unit processes integration will be conducted at the PRIDE facility, which will be constructed by early 2012. The PRIDE facility incorporates the unit processes all together in a cell with an Ar environment. The purpose of PRIDE is to test the processes for unit process performance, operability by remote equipment, the integrity of the unit processes, process monitoring, Ar environment system operation, and safeguards related activities. The test of PRIDE will be promising for further pyroprocessing technology development

  5. Validation of WIMS-CANDU using Pin-Cell Lattices

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Won Young; Min, Byung Joo; Park, Joo Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    The WIMS-CANDU is a lattice code which has a depletion capability for the analysis of reactor physics problems related to a design and safety. The WIMS-CANDU code has been developed from the WIMSD5B, a version of the WIMS code released from the OECD/NEA data bank in 1998. The lattice code POWDERPUFS-V (PPV) has been used for the physics design and analysis of a natural uranium fuel for the CANDU reactor. However since the application of PPV is limited to a fresh fuel due to its empirical correlations, the WIMS-AECL code has been developed by AECL to substitute the PPV. Also, the WIMS-CANDU code is being developed to perform the physics analysis of the present operating CANDU reactors as a replacement of PPV. As one of the developing work of WIMS-CANDU, the U{sup 238} absorption cross-section in the nuclear data library of WIMS-CANDU was updated and WIMS-CANDU was validated using the benchmark problems for pin-cell lattices such as TRX-1, TRX-2, Bapl-1, Bapl-2 and Bapl-3. The results by the WIMS-CANDU and the WIMS-AECL were compared with the experimental data.

  6. Current Status of Pyroprocessing Development at KAERI

    OpenAIRE

    Hansoo Lee; Geun-IL Park; Jae-Won Lee; Kweon-Ho Kang; Jin-Mok Hur; Jeong-Guk Kim; Seungwoo Paek; In-Tae Kim; IL-Je Cho

    2013-01-01

    Pyroprocessing technology has been actively developed at Korea Atomic Energy Research Institute (KAERI) to meet the necessity of addressing spent fuel management issue. This technology has advantages over aqueous process such as less proliferation risk, treatment of spent fuel with relatively high heat and radioactivity, and compact equipments. This paper describes the pyroprocessing technology development at KAERI from head-end process to waste treatment. The unit process with various scales...

  7. Current Status of Pyroprocessing Development at KAERI

    Directory of Open Access Journals (Sweden)

    Hansoo Lee

    2013-01-01

    Full Text Available Pyroprocessing technology has been actively developed at Korea Atomic Energy Research Institute (KAERI to meet the necessity of addressing spent fuel management issue. This technology has advantages over aqueous process such as less proliferation risk, treatment of spent fuel with relatively high heat and radioactivity, and compact equipments. This paper describes the pyroprocessing technology development at KAERI from head-end process to waste treatment. The unit process with various scales has been tested to produce the design data associated with scale-up. Pyroprocess integrated inactive demonstration facility (PRIDE was constructed at KAERI and it began test operation in 2012. The purpose of PRIDE is to test the process regarding unit process performance, remote operation of equipments, integration of unit processes, scale-up of process, process monitoring, argon environment system operation, and safeguards-related activities. The test of PRIDE will be promising for further pyroprocessing technology development.

  8. A study for the KAERI research tunnel

    International Nuclear Information System (INIS)

    Major goal of the R and D on the KAERI Research Tunnel in 1997 are 1) concept development of the KAERI research tunnel and its major units 2) computer simulation of facilities 3) study on thermo-hydro mechanical coupling in the vicinity of a waste repository 4) effect of excavated distrubed zone. In addition supplementary site investigation to understand the distribution of stresses in the site was done along with long term monitoring of the water table. (author). 44 refs., 16 tabs., 36 figs

  9. The neutron radiography programme at KAERI

    International Nuclear Information System (INIS)

    The first KAERI neutron radiography facility, which was installed at the research reactor KRR-2(2MW) in early 1980's to utilize for the inspection of the nuclear and non-nuclear objects, was closed at the end of 1995. As a continued programme, a new neutron radiography facility has been installed at HANARO with various upgrades. In this article, its design features, performance characteristics and utilization programme are outlined.

  10. The technological innovation case of the KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Choi, J. I. [Habat Univ., Daejeon (Korea, Republic of); Jang, S. K. [Sungkonghoe Univ., Seoul (Korea, Republic of); Hong, K. P. [Baekseok Univ., Chunan (Korea, Republic of); Lee, E. S. [National Fusion Research Institue, Daejeon (Korea, Republic of)

    2008-01-15

    The research aims to investigate what key success factors (KSFs) of technological innovation in KAERI are, and to suggest how these findings are utilized for KAERI. In order to achieve these goals we have employed case study based on in-depth interview and literature review. And there are two fields of research in KAERI: one is nuclear energy-related research, the other is non energy-related research. The former is 'nuclear fuel cladding tube' which is an industrial product and being regarded as catch-up (or imitative) mode of technological innovation: the latter is 'HemoHIM', herbal composition of health functional food, which is consumer goods and regarded as creative (or innovative) mode of technological innovation. We found some KSFs in these two research and development cases in KAERI: firstly, to train researcher to be a 'product champion' who can fill in the gap of 'death valley' between pure research and commercialization: secondly, to build researchers' competency in order to catch up advanced countries' technological competencies. Thirdly, to amend institutional rules and regulations for commercializing processes of R and D outcomes, notably 'R and D joint venture by Government Research Institute (GRI) and private sector' fourthly, to enhance the capabilities of external management for researchers' technological innovation competency. And finally, we recommend using successful R and D cases as educational materials when training young researchers for sharing old generations' experiences and tacit knowledge.

  11. The collision probability modules of WIMS-E

    International Nuclear Information System (INIS)

    This report describes how flat source first flight collision probabilities are calculated and used in the WIMS-E modular program. It includes a description of the input to the modules W-FLU, W-THES, W-PIP, W-PERS and W-MERGE. Input to other collision probability modules are described in separate reports. WIMS-E is capable of calculating collision probabilities in a wide variety of geometries, some of them quite complicated. It can also use them for a variety of purposes. (author)

  12. Analysis of the burnup credit benchmark with an updated WIMS-D Library

    International Nuclear Information System (INIS)

    The OECD/NEA Burnup Credit Benchmark was analyzed with the WIMSD5B code using a fully updated library based on ENDF/B-VI Revision 5 data. Parts-1A and 1B were considered. The criticality prediction tested in Part-1A was in very good agreement with the reference result. A slight trend to overestimate the absorption rate by the fission products was noted, which can be explained by spectral effects resulting from the coarseness of the WIMS-D 69-group energy grid. The isotopic composition prediction tested in Part-1B was within the uncertainty interval of the reference results, except for 109 Ag at lower burnup and 155 Gd in all the cases. For 109 Ag the cause of the discrepancy was the use of old fission yield data in generating the reference solution. Similarly for 155 Gd the difference was due to old 155 Eu capture cross sections. Compared to the measurements, a serious underprediction of Sm isotopes is observed. This could be due to problems in the measured values or in the nuclear data of Sm precursors. We conclude that our processing methods do not introduce significant errors to the basic nuclear data. Care should be taken in the interpretation of the reference average benchmark solution due to a possible bias towards the ENDF/B-V evaluated nuclear data files

  13. The WIMS-E module W-PROC

    International Nuclear Information System (INIS)

    The program W-PROC is a module of the WIMS-E Scheme for neutronics calculations. W-PROC calculates collision probabilities for a system consisting of spherical grains packed in annular geometry, such as the fuel in a high temperature gas cooled reactor. This report describes the modelling approximations made and gives instructions for using the program. (U.K.)

  14. Overview of the Radioecological Research at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yong Ho; Lim, Kang Muk; Kim, Byung Ho; Keum, Dong Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    This paper presents a brief history of the research and a summary of the data production. During the past 30 years, a comparatively large amount of radioecological data for food crops was produced at KAERI. Some of the data have been used for the off-site dose calculation or dynamic food-chain model validation in one way or another. A considerable amount of KAERI data was included in an IAEA's handbook and underlying TECDOC. Further studies should be conducted to have sufficient numbers of parameter values to realistically cover various environmental and agricultural conditions. It is desirable for as many of the produced data as possible to be used by the dose assessor. Not only the data producer but also the dose assessor needs to make an effort for a greater amount of the domestic data to be used in estimating the public dose for Koreans. Radioecology is a scientific discipline for studying the movement and accumulation of radionuclides within ecosystems composed of air, soil, water and living organisms including humans. It started in the late 1940s in the USSR and the early 1950s in the USA for the purpose of assessing the environmental impact of the radionuclides released by military uses of fissile material. With an increase in the peaceful use of nuclear energy, radioecologists took a great interest in the environmental impact assessment of nuclear power plants and other nuclear fuel cycle facilities. Radiation doses to the public by the planned and ongoing operations of such nuclear installations should be estimated for both normal operation and an accident. These estimations are made using assessment models which require parameter values to quantify various transfer processes of radionuclides in the ecosystem. In KAERI, radioecological research has been conducted for the past 30 years with an emphasis put on the production of data on the transfer of radionuclides to major food crops.

  15. Radiological Emergency Response System of KAERI

    International Nuclear Information System (INIS)

    The Act of Physical Protection and Radiological Emergency came into effect in Feb. 2004. This act requires to the nuclear industries that the situation of the radiological emergency should be monitored by some proper equipment. To monitor the radiological emergency based on the act, KAERI, Korea Atomic Energy Research Institute, has been installing RERS, Radiological Emergency Response System, and establishing the implementation plan on the radiological emergency response. This paper describes the hardware and the operation of the RERS in view of the radiological emergency response

  16. The status of KAERI nuclear material accountancy

    Energy Technology Data Exchange (ETDEWEB)

    Park, Ho Joon; Kim, Hyun Sook; Kim, Hyun Jo; Ko, Han Suk; Lee, Byung Doo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    Nuclear material accountancy within the framework of IAEA safeguards begins with the nuclear material accounting activities by facility operators and the State system of accounting for and control of nuclear material(SSAC), implemented in accordance with the provisions of the safeguards agreement between the IAEA and the State. IAEA verify the correctness of the nuclear material accounting information in the facility records and the reports provided by the SSAC to the IAEA. This paper are described the status of KAERI nuclear material accountancy

  17. A Study on the Revitalizing of technology commercialization in KAERI

    International Nuclear Information System (INIS)

    The TEC training program should be implemented for researches who want to commercialize their own technologies. To build creative organization culture is essential for technology commercialization. Collaboration strategy is related to analyze how KAERI is catching up their technological capabilities in nuclear technology, and what the success factors of KAERI in technology commercialization are.

  18. Preliminary analysis of the KAERI RCCS Experiment Using GAMMA+

    International Nuclear Information System (INIS)

    This paper describes the analysis of the KAERI RCCS experiment. GAMMA+ code was used for analysis of the RCCS 1/4-scale natural cooling experimental facility designed and built at KAERI to verify the performance of the natural circulation phenomenon. The results obtained from the GAMMA+ analysis showing the temperature profiles and flow rates at steady state were compared with the results from the preliminary experiments conducted in this facility. GAMMA+ analysis for the KAERI RCCS experimental setup was carried out to understand its natural circulation behavior. The air flow rate at the chimney exit achieved by experiments was from to be almost same as that of GAMMA+

  19. Beam Characterization at the KAERI UED Beamline

    CERN Document Server

    Setiniyaz, Sadiq; Baek, In-Hyung; Nam, Jinhee; Chae, MoonSik; Han, Byung-Heon; Gudkov, Boris; Jang, Kyu Ha; Park, Sunjeong; Miginsky, Sergey; Vinokurov, Nikolay; Jeong, Young Uk

    2016-01-01

    The UED (ultrafast electron diffraction) beamline of the KAERI's (the Korea Atomic Energy Research Institute's) WCI (World Class Institute) Center has been successfully commissioned. We have measured the beam emittance by using the quadrupole scan technique and the charge by using a novel measurement system we have developed. In the quadrupole scan, a larger drift distance between the quadrupole and the screen is preferred because it gives a better thin-lens approximation. A high bunch-charge beam, however, will undergo emittance growth in the long drift caused by the space-charge force. We present a method that mitigates this growth by introducing a quadrupole scan with a short drift and without using the thin-lens approximation. The quadrupole in this method is treated as a thick lens, and the emittance is extracted by using the thick-lens equations. Apart from being precise, our method can be readily applied without making any change to the beamline and has no need for a big drift space. For charge measure...

  20. Interaction of NRCs with their environment - KAERI's experience

    International Nuclear Information System (INIS)

    Main players in KAERI's environment are the Government, nuclear industry (essentially nuclear power related), Academic community and the public. The Board of Trustees of KAERI has members from three important ministries of the Government and this Board formulates the nuclear R and D programme. The current programme plan covers a period of 1996-2006. The Korean nuclear industry has grown out of the core groups within KAERI. Until 1996, certain key areas in the design of nuclear steam supply system, nuclear fuel and nuclear waste management were still a part of KAERI responsibilities. However, with the growth of the nuclear power programme to 14 GW(e) (16 reactors), and more reactors under construction and plan, a decision has been taken to shift these activities to the industry, along with the personnel (600). The Government has also decided to secure financial resources for R and D by a contribution of 0.1 cents/kw·h from the nuclear utilities to a fund. In 1998 this fund collected 90 million US$ and 75% was made available to KAERI. So there is a very strong linkage between the Government, KAERI and the nuclear industry. With the academic community, KAERI takes post-graduate and post doctoral research students, gives R and D projects to the universities and has joint projects in some areas like fusion research. With public, KAERI has followed the policy of openness. It has made specific efforts to convey more easily understood benefits of radioisotopes and radiation. Also, communication is quite often targeted at specific groups rather than public at large. This policy has helped in the public acceptance of nuclear power which provided 41% of the electricity in 1998. (author)

  1. On the use of WIMS-7 for calculations on accelerator-driven systems

    Energy Technology Data Exchange (ETDEWEB)

    De Kruijff, W.J.M.; Freudenreich, W.J.M

    1998-02-01

    The WIMS-7 code package has successfully been applied for a simple benchmark of a lead-cooled accelerator-driven system (ADS). With WIMS-7 it is possible to model a fixed source and to calculate the multiplication in a subcritical system. The calculations have shown that WIMS-7 is capable of treating this benchmark of a homogenized lead-cooled system with a fast neutron spectrum. The results described in this report are very promising and stimulate further investigation of WIMS-7 to study ADS-applications and lead-cooled reactor cores. It is useful to have a more extensive validation of WIMS-7 for lead-cooled ADS. In this report we have only considered a simple homogenized system. In the near future the application of WIMS-7 will be twofold. First, WIMS-7 can be applied to calculate the neutron spectrum in an accelerator-driven system in order to perform transmutation studies with a burnup code. Second, WIMS-7 can be used to study in more detail the neutronics of accelerator-driven systems. This is useful in order to learn more about the physics of accelerator-driven systems. 6 refs.

  2. On the use of WIMS-7 for calculations on accelerator-driven systems

    International Nuclear Information System (INIS)

    The WIMS-7 code package has successfully been applied for a simple benchmark of a lead-cooled accelerator-driven system (ADS). With WIMS-7 it is possible to model a fixed source and to calculate the multiplication in a subcritical system. The calculations have shown that WIMS-7 is capable of treating this benchmark of a homogenized lead-cooled system with a fast neutron spectrum. The results described in this report are very promising and stimulate further investigation of WIMS-7 to study ADS-applications and lead-cooled reactor cores. It is useful to have a more extensive validation of WIMS-7 for lead-cooled ADS. In this report we have only considered a simple homogenized system. In the near future the application of WIMS-7 will be twofold. First, WIMS-7 can be applied to calculate the neutron spectrum in an accelerator-driven system in order to perform transmutation studies with a burnup code. Second, WIMS-7 can be used to study in more detail the neutronics of accelerator-driven systems. This is useful in order to learn more about the physics of accelerator-driven systems. 6 refs

  3. The Wims-Traca code for the calculation of fuel elements. User's manual and input data

    International Nuclear Information System (INIS)

    The set of modifications and new options developped for the Wims-D code is explained. The input data of the new version Wims-Traca are described. The printed output of results is also explained. The contents and the source of the nuclear data in the basic library is exposed. (author)

  4. Web-based sorption database (KAERI-SDB)

    International Nuclear Information System (INIS)

    Radionuclide sorption data is necessary for the safety assessment of radioactive waste disposal. However the accessibility to the nuclide sorption database is limited. The web-based sorption database (KAERI-SDB) was developed to provide sorption data in a convenient way. The development of the KAERI-SDB was achieved by improving the performance of pre-existing sorption DB programme (SDB-21C) and incorporating the user requirement. The KAERI-SDB was designed that users can access it by using a web browser. Main functions of the KAERI-SDB include (1) log-in/join, (2) search and store of sorption data and (3) scatter plot chart and index chart. It is expected that the KAERI-SDB is widely applied to the safety assessment of radioactive waste disposal by enhancing the accessibility to experts and practitioner related the nuclear industry and governmental administration. It is also expected that reliabilities for the radioactive waste disposal increased by opening the web-based sorption DB to public

  5. KAERI charged particle cross section library for radioisotope production

    CERN Document Server

    Chang, J H; Kim, D H; Lee, Y O; Zhuang, Y X

    2001-01-01

    This report summarized information and figures describing the 'KAERI Charged Particle Cross Section Library for Radioisotope production' The library contains proton-, deutron-, He-3-, and alpha-induced monitor cross sections, and gamma- and positron-emitter production cross sections. Experimental data and evaluation methods are described, and the evaluated cross sections are compared with those of the IAEA, MENDL, and LA150. The library has cross sections and emission spectra suitable for the transport analysis in the design of radioisotope production system, and are available at http://atom.kaeri.re.kr/ in ENDF-6 format.

  6. Validation of WIMS-SNAP code systems for calculations in TRIGA-MARK II type reactors

    International Nuclear Information System (INIS)

    The following paper contributes to validate the Nuclear Engineering Department methods to carry out calculations in TRIGA reactors solving a Benchmark. The benchmark is analyzed with the WIMS-D/4-SNAP/3D code system and using the cross section library WIMS-TRIGA. A brief description of the DSN method is presented used in WIMS/d4 code and also the SNAP-3d code is shortly explained. The results are presented and compared with the experimental values. In other hand the possible error sources are analyzed. (author)

  7. Development of Operational Parameters for Advanced Voloxidation Process at KAERI

    International Nuclear Information System (INIS)

    KAERI has been developing a voloxidation process as a head-end process of pyroprocessing technology with INL (Idaho National Laboratory). The work scope of KAERI is to develop the operation parameters for advanced voloxidation process at KAERI using surrogate materials and SIMFUEL. In order to evaluate operation conditions of an advanced voloxidation process, oxidation and vaporization behavior of metals and Cs compounds was investigated in terms of thermal treatment atmosphere and temperature by using thermodynamic data. And also, the oxidation and vaporization behavior of semi-volatile fission products with process pressure and temperature was investigated using surrogate materials. Particle size control for U3O8 powder was investigated using SIMFUEL and a rotary voloxidizer. According to analysis of KAERI works, the operation conditions for advanced voloxiation process may be consisted of the following four steps: 1) oxidation of UO2 pellet into U3O8 powder at 500 .deg. C in oxidative atmosphere, 2) additional oxidation of noble metal alloy and vaporization of high vapor pressure of fission products at 700 .deg. C in oxidative atmosphere, 3) granulation of U3O8 powder and vaporization of Cs compounds at 1200 .deg. C in an atmosphere of argon, and 4) reduction of UO2+x granules into UO2 granules at 1000 .deg. C in an atmosphere of 4%H2-Ar. This report will be used as a useful means for determining the operation parameters for advanced voloxidation process

  8. Spectroscopic measurements and AMO data center in KAERI

    Science.gov (United States)

    Rhee, Yongjoo; Kim, S. K.; Park, H. M.; Lee, Jongmin

    2000-11-01

    An introduction to the AMO (Atomic, Molecular, and Optical) database system in KAERI is given with some experimental aspects related to the AMO data production. Data sources, constructing concepts and current status of the database are described. An example of measured data which have been compiled internally is given. .

  9. DRAGON挂载WIMS-D核数据库的基准题计算验证%Benchmark Validation of DRAGON Program Using WIMS-D Nuclear Data Library

    Institute of Scientific and Technical Information of China (English)

    杨雪; 施工; 王侃

    2007-01-01

    通过一系列基于实验的基准题对DRAGON3.05B程序挂载WIMS-D核数据库的计算结果进行验证,综合检验了其对不同燃料、不同元件结构的临界计算以及燃耗中的核密度和κ∝的计算正确性.并通过DRAGON3.05B与WIMSD-5B分别挂载WIMS-D和ENDF/B-VI.8核数据库的计算结果进行比较.结果表明:DRAGON3.05B挂载WIMS-D库的计算结果是可靠的,其正确性可以满足对钍基先进CANDU堆的设计要求.

  10. Risorse pedagogiche interattive: accesso e condivisione. Una soluzione WIMS+SAML

    OpenAIRE

    Cazzola, M

    2011-01-01

    Il poster presenta l'integrazione di WIMS (WWW Interactive Multipurpose Server) con Shibboleth, realizzata presso l'Università di Milano-Bicocca al fine di gestire l'autenticazione e l'autorizzazione degli utenti istituzionali sulla piattaforma.

  11. Proceedings of 2008 KAERI/JAEA Joint Seminar on Advanced Irradiation and PIE Technologies; November 5-7, 2008, KAERI, Daejeon, Korea

    OpenAIRE

    Ryu, W.-S.; 石原 正博

    2008-01-01

    Under the Arrangement for Cooperation in the field of peaceful uses of Nuclear Energy between the Korea Atomic Energy Research Institute (KAERI) and the Japan Atomic Energy Agency (JAEA), the 2008 KAERI-JAEA Joint Seminar on Advanced Irradiation and PIE (post-irradiation examination) Technologies has been held at KAERI in Daejeon, Korea, from November 5 to 7, 2008. This seminar was organized by the PIE & Radwaste Division, Research Reactor Engineering Division, and Hanaro Management Division ...

  12. The Status of Implementation on Additional Protocol at KAERI

    International Nuclear Information System (INIS)

    Under the Additional Protocol, a State is required to provide the IAEA with further information on nuclear related activities, all buildings on a site, etc. through an expanded declaration and further access rights at a nuclear site and any location included in the expanded declaration. This paper describes the implementation status on the expanded declaration and the complementary access at KAERI under the AP. This paper reviewed the implementation status of the AP at KAERI, and there are some practical issues to prepare the expanded declarations as mentioned above. From the view point of the effective and efficient processing of the expanded declaration, it will be necessary to discuss the criterion for the definition of the nuclear fuel cycle-related R and D to be declared under the AP with IAEA

  13. DUPIC nuclear fuel manufacturing and process technology development at KAERI

    International Nuclear Information System (INIS)

    DUPIC fuel cycle development project in KAERI of Korea was initiated in 1991 and has advanced in relevant technologies for last 10 years. The project includes five different topics such as nuclear fuel manufacturing, compatibility evaluation, performance evaluation, manufacturing facility management, and safeguards. The contents and results of DUPIC R and D up to now are as follow: - the basic foundation was established for the critically required pelletizing technology and powder treatment technology for DUPIC. - development of DUPIC process line and deployment of 20 each process equipment and examination instruments in DFDF. - powder and pellet characterization study was done at PIEF based on the simfuel study results, and 30 DUPIC pellets were successfully produced. - the manufactured pellets were used for sample fuel rods irradiated in July,2000 in HANARO research reactor in KAERI and has been under post irradiation examination. (Hong, J. S.)

  14. A Study on the Export Control System at KAERI

    International Nuclear Information System (INIS)

    The current non-proliferation regime requires strengthening the export control from Korea to foreign countries. This means that the ministries related to export control deeply emphasize the prohibition of the illegal proliferation in the domestic society as well as international society. The principle of export control for non-proliferation of WMD is to control the transfer of the strategic items/technology to the countries which intend to develop the WMD in accordance with the multilateral agreements of the Nuclear Supply Group (NSG), Wassenaar Agreement (WA), Austrian Group (AG) and Missile Technology Control Regime (MTCR). Among them, export controls at KAERI are deeply related to the guidelines of the NSG, an international nuclear export control regime. Since the new concept of an export system was launched in Jan. 2014, KAERI needs to consider new approaches to meet the requirement of the revised domestic law and regulation. To cope with this environmental change, this paper suggests new approaches to effectively conduct the export control at KAERI

  15. Validation of WIMS-AECL reactivity device calculations for CANDU reactor

    Energy Technology Data Exchange (ETDEWEB)

    Min, Byung Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Donnelly, J. V. [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

    1997-06-01

    An important component of the overall program to validate WIMS-AECL for use with RFSP in the analysis of CANDU-6 reactors for design and safety analysis calculations is the validation of calculations of incremental cross sections used to represent reactivity devices. A method has been developed for the calculation of the three-dimensional neutron flux distribution in and around CANDU reactor fuel channels and reactivity control devices. The methods is based on one- and two dimensional transport calculations with the WIMS-AECL lattice cell code, SPH homogenization, and three-dimensional flux calculations with finite-difference diffusion theory using the MULTICELL code. Simulations of Wolsung 1 Phase-B commissioning measurements and Point Lepreau restart tests have been performed, as a part of the program to validate WIMS-AECL lattice cell calculations for application to CANDU reactor simulations in RFSP. The incremental cross section properties of the Wolsung 1 and Point Lepreau adjusters, Mechanical Control Absorbers(MCA) and liquid Zone Control Unit (ZCU) is based on the WIMS-AECL/MULTICELL modelling methods and the results are compared with those of WIMS-AECL/DRAGON-2 modelling methods. (author). 13 tabs., 4 figs., 11 refs.

  16. A general introduction to the use of the WIMS-E modular program

    International Nuclear Information System (INIS)

    This report describes the WIMS-E Scheme for Neutronics Calculations. This was originally set up to extend the existing calculational facilities in the neutronics field so as to cover a wider range of requirements and to permit more rapid changes to meet future requirements. It consists of a family of compatible reactor physics programs which pass data to each other by way of sets of standardised files. These separate programs have also been combined to form the Integrated WIMS-E Modular Program which contains them as overlay segments together with a controlling routine which selects modules for execution in response to users' commands. (author)

  17. Validation of a new library of nuclear constants of the WIMS code; Validacion de una nueva biblioteca de constantes nucleares del Codigo WIMS

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F. [Departamento de Experimentacion, Gerencia del Reactor, ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1991-10-15

    The objective of the present work is to reproduce the experimental results of the thermal reference problems (benchmarks) TRX-1, TRX-2 and BAPL-1 to BAPL-3 with the WIMS code. It was proceeded in two stages, the first one consisted on using the original library of the code, while in the second one, a library that only contains the present elements in the benchmarks: H{sup 1}, O{sup 16}, Al{sup 27}, U{sup 235} and U{sup 238} was generated. To generate the present nuclear data in the WIMS library, it was used the ENDF/B-IV database and the Data processing system of Nuclear Data NJOY, the library was generated using the FIXER code. (Author)

  18. Coupling of Wims-AECL and Origen-S for depletion calculations - 357

    International Nuclear Information System (INIS)

    One of the more powerful tools for isotope depletion calculations in neutron-irradiated material is the SCALE (Standardized Computer Analyses for Licensing Evaluation) module ORIGEN-S, maintained and developed by Oak Ridge National Laboratory. ORIGEN-S takes as input, in addition to a material description, a problem-dependent cross section library in which relative reaction rates for each nuclear process have been pre-evaluated. Creating different libraries for different stages of burnup, and for different materials, allows the 'point' code phenomenology of ORIGEN-S to be extended to more complicated geometries. To this end, AECL (Atomic Energy of Canada Limited) has coupled its successful 2-D neutron transport solver WIMS-AECL 2.5d to ORIGEN-S to create the coupled code 'WOBI' (WIMS-ORIGEN Burnup Integration). This code has been validated against PIE (post irradiation examination) results for CANDUTM reactors and for light-water reactors, and is extensively used at AECL to calculate exit compositions and decay heats for high and low enriched uranium fuels at the NRU (National Research Universal) research reactor located at the Chalk River Laboratories. In addition, because of the significantly expanded list of reactions available in ORIGEN-S, WOBI is more useful for advanced fuel cycle studies than WIMS-AECL alone. This paper discusses the validation results, and verification of WOBI against simple WIMS-AECL and ORIGEN-S stand-alone models. (authors)

  19. LWR-WIMS, a computer code for light water reactor lattice calculations

    International Nuclear Information System (INIS)

    LMR-WIMS is a comprehensive scheme of computation for studying the reactor physics aspects and burnup behaviour of typical lattices of light water reactors. This report describes the physics methods that have been incorporated in the code, and the modifications that have been made since the code was issued in 1972. (U.K.)

  20. Definition and Analysis of Heavy Water Reactor Benchmarks for Testing New Wims-D Libraries

    International Nuclear Information System (INIS)

    This work is part of the IAEA-WIMS Library Update Project (WLUP). A group of heavy water reactor benchmarks have been selected for testing new WIMS-D libraries, including calculations with WIMSD5B program and the analysis of results.These benchmarks cover a wide variety of reactors and conditions, from fresh fuels to high burnup, and from natural to enriched uranium.Besides, each benchmark includes variations in lattice pitch and in coolants (normally heavy water and void).Multiplication factors with critical experimental bucklings and other parameters are calculated and compared with experimental reference values.The WIMS libraries used for the calculations were generated with basic data from JEF-2.2 Rev.3 (JEF) and ENDF/B-VI iNReleaseln 5 (E6) Results obtained with WIMS-86 (W86) library, included with WIMSD5B package, from Windfrith, UK with adjusted data, are included also, for showing the improvements obtained with the new -not adjusted- libraries.The calculations with WIMSD5B were made with two methods (input program options): PIJ (two-dimension collision probability method) and DSN (one-dimension Sn method, with homogenization of materials by ring).The general conclusions are: the library based on JEF data and the DSN meted give the best results, that in average are acceptable

  1. Nuclear data evaluation and group constant generation for reactor analysis

    International Nuclear Information System (INIS)

    A new 69-group nuclear data library for WIMS-KAERI code was generated using the ENDF/B-V, IV, JENDL-2, and ENDL-84 data and NJOY which is nuclear data processing code. Thermal reactor benchmark problems recommended by the Cross Section Evaluation Working Group at BNL were analyzed using this new library and WIMS-KAERI code. Using 14 benchmark problems the calculated average value and standard deviation for effective multiplication factors were 1.00303 and 0.00514, respectvely.(Author)

  2. Validation of WIMS-SNAP code systems for calculations in TRIGA-MARK II type reactors; Validacion del sistema de codigos WIMS-SNAP para calculos en reactores nucleares tipo TRIGA-MARK II

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez Valle, S.; Lopez Aldama, D. [Centro de Investigaciones Nucleares, Tecnologicas y Ambientales, La Habana (Cuba). E-mail: svalle@ctn.isctn.edu.cu

    2000-07-01

    The following paper contributes to validate the Nuclear Engineering Department methods to carry out calculations in TRIGA reactors solving a Benchmark. The benchmark is analyzed with the WIMS-D/4-SNAP/3D code system and using the cross section library WIMS-TRIGA. A brief description of the DSN method is presented used in WIMS/d{sup 4} code and also the SNAP-3d code is shortly explained. The results are presented and compared with the experimental values. In other hand the possible error sources are analyzed. (author)

  3. Status of the Decommissioning Engineering System Code Development of KAERI in 2014

    International Nuclear Information System (INIS)

    Various information systems have been developed and used at decommissioning sites for planning a project, record keeping for a post management and cost estimation. KAERI is the only expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR-1 and 2 and UCP (Uranium Conversion Plant) decommission. KAERI DES supports two kinds of platform; web-based or application oriented program. This paper describes current status and features of KAERI DES application. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DES application program, which is going to be an important mile stone of decommission industry in Korea. User friendly graphical interface and lots of actual data let people well understood on decommission cost evaluation. It is expected that continuous effort and funds will be delivered to this research

  4. Development of a neutron guide tube production technique at KAERI

    Science.gov (United States)

    Cho, Sang-Jin; Seung, Baek-Soek; Lee, Chang-Hee; Kim, Hark-Rho

    2006-11-01

    In this paper, we present KAERI's technical development status for a neutron guide tube fabrication. To achieve a high uniformity, very low roughness and perfect interface during the layer growth process, a sputtering machine was developed whereby various deposition parameters can be controlled. The Ni mirrors fabricated with this coating equipment show a neutron reflectivity of 97% at the critical angle and the Ni/Ti-supermirrors show ( M=2) 84%. For a substrate alignment and assembly for the guide elements, a non-contact measurement apparatus equipped with optical microscopes was developed instead of using a 3-axis measuring machine. By employing this optical equipment, it was possible to assemble a neutron guide with an accuracy in the lateral direction of 0.005 mm and in the vertical direction of 0.01 mm.

  5. Arc plasma simulation of the KAERI large ion sourcea)

    Science.gov (United States)

    In, S. R.; Jeong, S. H.; Kim, T. S.

    2008-02-01

    The KAERI large ion source, developed for the KSTAR NBI system, recently produced ion beams of 100keV, 50A levels in the first half campaign of 2007. These results seem to be the best performance of the present ion source at a maximum available input power of 145kW. A slight improvement in the ion source is certainly necessary to attain the final goal of an 8MW ion beam. Firstly, the experimental results were analyzed to differentiate the cause and effect for the insufficient beam currents. Secondly, a zero dimensional simulation was carried out on the ion source plasma to identify which factors control the arc plasma and to find out what improvements can be expected.

  6. The status and latest issues on KAERI export control implementation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Sook; Park, Ho Jun; Kim, Hyun Jo; Ko, Han Suk; Lee, Byung Doo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    There are four informal non-proliferation arrangements which seek to control the proliferation of weapons of mass destruction and their missile delivery systems and the transfer of conventional weapons and dual-use technologies. The four arrangements are Wassenaar Arrangement (WA) on export controls for conventional arms and dual use goods and technologies, Nuclear Supplies Group(NSG), Missile Technology Control Regime(MTCR) and Australia Group(AG) on chemical and biological weapons materials. ROK participates in four arrangements to seek to encourage responsible practice in the trade of strategic goods and technologies. It is achieved through the implementation of export control list. MKE Notification (Ministry of Knowledge Economy Notification No. 2009-250) specifies those items and technologies subject to control. In this paper, the status and latest issues on KAERI export control implementation are described

  7. A study on the mid- and long-term strategies of KAERI's future vision

    International Nuclear Information System (INIS)

    In this study, KAERI's role, expected changes of KAERI's management environments and its implementational directions, strategical direction of nuclear R and D, and KAERI's future vision and sustainable growth strategies beyond the up-to date successful achievements were analysed. The purpose of this study is investigating recent rapid changes of KAERI's political and management environments to establish future vision and growth strategies of KAERI in the 21st centuries. KAERI has performed its' mission as a government funded research organization successfully and significantly contributed promotion of national nuclear industry and capabilities through manpower development and self-reliance of nuclear power technologies and academic advancement in the fields of nuclear energy. That way, it has contributed to supply stable energy and develop economy and industry as well. In order to respond properly to newly emerged missions, integral and systematic institutional efforts are required to secure more research findings from the central and local Government and industries as well. High-quality human resources having creative expertise, experiences and skills are pre-requisite for securing competitiveness of nuclear technologies and industries. So it is essential to request the Governmental support and establish the manpower development plan in long term bases. KAERI is now standing at the turning moment to take off from the catch-up strategy of the advanced nuclear technologies (KAERI 1.0) into the innovative and creative vision and challenges, that is to say, KAERI 2.0, to establish an new technological culture, respond to social requirements and seek the international leading role

  8. Design of a Capacitive Flexible Weighing Sensor for Vehicle WIM System

    Directory of Open Access Journals (Sweden)

    Qing Li

    2007-08-01

    Full Text Available With the development of the Highway Transportation and Business Trade, vehicle weigh-in-motion (WIM technology has become a key technology and trend of measuring traffic loads. In this paper, a novel capacitive flexible weighing sensor which is light weight, smaller volume and easy to carry was applied in the vehicle WIM system. The dynamic behavior of the sensor is modeled using the Maxwell-Kelvin model because the materials of the sensor are rubbers which belong to viscoelasticity. A signal processing method based on the model is presented to overcome effects of rubber mechanical properties on the dynamic weight signal. The results showed that the measurement error is less than ���±10%. All the theoretic analysis and numerical results demonstrated that appliance of this system to weigh in motion is feasible and convenient for traffic inspection.

  9. La Escuela de Düsserdolf y el cine de Wim Wenders. The School of Düsserdolf and the cinema of Wim Wenders

    Directory of Open Access Journals (Sweden)

    Pilar Mayorgas

    2012-04-01

    Full Text Available El protagonismo de la imagen fotográfica en el cine de Wim Wenders, ya ha sido largamente estudiado, permitiéndonos un análisis aislado de la fotografía en su cine, que responda a la pregunta: qué estilo fotográfico e influencias se pueden hallar en la filmografía de Wenders. A partir de su propia auto-definición como cineasta y fotógrafo, compararemos sus imágenes, revisando las génesis y nexos que comparten, con el movimiento fotográfico de la Escuela de Düsserdolf que se construye en la misma Alemania de Wenders. Los mentores de esta Nueva Fotografía, son el matrimonio Becher: Bern y Hilla Becher iniciado en 1959, en Düsserdolf, y que junto a sus discípulos: Andreas Gursky, Candida Höfer, Thomas Struth o Thomas Ruff, colocarán a la fotografía en la primera línea del arte actual. Este hecho a un autor multidisciplinar como Wenders, no le pasará inadvertido, sino todo lo contrario; absorberá el nuevo discurso que propone esta Escuela, para exponerlo en sus tomas, revelando así en su cine una exégesis de esta nueva propuesta fotográfica en dialogo con el lenguaje cinematográfico. Todos ellos contribuirán a consolidar la imagen como arte, erigiendo al paisaje como protagonista principal.The role of the photographic image in the film by Wim Wenders has already been extensively studied, allowing us an isolated analysis of the picture at the cinema, to respond to the question: which photographic style and influences can be found in the filmography of Wim Wenders. From its own self-definition as a filmmaker and photographer, compare your images, reviewing the genesis and links that share with the movement's photographic School of Dusserdolf that is being built in the same Germany of Wim Wenders. The mentors of this new photography are marriage Becher: Bern and Hilla Becher initiated in 1959 in Dusserdolf, and that together with his disciples: Andreas Gursky, Candida Höfer, Thomas Struth or Thomas Ruff, positioned at the

  10. Recent Progress on the DUPIC Fuel Fabrication Technology at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jung-Won Lee; Ho-Jin Ryu; Geun-Il Park; Kee-Chan Song [Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong-ku, Daejeon, 305-353 (Korea, Republic of)

    2008-07-01

    Since 1991, KAERI has been developing the DUPIC fuel cycle technology. The concept of a direct use of spent PWR fuel in Candu reactors (DUPIC) is based on a dry processing method to re-fabricate Candu fuel from spent PWR fuel without any intentional separation of the fissile materials and fission products. A DUPIC fuel pellet was successfully fabricated and the DUPIC fuel element fabrication processes were qualified on the basis of a Quality Assurance program. Consequently, the DUPIC fuel fabrication technology was verified and demonstrated on a laboratory-scale. Recently, the fuel discharge burn-up of PWRs has been extended to reduce the amount of spent fuel and the fuel cycle costs. Considering this trend of extending the fuel burn-up in PWRs, the DUPIC fuel fabrication technology should be improved to process high burn-up spent fuels. Particularly the release behavior of cesium from the pellet prepared with a high burn-up spent fuel was assessed. an improved DUPIC fuel fabrication technology was experimentally established with a fuel burn-up of 65,000 MWd/tU. (authors)

  11. Current activities of post-irradiation examination at KAERI

    International Nuclear Information System (INIS)

    A wide range of post-irradiation examination (PIE) for the nuclear fuels irradiated at NPPs with different design characteristics have been carried out at PIEF at KAERI. The examination was conducted to evaluate the irradiation performances as well as the fuel integrities. The input data leading to the design upgrades of the nuclear fuels have mostly been obtained from the PIE of the irradiated fuels. A comprehensive non-destructive and destructive examination equipment are incorporated with the hot cell examination system. The main activity of PIEF is concentrated on the commercial nuclear fuel examination as the IMEF focused on the HANARO irradiated fuel and material examination. Recently, the above mentioned two facilities put great concentrations on the examination of the structural components of the fuel assembly such as skeleton, spacer grid and hold down spring elements to cope with the safety requirements of fuel integrities to meet a highly extended burn up conditions. In this paper, a brief and general activity of the both facilities and the future scope of work are introduced. (author)

  12. DUPIC fuel fabrication using spent PWR fuels at KAERI

    International Nuclear Information System (INIS)

    This document contains DUPIC fuel cycle R and D activities to be carried out for 5 years beyond the scope described in the report KAERI/AR-510/98, which was attached to Joint Determination for Post-Irradiation Examination of irradiated nuclear fuel, by MOST and US Embassy in Korea, signed on April 8, 1999. This document is purposely prepared as early as possible to have ample time to review that the over-all DUPIC activities are within the scope and contents in compliance to Article 8(C) of ROK-U.S. cooperation agreement, and also maintain the current normal DUPIC project without interruption. Manufacturing Program of DUPIC Fuel in DFDF and Post Irradiation Examination of DUPIC Fuel are described in Chapter I and Chapter II, respectively. In Chapter III, safeguarding procedures in DFDF and on-going R and D on DUPIC safeguards such as development of nuclear material accounting system and development of containment/surveillance system are described in details

  13. DUPIC fuel fabrication using spent PWR fuels at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ho Dong; Yang, Myung Seung; Ko, Won Il and others

    2000-12-01

    This document contains DUPIC fuel cycle R and D activities to be carried out for 5 years beyond the scope described in the report KAERI/AR-510/98, which was attached to Joint Determination for Post-Irradiation Examination of irradiated nuclear fuel, by MOST and US Embassy in Korea, signed on April 8, 1999. This document is purposely prepared as early as possible to have ample time to review that the over-all DUPIC activities are within the scope and contents in compliance to Article 8(C) of ROK-U.S. cooperation agreement, and also maintain the current normal DUPIC project without interruption. Manufacturing Program of DUPIC Fuel in DFDF and Post Irradiation Examination of DUPIC Fuel are described in Chapter I and Chapter II, respectively. In Chapter III, safeguarding procedures in DFDF and on-going R and D on DUPIC safeguards such as development of nuclear material accounting system and development of containment/surveillance system are described in details.

  14. Thermal Analysis of KAERI TRISO Fuel Irradiation at HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Moon-Sung; Kim, B. G.; Yang, S. W. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The TRISO(Tri-structural Isotropic)-coated fuel particle for a VHTR has a diameter of around 1 mm, and is composed of a nuclear fuel kernel and four different outer coating layers. These coating layers consist of a buffer PyC (pyrolytic carbon) layer, an inner PyC layer, a SiC layer, and an outer PyC layer. The fuel kernel is a source of a heat generation by the nuclear fission of fissile uranium. The role of each of the four coating layers is different in view of retaining the generated fission products and other interactions during in-reactor service. KAERI has been developing a TRISO-coated particle fuel technology as a part of the Korean VHTR (Very High Temperature modular gas cooled Reactor) project, which started in 2004, and completed its first irradiation test of TRISO fuels in its research reactor, HANARO for an evaluation and prediction of the irradiation behavior of the fuel. The test was started in August 4, 2013 and finished in March 31, 2014 completing its 5 cycle irradiation of 132.2 EFPD. In this paper, thermal performance of TRISO fuels was evaluated for its five cycle irradiation at HANARO which had been carried out in the absence of the fuel temperature monitoring. A COMSOL based FE (finite element) model was utilized in this analysis. Thermal performance of TRISO fuels was evaluated for its five cycle irradiation at HANARO which had been carried out in the absence of the fuel temperature monitoring. A maximum peak temperature of 1,083 .deg. C was obtained in the rod 1 at 25.06 EFPD and the temperatures decreased as the cycle progresses.

  15. Proceedings of the third JAERI-KAERI joint seminar on post irradiation examination technology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-09-01

    Between the Department of JMTR of the Japan Atomic Energy Research Institute (JAERI) and the Nuclear Fuel Cycle Research Group of the Korea Atomic Energy Research Institute (KAERI), it has been periodically carried out the collaboration on technical information exchange by specialists and scientists, under the Arrangement of the Implementation of Cooperative Research Program in the Field of Peaceful Uses of Nuclear between JAERI and KAERI. And JAERI-KAERI joint seminar has been held every three years. The 1st and 2nd JAERI-KAERI Joint Seminars were held in November 1992 at JAERI and in September 1995 at KAERI, respectively. The 3rd JAERI-KAERI Joint Seminar was held on 25 and 26 March, 1999 at the Oarai Research Establishment of JAERI. In this seminar, total participants of 84 were joined from JAERI, KAERI, Hanyang University, Japan Nuclear Cycle Development Institute, Oarai Branch of Institute for Materials Research (IMR) of Tohoku University, Nippon Nuclear Fuel Development Co., Ltd., Nuclear Development Corporation and others. Contributed presentations were in three sessions; Current status and future perspectives on PIE, PIE techniques and Evaluation of PIE data. Re-assembling technique for JOYO fuel, Nd-YAG laser welding technique, grain boundary analysis using FEG-TEM, lift time estimation of PWR Rod Cluster Control Assembly (RCCA) rodlet and failure analysis of Korea Nuclear Power Plant (KNP) fuel have been widely noticed as topic items on PIE. And some comments from PIE user, were pointed out that the nano-PIE technique, the flexibility to ad-hoc demands on testing space or utilization, and the international collaboration were very important for the next generation's PIE. The 34 of the present papers are indexed individually. (J.P.N.)

  16. Proceedings of the third JAERI-KAERI joint seminar on post irradiation examination technology

    International Nuclear Information System (INIS)

    Between the Department of JMTR of the Japan Atomic Energy Research Institute (JAERI) and the Nuclear Fuel Cycle Research Group of the Korea Atomic Energy Research Institute (KAERI), it has been periodically carried out the collaboration on technical information exchange by specialists and scientists, under the Arrangement of the Implementation of Cooperative Research Program in the Field of Peaceful Uses of Nuclear between JAERI and KAERI. And JAERI-KAERI joint seminar has been held every three years. The 1st and 2nd JAERI-KAERI Joint Seminars were held in November 1992 at JAERI and in September 1995 at KAERI, respectively. The 3rd JAERI-KAERI Joint Seminar was held on 25 and 26 March, 1999 at the Oarai Research Establishment of JAERI. In this seminar, total participants of 84 were joined from JAERI, KAERI, Hanyang University, Japan Nuclear Cycle Development Institute, Oarai Branch of Institute for Materials Research (IMR) of Tohoku University, Nippon Nuclear Fuel Development Co., Ltd., Nuclear Development Corporation and others. Contributed presentations were in three sessions; Current status and future perspectives on PIE, PIE techniques and Evaluation of PIE data. Re-assembling technique for JOYO fuel, Nd-YAG laser welding technique, grain boundary analysis using FEG-TEM, lift time estimation of PWR Rod Cluster Control Assembly (RCCA) rodlet and failure analysis of Korea Nuclear Power Plant (KNP) fuel have been widely noticed as topic items on PIE. And some comments from PIE user, were pointed out that the nano-PIE technique, the flexibility to ad-hoc demands on testing space or utilization, and the international collaboration were very important for the next generation's PIE. The 34 of the present papers are indexed individually. (J.P.N.)

  17. Proceedings of 2008 KAERI/JAEA joint seminar on advanced irradiation and PIE technologies

    International Nuclear Information System (INIS)

    Under the Arrangement for Cooperation in the field of peaceful uses of Nuclear Energy between the Korea Atomic Energy Research Institute (KAERI) and the Japan Atomic Energy Agency (JAEA), the 2008 KAERI-JAEA Joint Seminar on Advanced Irradiation and PIE (post-irradiation examination) Technologies has been held at KAERI in Daejeon, Korea, from November 5 to 7, 2008. This seminar was organized by the PIE and Radwaste Division, Research Reactor Engineering Division, and HANARO Management Division in KAERI. It was also the first time to hold the seminar under the agreement signed September 4, 2008. This triennial seminar is the sixth in series of bilateral exchange of irradiation technologies. Since the first joint seminar on Post Irradiation Examination Technology between JAERI and KAERI held at JAERI Oarai center, Japan in 1992, it has been a good model of international cooperation program between KAERI and JAEA in the field of neutron irradiation uses. At the fifth seminar in 2005, irradiation technology field was included to the joint seminar, moreover in this time it is expanded to the research reactor management field for covering whole areas of irradiation using in research reactors. The seminar was divided into three technical sessions; the sessions addressed the general topics of 'research reactor management', 'advanced irradiation technology' and 'post-irradiation examination technology'. Total 46 presentations were made, and active information exchange was done among participants. This proceeding is containing the papers or manuscripts presented in the 2008 KAERI-JAEA Joint Seminar on Advanced Irradiation and PIE Technologies. The 46 of the presented papers indexed individually. (J.P.N.)

  18. Assessment of a Bridge WIM System on Integral Concrete Bridges and on Steel Orthotropic Decks

    OpenAIRE

    Ieng, Sio Song; SCHMIDT, Franziska; ROMBONI, Frédéric; Jacob, Bernard

    2011-01-01

    Bridge-Weigh-In-Motion uses bridges as a scale to weigh vehicles. Practically, this is done by measuring the strains in that bridge, and relating them to the weight and dimensions of a truck called “calibration trucks” whose shape and axle weights are well known. This article summarizes different B-WIM experiments the institute IFSTTAR (formerly called LCPC) realized and the lessons drawn from this experience. First, the system has been tested on frame-type bridges with integral s...

  19. Sensitivity analysis on various parameters for lattice analysis of DUPIC fuel with WIMS-AECL code

    Energy Technology Data Exchange (ETDEWEB)

    Roh, Gyu Hong; Choi, Hang Bok; Park, Jee Won [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The code WIMS-AECL has been used for the lattice analysis of DUPIC fuel. The lattice parameters calculated by the code is sensitive to the choice of number of parameters, such as the number of tracking lines, number of condensed groups, mesh spacing in the moderator region, other parameters vital to the calculation of probabilities and burnup analysis. We have studied this sensitivity with respect to these parameters and recommend their proper values which are necessary for carrying out the lattice analysis of DUPIC fuel.

  20. Proceedings of 2012 JAEA/KAERI joint seminar on advanced irradiation and PIE technologies

    International Nuclear Information System (INIS)

    Under the 'Arrangement for Corporation in the field of peaceful uses of Nuclear Energy between the Japan Atomic Energy Agency (JAEA) and the Korean Atomic Energy Research Institute (KAERI)', the 2012 JAEA/KAERI Joint Seminar on Advanced Irradiation and PIE (post-irradiation examination) Technologies has been held at Mito, Japan from March 28 to 30, 2012. This triennial seminar is the seventh in series of bilateral exchange of irradiation and PIE technologies and research reactor management. Since the first joint seminar on the PIE Technology between JAERI (Japan Atomic Energy Research Institute, former agency of JAEA) and KAERI was held at JAERI Oarai Research Institute, Japan in 1992, the international cooperation program between JAEA and KAERI has been actively carried out in the field of neutron irradiation. At the fifth seminar in 2005 and sixth in 2008, the irradiation technology and the research reactor management fields were included, respectively, to the joint seminar, and it covers whole areas of irradiation using research reactors. In this seminar total 37 presentations were made in three technical sessions, which are 'research reactor management', 'advanced irradiation technology' and 'post-irradiation examination technology', and active information exchange was done among participants. Papers or manuscripts presented in the 2012 JAEA/KAERI Joint Seminar on Advanced Irradiation and PIE Technologies are contained in the proceedings. (author)

  1. Internal structure of spiral arms traced with [CII]: Unraveling the WIM, HI, and molecular emission lanes

    CERN Document Server

    Velusamy, T; Goldsmith, P F; Pineda, J L

    2015-01-01

    The spiral arm tangencies are ideal lines of sight in which to determine the distribution of interstellar gas components in the spiral arms and study the influence of spiral density waves on the interarm gas in the Milky Way. We present a large scale (~15deg) position-velocity map of the Galactic plane in [CII] from l = 326.6 to 341.4deg observed with Herschel HIFI. We use [CII] l-v maps along with those for Hi and 12CO to derive the average spectral line intensity profiles over the longitudinal range of each tangency. Using the VLSR of the emission features, we locate the [CII], HI, and 12CO emissions along a cross cut of the spiral arm. In the spectral line profiles at the tangencies [CII] has two emission peaks, one associated with the compressed WIM and the other the molecular gas PDRs. When represented as a cut across the inner to outer edge of the spiral arm, the [CII]-WIM peak appears closest to the inner edge while 12CO and [CII] associated with molecular gas are at the outermost edge. HI has broader ...

  2. WLUP3.0, 69 and 172 Group Cross Section Libraries for WIMS

    International Nuclear Information System (INIS)

    Description or function: WLUP contains validated WIMS-D formatted cross section libraries in 69 and 172 energy group structures for nuclear reactor calculations. Materials from recently released evaluated nuclear data libraries are included. The NJOY nuclear data processing system was applied for generating the cross section files following the models and conventions built into the WIMS-D lattice code. The relevant features for the WIMS users are: - Energy group structures: 69 and 172 energy groups. - List of materials: WIMS ID, general information, source of data. - Cross sections: 69 and 172 group plots. - Resonance data: WIMS ID, temperature, background cross sections. - Goldstein-Cohen factors: Goldstein-Cohen lambda values. - Thermal scattering data: thermal scattering laws and P1 matrixes. - Fission spectrum: fission spectrum data. - Burnup data: burnup chains. - Fission product yields: fission yield tables. - Pseudo lumped fission product: Description of pseudo fission product. - Energy release by fission: table of energy released by fission. - Dosimetry data: dosimetry reactions, source of data. - Averaging flux and current spectra: flux and current spectra plots (Numerical data on NJOY inputs). - WIMSD5B updates: WIMSD5B extensions and updates. - Processing methods: Brief description on processing methods. Moderators: 1-H-H2O, 1-H-ZrH, 1-D-D2O, 4-Be, 6-C, 8-O-16. Structural materials: 2-He-3, 2-He-4, 3-Li-6, 3-Li-7, 5-B-10, 5-B, 7-N, 9-F, 11-Na, 12-Mg, 13-Al, 14-Si, 15-P, 16-S, 17-Cl, 20-Ca, 22-Ti, 23-V, 24-Cr, 25-Mn, 26-Fe, 27-Co-59, 28-Ni, 29-Cu, 40-Zr, 41-Nb-93, 42-Mo, 47-Ag, 48-Cd, 49-In, 50-Sn, 51-Sb-121, 51-Sb-123, 63-Eu, 72-Hf, 73-Ta, 74-W, 82-Pb. Burnable materials: 5-B-10, 5-B-11, 72-Hf-176, 72-Hf-177, 72-Hf-178, 72-Hf-179, 72-Hf-180. Fission products: 36-Kr-83, 42-Mo-95, 43-Tc-99, 44-Ru-101, 44-Ru-103, 44-Ru-106, 45-Rh-103, 45-Rh-105, 46-Pd-105, 46-Pd-107, 46-Pd-108, 47-Ag-109, 48-Cd-113, 49-In-115, 51-Sb-125, 52-Te-127, 53-I-127, 53-I-135, 54-Xe

  3. The KAERI 10 MeV Electron Linac - Description and Operational Manual

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Cheol; Park, Seong Hee; Jung, Young Uk; Han, Young Hwan; Kang, Hee Young

    2005-06-15

    The objective of this technical report is to guide the right operation and maintenance of the KAERI electron linac system. The KAERI electron linac system consists of 2 MeV injector based on 176 MHz Normal conducting RF (Radio Frequency)cavity and 10 MeV main accelerator based on 352 MHz Superconducting RF cavity, electron beamlines (injection and extraction). Since a electron accelerator generates hazard radiation, this system is located at the shielded room in basement and we can operate the system using the remote control system. It includes the description and the operational manual as well as the detailed technical direction for trouble shooting.

  4. MOX use in reactors: Benchmarking of neutronic codes -- Analyses of selected Saxton plutonium program experiments using WIMS7a

    Energy Technology Data Exchange (ETDEWEB)

    Cuevas Vivas, G.F.; Paris, T.A. [Texas A and M Univ., College Station, TX (United States)

    1999-03-01

    As part of the effort for the benchmarking neutronic codes for plutonium utilization, the deterministic code WIMS7a (and its associated JEF 2.2 nuclear data library) was employed to calculationally model a selected group of the Saxton experiments. The selection of the experimental configurations to be modeled was performed based on the best experimental information available, and so as to fully exploit the neutronic variety of the Saxton plutonium program experiments. The modular WIMS7a code can be run in many ways. For the analyses presented here, a solver strategy was implemented using WIMS7a`s most evolved modules. The results showed a slightly better agreement with the experimental values for the effective neutron multiplication than the earlier results (obtained in 1997) using the codes, WIMSD4m and DIF3D. However, the calculated relative rod power distributions were not improved even though several energy group structures were tried. The simulations were carried out at Texas A and M University with access to WIMS7a being obtained via a one year lease from the AEA Technology.

  5. A computer program with graphical user interface to plot the multigroup cross sections of WIMS-D library

    International Nuclear Information System (INIS)

    As a result of the IAEA Co-ordinated Research Programme entitled 'Final Stage of the WIMS Library Update Project', new and updated WIMS-D libraries based upon ENDF/B-VI.5, JENDL-3.2 and JEF-2.2 have become available. A project to prepare an exhaustive handbook of WIMS-D cross sections from old and new libraries has been taken up by the authors. As part of this project, we have developed a computer program XnWlup with user-friendly graphical interface to help the users of WIMS-D library to enable quick visualization of the plots of the energy dependence of the multigroup cross sections of any nuclide of interest. This software enables the user to generate and view the histogram of 69 multi-group cross sections as a function of neutron energy under Microsoft Windows environment. This software is designed using Microsoft Visual C++ and Microsoft Foundation Classes Library. The current features of the software, on-line help manual and future plans for further development are described in this paper

  6. Traffic weigh-in-motion (WIM measurements and validation of the Texas perpetual pavement structural design concept

    Directory of Open Access Journals (Sweden)

    Lubinda F. Walubita

    2011-01-01

    Full Text Available Over the past few years, the State of Texas has used perpetual pavement (PP structures on its heavily trafficked highways, where the expected 20-year truck-traffic estimate of 80 kN ESALs (equivalent single axle loads is in excess of 30 million. As a means to validate the Texas PP structural design concept and to make optimal future truck-traffic design recommendations, traffic Weigh In-Motion (WIM measurements were conducted and analyzed for two PP projects. The findings indicated that the initial 80 kN ESAL traffic design estimates for PP were comparable to the projections based on the actual measured WIM traffic data. However, underestimation of the hot mix asphalt layer dynamic moduli resulted in conservative designs for the PP structures. In addition, based on the successful use of the automated WIM data stations for traffic data collection, the paper highlights possible applications and advantages (as compared to conventional manual collection of traffic data of using detailed WIM traffic data information for future analyses of both highway operation and pavement structural design.

  7. The Status of Development on a Web-Based Nuclear Material Accounting System at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byungdoo; Kim, Inchul; Lee, Seungho; Kim, Hyunjo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The Integrated Safeguards (IS) has been applied to 10 nuclear facilities and 1 location outside facility (LOF) at the Korea Atomic Energy Research Institute (KAERI) since July 2008. One of the major changes in the implementation of safeguards under the IS is to apply the concept of a Random Interim Inspection (RII) instead of an interim inspection. The RII plan is notified within a few hours under the IS. It is thus difficult for facility operators to prepare the inspection documents within a short time if they do not periodically manage and process the nuclear material accounting data at each facility. To resolve these issues, KAERI developed a Web-based accounting system with the function of a near real-time accounting (NRTA) system to effectively and efficiently manage the nuclear material accounting data produced at the nuclear facilities and cope with a short notice inspection under the IS, called KASIS (KAeri Safeguards Information treatment System). The facility operators must input the accounting data on the inventory changes, which are the transfers of nuclear materials among the nuclear facilities and the chemical/physical composition changes, into the KASIS. KAERI also established an RFID system for controlling and managing the transfer of nuclear material and/or radioactive materials between the nuclear facilities for the purpose of nuclear safety management, and developed the nuclear material accounting system with the functions of inventory management of nuclear material at the facility level.

  8. Status of the Decommissioning Project Management Information System Development of KAERI in 2015

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Hyung Gon; Park, Seungkook; Park, Heeseong; Song, Chanho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Various information systems have been developed and used at decommissioning sites for planning a project, record keeping for a post management and cost estimation. KAERI is the only one expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR-1 and 2 and UCP (Uranium Conversion Plant) decommission. KRR-1 and KRR-2 are TRIGA MARK type of research reactor which were constructed worldwide. Hence, there are many chance to use decommissioning experiences and data when other TRIGA MARK type of research reactors start to decommission. KAERI DPMIS stands for Decommissioning Project Management Information System, which is aiming to re-use of data effectively. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DPMIS application program, which is going to be an important mile stone of decommission industry in Korea. User friendly graphical interface and lots of actual data let people well understood on decommission planning. It is expected that continuous effort and funds will be delivered to this research.

  9. The Status of Development on a Web-Based Nuclear Material Accounting System at KAERI

    International Nuclear Information System (INIS)

    The Integrated Safeguards (IS) has been applied to 10 nuclear facilities and 1 location outside facility (LOF) at the Korea Atomic Energy Research Institute (KAERI) since July 2008. One of the major changes in the implementation of safeguards under the IS is to apply the concept of a Random Interim Inspection (RII) instead of an interim inspection. The RII plan is notified within a few hours under the IS. It is thus difficult for facility operators to prepare the inspection documents within a short time if they do not periodically manage and process the nuclear material accounting data at each facility. To resolve these issues, KAERI developed a Web-based accounting system with the function of a near real-time accounting (NRTA) system to effectively and efficiently manage the nuclear material accounting data produced at the nuclear facilities and cope with a short notice inspection under the IS, called KASIS (KAeri Safeguards Information treatment System). The facility operators must input the accounting data on the inventory changes, which are the transfers of nuclear materials among the nuclear facilities and the chemical/physical composition changes, into the KASIS. KAERI also established an RFID system for controlling and managing the transfer of nuclear material and/or radioactive materials between the nuclear facilities for the purpose of nuclear safety management, and developed the nuclear material accounting system with the functions of inventory management of nuclear material at the facility level

  10. Validation of WIMS-AECL/(MULTICELL)/RFSP system by the results of phase-B test at Wolsung-II unit

    Energy Technology Data Exchange (ETDEWEB)

    Hong, In Seob; Min, Byung Joo; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-03-01

    The object of this study is the validation of WIMS-AECL lattice code which has been proposed for the substitution of POWDERPUFS-V(PPV) code. For the validation of this code, WIMS-AECL/(MULTICELL)/RFSP (lattice calculation/(incremental cross section calculation)/core calculation) code system has been used for the Post-Simulation of Phase-B physics Test at Wolsung-II unit. This code system had been used for the Wolsong-I and Point Lepraeu reactors, but after a few modifications of WIMS-AECL input values for Wolsong-II, the results of WIMS-AECL/RFSP code calculations are much improved to those of the old ones. Most of the results show good estimation except moderator temperature coefficient test. And the verification of this result must be done, which is one of the further work. 6 figs., 15 tabs. (Author)

  11. Qualification of the WIMS lattice code, for the design, operation and accident analysis of nuclear reactors

    International Nuclear Information System (INIS)

    A basic problem in nuclear reactor physics in that of the description of the neutron population behaviour in the multiplicative medium of a nuclear fuel. Due to the magnitude of the physical problem involved and the present degree of technological evolution regarding computing resources, of increasing complexity and possibilities, the calculation programs or codes have turned to be a basic auxiliary tool in reactor physics. In order to analyze the global problem, several aspects should be taken into consideration. The first aspect to be considered is that of the availability of the necessary nuclear data. The second one is the existence of a variety of methods and models to perform the calculations. The final phase for this kind of analysis is the qualification of the computing programs to be used, i.e. the verification of the validity domain of its nuclear data and the models involved. The last one is an essential phase, and in order to carry it on great variety of calculations are required, that will check the different aspects contained in the code. We here analyze the most important physical processes that take place in a nuclear reactor cell, and we consider the qualification of the lattice code WIMS, that calculates the neutronic parameters associated with such processes. Particular emphasis has been put in the application to natural uranium fuelled reactor, heavy water cooled and moderated, as the Argentinean power reactors now in operation. A wide set of experiments has been chosen: a.-Fresh fuel in zero-power experimental facilities and power reactors; b.-Irradiated fuel in both types of facilities; c.-Benchmark (prototype) experiments with loss of coolant. From the whole analysis it was concluded that for the research reactors, as well as for the heavy water moderated power reactors presently operating in our country, or those that could operate in a near future, the lattice code WIMS is reliable and produces results within the experimental values and

  12. Performance Analysis and Test on the KAERI Devised Spacer Grids for PWRs

    Science.gov (United States)

    Song, Kee-Nam; Lee, Soo-Bum

    Spacer grid which is one of the most important structural components in a pressurized light water reactor fuel assembly supports the fuel rods laterally and vertically. Based on design experiences and by scrutinizing the design features of advanced nuclear fuels and the international patents of spacer grids, KAERI has devised its own spacer grid shapes and acquired patents. In this study, a performance evaluation on two new spacer grid shapes devised by KAERI was carried out from mechanical/structural and thermohydraulic view points. And also a performance evaluation on two commercial spacer grid shapes was carried out for the sake of a comparison. The comparisons included the spring characteristics, fuel rod vibration characteristics, fretting wear resistance, impact strength characteristics, CHF enhancement, and pressure drop level of the spacer grid shapes. The comparison results have shown that the performances of the new spacer grid shapes are better or at least not worse than those of the commercial spacer grid shapes.

  13. Blasting Impact by the Construction of an Underground Research Tunnel in KAERI

    International Nuclear Information System (INIS)

    The underground research tunnel, which is under construction in KAERI for the validation of HLW disposal system, is excavated by drill and blasting method using high-explosives. In order not to disturb the operation at the research facilities such as HANARO reactor, it is critical to develop a blasting design , which will not influence on the facilities, even though several tens of explosives are detonated almost simultaneously. To develop a reasonable blasting design, a test blasting at the site should be performed. A preliminary analysis for predicting the expected vibration and noise by the blasting for the construction of the underground research tunnel was performed using a typical empirical equation. From the study, a blasting design could be developed not to influence on the major research facilities in KAERI. For the validation of the blasting design, a test blasting was carried out at the site and the parameters of vibration equation could be determined using the measured data during the test blasting. Using the equation, it was possible to predict the vibration at different locations at KAERI and to conclude that the blasting design would meet the design criteria at the major facilities in KAERI. The study would verify the applicability of blasting method for the construction of a research tunnel in a rock mass and that would help the design and construction of large scale underground research laboratory, which might be carried out in the future. It is also meaningful to accumulate technical experience for enhancing the reliability and effectiveness of the design and construction of the HLW disposal repository, which will be constructed in deep underground by drill and blasting technique

  14. Proceedings of 2005 JAEA-KAERI joint seminar on advanced irradiation and PIE technologies

    International Nuclear Information System (INIS)

    In this seminar, total participants of over 100 were jointed from JAEA, KAERI, Hanyang University, Chungnam National University, Kyung Hee University, Oarai Branch of Institute for Materials Research (IMR) of Tohoku University, Nippon Nuclear Fuel Development Co., Ltd., Nuclear Development Corporation and others. The technical development and experimental data on the irradiation test and PIE were aggressively discussed in this seminar. Contributed presentations were 35 in three sessions; Current status and future program on irradiation test and PIE (10 presentations), Development of irradiation and PIE technologies (15 presentations) and Evaluation of irradiation and PIE data (10 presentations). Development of instrumented capsule technologies for HANARO irradiation, current PIE activities in each hot laboratory of both countries, development of irradiation capsules in JMTR for the Irradiation Assisted Stress Corrosion Cracking (IASCC) study, development of irradiation and PIE techniques for the safety research on the high burnup fuel, utilization plan of JOYO and development of MOX fuel containing americium have been widely noticed as topic items on irradiation and PIE technologies. This proceedings is containing papers presented in the 2005 JAEA-KAERI Joint Seminar. It also indicates the current status of the aggressive information exchange activity on two fields of irradiation test and PIE technologies between JAEA and KAERI under the Arrangement for the Implementation of Cooperative Research Program mentioned above. The 35 of the presented papers are indexed individually. (J.P.N.)

  15. A study for developing training courses of the nuclear training center -with priority given to the training goals of KAERI-

    International Nuclear Information System (INIS)

    The final goal of this project, which covers 3 years (from 1992 to 1994), is to develop personnel training courses of the Korea Atomic Energy Research Institute (KAERI) and to derive the most desirable training system therefrom. To achieve this final goal successfully the first year's research was designed and has been carried on; firstly, to analyze the on-going issues and what kind of reform measures should be introduced to both the input and conversion processes of KAERI to efficiently achieve the organization goals, secondly, to derive personnel training goals of KAERI based on the analyses. First, this study introduced the viewpoint of systems approach for organization analysis, and defined that the productivity of an organization mainly depends on manpower quality of the input section and efficiency of the conversion process. Next, general organization theories and characteristics of research and development organization were studied, and derived that in research and development organization the expertise of a specialist should be regarded as the main value rather than his position, and the atmosphere should be human-centered, being free and democratic rather than authoritarian. And the study emphasizes more flatted structure of organization, necessity of sense of Management By Objectives (MBO), future planning capability, quality of manager with democratic leadership as criteria for the analysis of research and development organization. Finally, analyzing organization structure and behavior of KAERI based on the criteria, the study derived the ends-means hierarchy of personnel training of KAERI and discussed the necessity of organization reform of KAERI. (Author)

  16. The development of KAERI management information system -First year: The development of manpower information management system-

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Shin Bok; Huh, Young Hwan; Lee, Jong Bok; Park, Soo Jin; Lee, Young Jae; Park, Yeon Sik; Jang, Deok Kyu; Park, Seung Deok; Kim, Jong Myeong [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1991-12-01

    The purpose of this report is to describe the implementation of the management information system for manpower. This job is the first year`s for development KAERI management information system. It is important to properly manage a manpower to cope with the external circumstances promptly and to maximize the productivity of the organization. This report aims at basic management of manpower and uses multimedia to keep abreast with the times and introduces the concept of GUI (Graphic User Interface) to user for ease access. (Author).

  17. The development of KAERI management information system -First year: The development of manpower information management system-

    International Nuclear Information System (INIS)

    The purpose of this report is to describe the implementation of the management information system for manpower. This job is the first year's for development KAERI management information system. It is important to properly manage a manpower to cope with the external circumstances promptly and to maximize the productivity of the organization. This report aims at basic management of manpower and uses multimedia to keep abreast with the times and introduces the concept of GUI (Graphic User Interface) to user for ease access. (Author)

  18. Analysis of climate change scenarios in an olive orchard microcatchment in Spain using the model WIMMED

    Science.gov (United States)

    Guzmán, Enrique; Aguilar, Cristina; José Polo, María; Taguas, Encarnación V.

    2015-04-01

    Olive orchards constitute traditional systems in the Mediterranean Basin. In Andalusia, Southern Spain, more than 1.5Mha are dedicated to olive crop land use, which represent a production of 1Mt of olive oil per year. This is a strategic economic sector with environmental and social relevance. In the context of climate change in Andalusia, the Intergovernmental Panel on Climate Change has highlighted that an increase of temperatures and rainfall intensities as well as the reduction of cumulated rainfall might be expected. This may mean serious detrimental economic and environmental risks associated to floods and the reduction of available water resources which would be convenient to quantify. The objective of this work is to analyse the rainfall-runoff relationships in an olive orchard catchment by the application of the distributed hydrological model WIMMED (Herrero et al., 2009) simulating the effects of climate change, with a special emphasis on extreme events. Firstly, the model was calibrated and validated with 9 maximum annual events of a datasets from 2005-2012 obtained in an olive orchard catchment in Spain (Taguas et al., 2010). In this stage, only the saturated hydraulic conductivity and soil moisture in saturation were adjusted after a sensitivity analysis where 68 simulations were carried out. A good agreement was obtained between observed and simulated hydrographs. The mean errors and the root mean square errors were 0.18 mm and 2.19 mm for the calibration and 0.18 and 1.94 mm, for the validation. Finally, the catchment response to the increase of intensity and temperature and the reduction of cumulated rainfall were simulated for the maximum event of the series. The results showed a rise of 11% of the runoff coefficient quantifying the possible impact of climate change. REFERENCES Herrero J, Polo M., Moñino A., Losada MA (2009). An energy balance snowmelt model in a Mediterranean site. J. Hydrol. 371, pp. 98-107 Taguas EV, Peña A, Ayuso JL, Yuan Y

  19. Comparison of MCNP4B and WIMS-AECL calculations of coolant-void-reactivity effects for uniform lattices of CANDU fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kozier, K.S. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    1999-07-01

    This paper compares the results of coolant-void reactivity (CVR) reactor-physics calculations performed using the Monte Carlo N-particle transport code, MCNP version 4B, with those obtained using Atomic Energy of Canada Limited's (AECL's) latest version of the Winfrith improved multigroup scheme (WIMS) code, WIMS-AECL version 2-5c. Cross sections derived from the evaluated nuclear data file version B-VT (ENDF/B-VI) are used for both the WIMS-AECL and MCNP4B calculations. The comparison is made for uniform lattices at room temperature containing either fresh natural uranium or mixed oxide (MOX) 37-element CANDU fuel. The MOX fuel composition corresponds roughly to that of irradiated CANDU fuel at a burnup of about 4500 MWd/tU. The level of agreement between the CVR predictions of WIMS-AECL and MCNP4B is studied as a function of lattice buckling (a measure of the curvature of the neutron-flux distribution) over the range from 0.0 to 4.1 m{sup -2}. For the cases studied, it is found that the absolute keff values calculated by WIMS-AECL are higher than those of MCNP4B by several mk (1 mk is a change of 0.001 in keff), amounts that depend on the fuel type being modelled and the particular cross-section data used. However, the agreement between WIMS-AECL and MCNP4B is much better for the CVR (i.e., the {delta}keff on coolant voiding), and is relatively insensitive to the fuel type. (author)

  20. Comparison of MCNP4B and WIMS-AECL calculations of coolant-void-reactivity effects for uniform lattices of CANDU fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kozier, K.S

    1999-05-01

    This paper compares the results of coolant-void reactivity (CVR) reactor-physics calculations performed using the Monte Carlo N-particle transport code, MCNP version 4B, with those obtained using Atomic Energy of Canada Limited's (AECL's) latest version of the Winfrith improved multigroup scheme (WIMS) code, WIMS-AECL version 2-5c. Cross sections derived from the evaluated nuclear data file version B-VI (ENDF/B-VI) are used for both the WIMS-AECL and MCNP4B calculations. The comparison is made for uniform lattices at room temperature containing either fresh natural uranium or mixed oxide (MOX) 37-element CANDU fuel. The MOX fuel composition corresponds roughly to that of irradiated CANDU fuel at a burnup of about 4500 MWd/tU. The level of agreement between the CVR predictions of WIMS-AECL and MCNP4B is studied as a function of lattice buckling (a measure of the curvature of the neutron-flux distribution) over the range from 0.0 to 4.1 m{sup -2} . For the cases studied, it is found that the absolute k values calculated by WIMS-AECL are higher than those of MCNP4B by several mk (1 mk is a change of 0.001 in k), amounts that depend on the fuel type being modelled and the particular cross-section data used. However, the agreement between WIMS-AECL and MCNP4B is much better for the CVR (i.e., the {delta}k on coolant voiding), and is relatively insensitive to the fuel type. (author)

  1. Evaluation for KAERI 6x6 Reflood Test Using TRACE Code

    International Nuclear Information System (INIS)

    The Safety and Performance Analysis Code for Nuclear Power Plants (SPACE) has been developed by the Korean nuclear industries. The SPACE is a best-estimated two phase three-field thermal-hydraulic analysis code to analyze the performance of pressurized water reactors and is under a licensing review by the regulatory body. For a new code, various SET/IET assessments should be performed to identify the accuracy of code/model. Among the SETs to evaluate the effect of reflood heat transfer, the KAERI 6x6 reflood test was evaluated by the only SPACE code. The 6x6 reflood test facility (ATHER) has been constructed at KAERI to investigate quantitatively the mechanism of reflood phenomena during the reflood phase of LBLOCA and to evaluate the effect of droplet flow on core cooling during the reflood phase. In this study, the ATHER test was assessed independently by the TRACE code. The objectives of this study are to identify the prediction capability of TRACE code and to utilize the prediction results for the review of SPACE code. The TRACE V5.0 patch 4 was used in this calculation. The calculation for the 6x6 reflood test (ATHER) was performed with the TRACE code. From the calculation results, the major behavior of the wall temperature could be predicted well. However, the further study will be needed to resolve the differences of quenching behaviors and to understand the reflood heat transfer model of TRACE code

  2. KAERI/BNFL/COGEMA joint cooperation on environmentally friendly nuclear fuel cycle option study in Korea

    International Nuclear Information System (INIS)

    Through the project of 'KAERI/BNFL/COGEMA joint cooperation on environmentally friendly nuclear fuel cycle option study in Korea', the followings were studied. 1. Evaluation of environmental friendliness and of economic feasibility on the thermal neutron reactor type nuclear fuel cycle. 2. Evaluation of environmental friendliness on the future type nuclear fuel cycle. 3. Perspective of middle and long term electric power supply and of nuclear power plant constructionstes, development of device for the pretreatment of solid wastes, treatment of DU waste, analysis of the contaminated soil waste, induction of optimum conditions of coring from the 200L flexible waste forms, and long-term leaching test of 200L drum's waste form for the development of waste treatment and volume reduction technology, the characterization of waste formsenerated at KAERI. Therefore, radwastes are disposed of in a disposal site as solidified waste forms for its complete isolation from the human environment. The physicochemical properties of waste forms and the radionuclide concentration in waste forms should be evaluated for the radiological and structural safety of a disposal site, radionuclide type and solidification matrix, and it is difficult to carry out tests(for example, compressive strength, leaching rate, etc)with a full-scale waste forms. The waste classification and acceptance criteria is the result of technology development for characterization of waste and solidified waste forms. This treatment is carry out to low-cost and low-absorbed dose

  3. Chest Wall Thickness Measurements and the Dosimetric Implications for Male Radiation Workers at the KAERI

    International Nuclear Information System (INIS)

    Using ultrasound techniques, the Korea Atomic Energy Research Institute has measured chest wall thicknesses of a group of male workers at the Korea Atomic Energy Research Institute. A site-specific biometric equation has been developed for these workers. Chest wall thickness is an important modifier on lung counting efficiency. These data have been put into the perspective of the ICRP recommended dose limits for occupationally exposed workers:100 mSv in a 5-year period with a maximum of 50 mSv in any one year. For measured chest wall thicknesses of 1.9 cm to 4.1 cm and a 30 min counting time, the achievable MDAs for natural uranium in the KAERI lung counter vary from 5.75 mg to 11.28 mg. These values are close to, or even exceed, the predicted amounts of natural uranium that will remain in the lung (absorption type M and S) after an intake equal to the Annual Limit on Intake corresponding to a committed dose of 20 mSv. This paper shows that the KAERI lung counter probably cannot detect an intake of Type S natural uranium in a worker with a chest wall thickness equal to the average value (2.7 cm) under routine counting conditions

  4. Comparison of KAERI results on IAEA CRP phase4 benchmark problem for liquid metal fast reactor reactivity effects

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ki Bog; Jang, Jin Wook; Song, Hoon; Kim, Young Il [KAERI, Taejon (Korea, Republic of)

    2003-07-01

    IAEA Coordinated Research Project (CRP) proposed a benchmark problem in order to validate, verify and improve methodologies and computer codes used for the calculation of reactivity coefficients in fast reactors aiming at enhancing the utilization of plutonium and minor actinides. The prupose of this paper is to report the calculation results based on the K-CORE system developed by KAERI and to compare the results performed by the each paticipant for the IAEA CRP Phase 4 of BN-600 full mixed oxide (MOX) fueled core benchmark analyses. The K-CORE calculational methods employed in the benchmark analyses are explained. The benchmark results carried out by KAERI and the other particpants are collected and intercompared. According to comparison results, the k-eff and the fuel Doppler coefficients of KAERI shows a little bit higher than the other's values mainly due to using JEF 2.2 cross section data library. The fuel density coefficients and the effective delayed neutron fraction and the neutron lifetime show good agreement compared with the other participants' values. Even though the KAERI results for the steel Doppler, fuel density and sodium density coefficients, exists in the range of minimum and maximum values between the participants, there are big discrepancies in reactivity coefficients. So the prediction of reactivity coefficients requires further investigation.

  5. Plant application uncertainty evaluation of LBLOCA analysis using RELAP5/MOD3/KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Yong; Chung, Bub Dong; Hwang, Tae Suk; Lee, Guy Hyung; Chang, Byung Hoon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-06-01

    A practical realistic evaluation methodology to evaluate the ECCS performance that satisfies the requirements of the revised ECCS rule has been developed and this report describes the application of new REM to large break LOCA. A computer code RELAP5/MOD3/KAERI, which was improved from RELAP5/ MOD3.1 was used as the best estimated code for the analysis and Kori unit 3 and 4 was selected as the reference plant. Response surfaces for blowdown and reflood PCTs were generated from the results of the sensitivity analyses and probability distribution functions were established by using Monte-Carlo sampler for each response surface. This study shows that plant application uncertainty can be quantified and demonstrates the applicability of the new realistic evaluation methodology. (Author) 29 refs., 40 figs., 8 tabs.

  6. A Compton X-ray source based on a SC linac at KAERI

    Science.gov (United States)

    Bondarenko, A. V.; Han, Y. H.; Jeong, Y. U.; Lee, B. C.; Miginsky, S. V.; Park, S. H.

    2007-05-01

    A quasi-monochromatic X-ray source based on a KAERI SC linac system has been designed and is being manufactured now. 10 MeV 10 mA electron beam together with 20 W 1.06 μm laser beam will be used for 1.8 keV Compton X-ray generation with a few percentage of energy spread and 10 7 photons /s flux. A simple straight beamline was designed to deliver the electron beam with no degradation of its emittance and energy spread and to focus it to a proper size to produce the desired X-rays. We expect the first demonstration of 1.8 keV Compton X-ray generation in autumn 2006.

  7. A neutron guide installation status and its first performance test result at KAERI

    Science.gov (United States)

    Cho, S. J.; Cho, Y. G.; Lee, C. H.; Lee, K. H.; Kim, K. P.

    2011-04-01

    A neutron guide system that includes neutron guides, a main shutter, and a vacuum system was successfully installed at the HANARO research reactor of the Korea Atomic Energy Research Institute (KAERI) last year, and is now operating with 5 cold neutron instruments. The neutron flux and spectrum were measured by using gold wire and a disc chopper. The total measured neutron fluxes for various position are about 10-25% lower than the calculated fluxes, which is probably caused by neutron guide misalignment, larger gap between neutron guides, low reflectivity, imperfect cold neutron source data, and so on. But the measured neutron fluxes of the neutron guides are very high. The status of the neutron guide installation and its first performance test result is described in this paper.

  8. Construction of the 1 kJ Nd: glass laser facility at KAERI

    Science.gov (United States)

    Lim, C.; Hong, S.-K.; Ko, K.; Jin, J.-T.; Kim, M.; Yun, D.-H.; Li, L.-J.; Lee, D.-W.; Lee, K.-T.; Kim, C.-J.

    2008-05-01

    We report on the design and present status of a 1 kJ Nd:Glass laser facility for basic research on quantum engineering at KAERI (Korea Atomic Energy Research Institute). By applying a newly designed spatial filter with a serrated aperture, we improved the diffracted Gaussian spatial profile of an oscillator into a flat-top one. The laser system consists of 4 beam lines, each with the energies of more than 200 J at the nano-second regime. We measured the gain and spatial profiles of each amplification stage. A spectral shaping by a two-stage OPCPA (Optical Parametric Chirped Amplifier) for a pico-second front end was studied to compensate for gain narrowing in multi-stage amplifier chains.

  9. A Study on the Management of Intellectual Property for the Potential Markets of KAERI

    International Nuclear Information System (INIS)

    The intellectual property law of the Republic of South Africa is similar to that of Korea except for a few regulations. In Republic of South Africa, the rights of joint inventor are limited, there is no request for examination, and the allowance of patent is generally determined within 18 months from the application date. Risky patents or applications are not found in Republic of South Africa. However, KAERI needs ceaselessly to search and investigate patents or patent applications in Republic of South Africa. Finally, we propose to build a patent management team within an operation division to respond swiftly to possible market changes. The operation-oriented patent management team will efficiently secure competitive patents and effectively realize a profit from the competitive patents

  10. Joint KAERI/VAEC pre-possibility study on a new research reactor for Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Park, Cheol; Lee, B. C.; Chae, H. T.; Kim, H.; Lee, C. S.; Choi, C. O.; Jun, B. J. [KAERI, Taejon (Korea, Republic of); Vien, Luong Ba; Dien, Nguyen Nhi [Vietnam Atomic Energy Commission, Hanoi (Viet Nam)

    2004-05-01

    Based on the agreement on the technical cooperation for nuclear technology between Korea and Vietnam, a KAERI/VAEC joint study on the pre-possibility of a new research reactor for Vietnam has been carried out in the research reactor area from Nov. 2003 to May 2004. In this report, the results of the pre-possibility study on a new research reactor are described. The report presents the necessity of a new research reactor in Vietnam, and the desired performance requirements of the new research reactor if necessary. The major design characteristics of some existing research reactors and those under planning were also reviewed and the main characteristics which should be considered in selecting a new multipurpose research reactor for Vietnam were drawn. Some recommendations on the considerations for the next step of the feasibility study such as the project formulation, manpower requirements and international co-operation were also briefly touched upon.

  11. Development of a 14.5 GHz electron cyclotron resonance ion source at KAERI

    International Nuclear Information System (INIS)

    A 14.5 GHz electron cyclotron resonance ion source has been designed and fabricated at KAERI (Korea Atomic Energy Research Institute) to produce multi-charged ion beams (particularly C6+ ion beams) for medical applications. The magnet system has normal conductor solenoid coils and a permanent magnet hexapole. A welded tube with aluminium and stainless steel is used as an ECR plasma chamber to improve the production of secondary electrons. A klystron supplies microwave energy to the plasma. A movable beam extractor with an 8 mm aperture covers various ion species and charge numbers of the beam. Fabrication and initial experimental results on ECR plasma and beam extraction are discussed in this paper.

  12. Assessment of RELAP5/Mod3/KAERI using semiscale test S-06-3

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Yong; Choi, Han Rim; Chung, Bub Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-06-01

    This report presents the results of the RELAP5/MOD3/KAERI assessment utilizing a semi scale large break loss-of-coolant experiment Test S-06-3. Test S-06-3 is a 200% double ended cold break experiment performed in semi scale Mod-1 facility in 1987 for the purpose of investigating the thermal and hydraulic phenomena accompanying a hypothetical large break LOCA in a pressurized were reactor system. Through comparisons between data and best-estimate RELAP5 calculation, the capabilities of RELAP5 to calculate the large break LOCA accident were assessed. Emphasis was placed on the capability of the code to calculate break flow rates during system blowdown phase, emergency core cooling system injection bypass during refill phase, quenching during reflood phase, and the peak cladding temperature behavior throughout the whole experiment. (Author) 12 refs., 38 figs., 2 tabs.

  13. Joint KAERI/VAEC pre-possibility study on a new research reactor for Vietnam

    International Nuclear Information System (INIS)

    Based on the agreement on the technical cooperation for nuclear technology between Korea and Vietnam, a KAERI/VAEC joint study on the pre-possibility of a new research reactor for Vietnam has been carried out in the research reactor area from Nov. 2003 to May 2004. In this report, the results of the pre-possibility study on a new research reactor are described. The report presents the necessity of a new research reactor in Vietnam, and the desired performance requirements of the new research reactor if necessary. The major design characteristics of some existing research reactors and those under planning were also reviewed and the main characteristics which should be considered in selecting a new multipurpose research reactor for Vietnam were drawn. Some recommendations on the considerations for the next step of the feasibility study such as the project formulation, manpower requirements and international co-operation were also briefly touched upon

  14. The Neutronic And Power Distribution Calculations For Triga 2 MW Reactor Using WIMS-D/4 And Citation Codes

    International Nuclear Information System (INIS)

    . The neutronic calculation has been carried out for TRIGA 2 MW reactor. These included criticality flux and power distributions. Computer code Citation which solves 7-groups, 3-dimensional hexagonal geometry has been used. The multi groups-cross-section is generated by the WIMS-D/4 code.This 7-group-39x39x38-mesh-points problem takes about 90 minutes on the Pentium-133 MHz PC. The calculation of the initial core of TRIGA 2 MW reactor shows that the excess reactivity of the core is 7,8% and the thermal fluxes in the irradiation positions are between 1.0-2.9*1013n cm-2s-1. The results are about 10% deviate from those calculated by General Atomics. In the initial core, the highest power is produced in the C-9 position. The fuel element in this position produces 30.7 k W thermal power

  15. Modeling TRIGA reactor pulses using the STAR 3D nodal kinetics and WIMS-D4 codes

    International Nuclear Information System (INIS)

    A detailed three-dimensional (3D) time-dependent STAR nodal kinetics model coupled to a one-dimensional (1D) thermal-hydraulics WIGL model has been developed to describe and benchmark the peak power and pulse behavior of the Penn State University (PSU) Breazeale TRIGA reactor. Different core loading patterns were used for several TRIGA pulse tests with different reactivity insertion worths (1.5 dollar, 2.0 dollar, 2.5 dollar). The STAR nodal kinetics code and TRIGA model adequately simulates TRIGA pulses when group constants are generated from physics codes (i.e., WIMS-D4) that can accurately model the TRIGA uranium-zirconium-hydride fuel

  16. Mapping Fractures in KAERI Underground Research Tunnel using Ground Penetrating Radar

    Science.gov (United States)

    Baek, Seung-Ho; Kim, Seung-Sep; Kwon, Jang-Soon

    2016-04-01

    The proportion of nuclear power in the Republic of Korea occupies about 40 percent of the entire electricity production. Processing or disposing nuclear wastes, however, remains one of biggest social issues. Although low- and intermediate-level nuclear wastes are stored temporarily inside nuclear power plants, these temporary storages can last only up to 2020. Among various proposed methods for nuclear waste disposal, a long-term storage using geologic disposal facilities appears to be most highly feasible. Geological disposal of nuclear wastes requires a nuclear waste repository situated deep within a stable geologic environment. However, the presence of small-scale fractures in bedrocks can cause serious damage to durability of such disposal facilities because fractures can become efficient pathways for underground waters and radioactive wastes. Thus, it is important to find and characterize multi-scale fractures in bedrocks hosting geologic disposal facilities. In this study, we aim to map small-scale fractures inside the KAERI Underground Research Tunnel (KURT) using ground penetrating radar (GPR). The KURT is situated in the Korea Atomic Energy Research Institute (KAERI). The survey target is a section of wall cut by a diamond grinder, which preserves diverse geologic features such as dykes. We conducted grid surveys on the wall using 500 MHz and 1000 MHz pulseEKKO PRO sensors. The observed GPR signals in both frequencies show strong reflections, which are consistent to form sloping planes. We interpret such planar features as fractures present in the wall. Such fractures were also mapped visually during the development of the KURT. We confirmed their continuity into the wall from the 3D GPR images. In addition, the spatial distribution and connectivity of these fractures are identified from 3D subsurface images. Thus, we can utilize GPR to detect multi-scale fractures in bedrocks, during and after developing underground disposal facilities. This study was

  17. Investigation for the Fossil Embryo using Neutron Tomography at HANARO, KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Joo; Sim, Cheul Muu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Dong Hee [National Science Museum, Daejeon (Korea, Republic of); Grellet-Tinner, Gerald [The Field Museum, Chicago (United States)

    2012-05-15

    Neutron imaging technique is one of non-destructive method. It is similar to X-ray and g-ray methods in using the different attenuation characteristics depending on materials. However, there is great difference between them. The mass attenuation coefficients of X-ray and g- ray monotonically increase with the atomic number since they interact with electrons. Thus X-ray image method does not supply sufficient contrast between similar atomic numbers. On the other hand, that of thermal neutrons depends much on the nucleus not electrons. Especially thermal neutrons easily penetrate most of metals, while they are attenuated well by such materials as hydrogen, water, boron, gadolinium and cadmium. Because of these unique characteristics of neutron, neutron imaging technique has been utilized for NDT or researches for next power sources (fuel cell or Li-Ion battery). Recently, dinosaur egg was found at the Aptian. Albian Algui Ulaan Tsav site, Mongolia. In this study, we applied the neutron imaging technique to investigate dinosaur embryo at Neutron Radiography Facility of HANARO, KAERI

  18. Status of neutron beam facilities at HANARO and a thermal neutron guide project of KAERI

    International Nuclear Information System (INIS)

    After successful installation of cold neutron facilities at HANARO such as neutron guides, cold neutron source including cold neutron instruments, now 14 cold and thermal neutron spectrometers are operating, and 5 instruments are under commissioning. The neutron guides with complicated shapes placed in the beam plug and the main shutter also in the curved part were delivered by a guide provider but the rest guides such as the guides in the guide bunker and the guide hall area were fabricated by KAERI. All the guides are coated with M=2 supermirror having different cross-sections and curvatures were operating with a high performance, where 10 cold neutron spectrometers will open to outside users. For a planning of a new project called ‘thermal guide facilities development’, the neutron guide system design started late last year, which was carried out to optimize the layout of the instruments and to calculate the neutron flux at sample position. At this meeting, the simulation results of the thermal neutron guide beam lines, status of in-house neutron guide development and specifications of some instruments will be presented.

  19. Conceptual design study of an integrated pyro-process facility at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    You, Gil-Sung; Choung, Won-Myung; Lee, Eun-Pyo; Cho, Il-Je; Kwon, Kie-Chan; Hong, Dong-Hee; Lee, Won-Kyung; Ku, Jeong-Hoe [Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2009-06-15

    KAERI has been developing pyro-process facilities for a dry processing research of spent fuel about ten years since 1997. A hot cell facility, named the ACPF-Advanced spent fuel Conditioning Process Facility, for the demonstration of a head-end part of pyro-process was developed at November 2005. An inactive demonstration facility for the integrated pyro-process, named PRIDE-pyro-process Integrated inactive Demonstration, has been developing since 2007. The PRIDE facility consists of two cells: one is an air environment cell and another one is an argon environment cell. This facility includes several pyro-process equipment, such as a decladding/voloxidation device, a powder mixing device, an electro-reduction equipment, an electro-refining equipment, an electro-winning equipment, a Cd distillation equipment, a waste salt regeneration and solidification equipment, a salt distillation equipment, etc. In the cell and on the wall, some cell equipment, such as one cell crane, one BTDSM (Bridge Transported Dual arm Servo Manipulator), two HMSM (Horizontally Moving dual arm Servo Manipulator) will be also installed. This facility will be utilized to obtain the basic requirements for an engineering scale pyro-process facility in which the spent fuels from power reactors can be treated. (authors)

  20. First lasing of the KAERI millimeter-wave free electron laser

    Energy Technology Data Exchange (ETDEWEB)

    Lee, B.C.; Jeong, Y.U.; Cho, S.O. [Korea Atomic Energy Research Institute, Taejon (Korea, Democratic People`s Republic of)] [and others

    1995-12-31

    The millimeter-wave FEL program at KAERI aims at the generation of high-power CW laser beam with high efficiency at the wavelength of 3{approximately}10 mm for the application in plasma heating and in power beaming. In the first oscillation experiment, the FEL has lased at the wavelength of 10 mm with the pulsewidth of 10{approximately}30 {mu}s. The peak power is about 1 kW The FEL is driven by a recirculating electrostatic accelerator having tandem geometry. The energy and the current of the electron beam are 400 keV and 2 A, respectively. The FEL resonator is located in the high-voltage terminal and is composed of a helical undulator, two mesh mirrors, and a cylindrical waveguide. The parameters of the permanent-magnet helical undulator are : period = 32 mm, number of periods = 20, magnetic field = 1.3 kG. At present, with no axial guiding magnetic field only 15 % of the injected beam pass through the undulator. Transport ratio of the electron beam through the undulator is very sensitive to the injection parameters such as the diameter and the divergence of the electron beam Simulations show that, with unproved injection condition, the FEL can generate more than 50 kW of average power in CW operation. Details of the experiments, including the spectrum measurement and the recirculation of electron beam, are presented.

  1. Compton X-Ray Generation at the KAERI SC RF LINAC

    CERN Document Server

    Park, S H; Jeong, Y U; Lee, B C; Lee, K

    2005-01-01

    The KAERI SC RF linac with one 352 MHz cryomodule is routinely operating at 10 MeV. The maximum accelerating gradient achieved so far is about 7.7 MV/m and is expected to increase up to 9 MV/m, if thermal loss and/or vibration instability is sufficiently suppressed. As a next step, we plan to generate Compton X-rays using external lasers at the straight section, just after the SC linac. This beamline will be relocated to downstream next to undulator beamline for a FEL, when the recirculating beamline is built. In this presentation, we estimate the parameters of Compton X-rays at a given system and suggest the new scheme to increase the flux, or to generate fs X-ray pulses using electron beams with a few tens ps pulse duration, using an intense ultra-short laser. We discussed a coherent condition for Relativistic Nonlinear Thomson Scattered (RNTS) radiation (or Nonlinear Compton Scattered radiation).

  2. Status and Plans for the Daejeon Ion Accelerator Complex at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Huh, Sung-Ryul; Chang, Dae-Sik; Hwang, Churl-Kew; Jung, Bong-Ki; Jin, Jeong-Tae; Oh, Byung-Hoon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The Daejeon ion accelerator complex (DIAC) is being built at the Korea atomic energy research institute (KAERI) in order to fulfill an increasing demand for heavy ion beam facilities for various applications including biological and nanomaterial research. Based on linacs of the Tokai radioactive ion accelerator complex (TRIAC) given from the high energy accelerator research organization (KEK), Japan, the dedicated accelerators in the DIAC are designed to produce stable heavy ion beams with energies up to 1 MeV/u and beam currents up to 300 µA. In this article, status, plans, and some preliminary test results for the DIAC construction are presented and discussed. At present the full-power test of the IH2-4 linacs is limited by the multipacting. Based on the understanding of the multipacting characteristics, full-power test of all IH linacs will be finished soon. After that, full-power test of the RFQ linacs, the radiation shielding analysis, the beam tuning will be done until the end of this year.

  3. Mechanical Property and Oxidation Behavior of ATF cladding developed in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun-Gil; Kim, Il-Hyun; Jung, Yang-Il; Park, Dong-Jun; Park, Jung-Hwan; Park, Jeong-Yong; Koo, Yang-Hyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    To realize the coating cladding, coating material (Cr-based alloy) as well as coating technology (3D laser coating and arc ion plating combined with vacuum annealing) can be developed to meet the fuel cladding criteria. The coated Zr cladding can be produced after the optimization of coating technologies. The coated cladding sample showed the good oxidation/corrosion and adhesion properties without the spalling and/or severe interaction with the Zr alloy cladding from the various tests. Thus, it is known that the mechanical property and oxidation behavior of coated cladding concept developed in KAERI is reasonable for applying the ATF cladding in LWRs. At the present time various ATF concepts have been proposed and developing in many countries. The ATF concepts with potentially improved accident performance can be summarized to the coating cladding, Mo-Zr cladding, FeCrAl cladding, and SiCf/SiC cladding. Regarding the cladding performance, ATF cladding concepts will be evaluated with respect to the accident scenarios and normal operations of LWRs as well as to the fuel cladding fabrication.

  4. Rf System For The Industrial Linear Electron Accelerator At Kaeri (daejeon, Korea)

    CERN Document Server

    Arbuzov, V S; Evtushenko, Yu A; Gorniker, E I; Kenjebulatov, E K; Kondakov, A A; Krutikhin, S A; Kurkin, G Ya; Motygin, S V; Osipov, V N; Petrov, V M; Pilan, Andrey M; Popov, A R; Shteinke, A M; Tribendis, A G

    2004-01-01

    Budker Institute of Nuclear Physics has developed and produced RF generators, feeder lines and a control system for an industrial linear electron accelerator at Korean Atomic Energy Research Institute (KAERI, Daejeon, Korea). The accelerator is based on two superconducting RF cavities produced by CERN. Design energy of the accelerator is 10 MeV and design beam current is 10 mA. A 2 MeV injector for the accelerator was made by BINP earlier. Two-channel RF system of the accelerator operates at the frequency of 352 MHz in CW mode. Each channel has two-stage tetrode amplifier with output power of 50 kW, 100 W transistor preamplifier and the control system. Both tetrode stages have identical design. TH571B tetrode tubes produced by THALES (France) are used. Output power of 45 kW per channel was reached in an equivalent resistive load. Now BINP continues development of the accelerator. The energy of 11 MeV and the beam current of 1.9 mA were achieved. The amplitude of accelerating voltage was 4.5 MV in each cavity,...

  5. Surface Decontamination of System Components in Uranium Conversion Plant at KAERI

    International Nuclear Information System (INIS)

    A chemical decontamination process using nitric acid solution was selected as in-situ technology for recycle or release with authorization of a large amount of metallic waste including process system components such as tanks, piping, etc., which is generated by dismantling a retired uranium conversion plant at Korea Atomic Energy Research Institute (KAERI). The applicability of nitric acid solution for surface decontamination of metallic wastes contaminated with uranium compounds was evaluated through the basic research on the dissolution of UO2 and ammonium uranyl carbonate (AUC) powder. Decontamination performance was verified by using the specimens contaminated with such uranium compounds as UO2 and AUC taken from the uranium conversion plant. Dissolution rate of UO2 powder is notably enhanced by the addition of H2O2 as an oxidant even in the condition of a low concentration of nitric acid and low temperature compared with those in a nitric acid solution without H2O2. AUC powders dissolve easily in nitric acid solutions until the solution pH attains about 2.5 ∼ 3. Above that solution pH, however, the uranium concentration in the solution is lowered drastically by precipitation as a form of U3(NH3)4O9 . 5H2O. Decontamination performance tests for the specimens contaminated with UO2 and AUC were quite successful with the application of decontamination conditions obtained through the basic studies on the dissolution of UO2 and AUC powders

  6. Investigation for the Fossil Embryo using Neutron Tomography at HANARO, KAERI

    International Nuclear Information System (INIS)

    Neutron imaging technique is one of non-destructive method. It is similar to X-ray and g-ray methods in using the different attenuation characteristics depending on materials. However, there is great difference between them. The mass attenuation coefficients of X-ray and g- ray monotonically increase with the atomic number since they interact with electrons. Thus X-ray image method does not supply sufficient contrast between similar atomic numbers. On the other hand, that of thermal neutrons depends much on the nucleus not electrons. Especially thermal neutrons easily penetrate most of metals, while they are attenuated well by such materials as hydrogen, water, boron, gadolinium and cadmium. Because of these unique characteristics of neutron, neutron imaging technique has been utilized for NDT or researches for next power sources (fuel cell or Li-Ion battery). Recently, dinosaur egg was found at the Aptian. Albian Algui Ulaan Tsav site, Mongolia. In this study, we applied the neutron imaging technique to investigate dinosaur embryo at Neutron Radiography Facility of HANARO, KAERI

  7. KAERI's technology development program of chemical decontamination for nuclear power reactors

    International Nuclear Information System (INIS)

    The activated corrosion products formed on the internal surface of primary coolant system of nuclear power plants can be removed by chemical decontamination. Dilute chemical decontamination method is widely used in consideration of keeping base metal integrity and producing relatively small amount of resulting radwastes. The application of chemical decontamination to PWRs is limited at present mainly to the channel heads of steam generators, but a growing necessity of entire NSSS decontamination is expected to accelerate the development and demonstration of the technology so that the commercial application of the technology will be realized in early 1990s. In Korea, nine nuclear power plants of PWR type except one will be available by 1989. The first chemical decontamination of the steam generator channel head of this nuclear power plant was done in 1984 by a foreign technology. KAERI's chemical decontamination technology development program funded by the Ministry of Science and Technology was started in 1983 to establish the technical guidelines and criteria and to obtain the technical self reliance. It is described. (Kako, I.)

  8. SNU-KAERI Degree and Research Center for Radiation Convergence Sciences

    International Nuclear Information System (INIS)

    In this study, we tried to establish and perform the demonstrative operation of the 'Degree and Research Center for Radiation Convergence Sciences' to raise the Korea's technology competitiveness. As results of this project we got the successful accomplishment as below: 1. Operation of Degree and Research Center for Radiation Convergence Sciences and establishment of expert researcher training system Ο Presentation of an efficient model for expert researcher training program through the operation of university-institute collaboration courses by combining of Graduate course and DRC system. Ο Radiation Convergence Sciences major is scheduled to be established in 2013 at SNU Graduate School of Convergence Science and Technology Ο A big project for research, education, and training of radiation convergence science is under planning 2. Establishment and conduction of joint research by organization of radiation convergence research consortium · Joint research was conducted in close connection with the research projects of researchers participating in this DRC project (44 articles published in journals, 6 patents applied, 88 papers presented in conferences) · The resources of the two organization (SNU and KAERI), such as research infrastructure (hightech equipment and etc), manpower (professor/researcher), and original technology and know how were utilized to conduct the joint research and to establish the collaboration system of the two organizations

  9. Assessment of the KAERI 6*6 reflood experiment using the SPACE code

    International Nuclear Information System (INIS)

    Nuclear industries in Korea are developing the nuclear safety analysis code named SPACE (Safety and Performance Analysis Code) which is based on a multi-dimensional, two-fluid, three-field model for a licensing application of pressurized water reactors. A reflood heat transfer phenomena can be predicted with using a general wall heat transfer model or a separate reflood heat transfer model of the SPACE code based on a user option. The reflood heat transfer package takes into account the two-dimensional heat conduction effects near the quench fronts. This paper briefly introduces the heat transfer models of the SPACE code regarding the reflood heat transfer phenomena, and the preliminary assessment results against KAERI 6*6 reflood heat transfer experiments using the general film boiling and the reflood heat transfer models. The objectives of these assessments are to examine the preliminary prediction capabilities of the SPACE code against the reflood phenomena, and to suggest future directions for improvement. Both the general wall heat transfer and the reflood heat transfer models of the SPACE code predicts reasonably the wall temperature behavior and quenching time. However, for a high reflooding velocity, the SPACE code showed slightly earlier quenching than the experiment because of a faster water accumulation in the test section. Thus, physical models such as droplet entrainment, interfacial drag, and droplet diameter should be checked and improved for the high flooding rates. (authors)

  10. Proceedings of 2012 JAEA/KAERI Joint Seminar on Advanced Irradiation and PIE Technologies; March 28-30, 2012, Mito, Japan

    OpenAIRE

    石原 正博; 石塚 悦男; 鈴木 雅秀

    2012-01-01

    Under the "Arrangement for Corporation in the field of peaceful uses of Nuclear Energy between the Japan Atomic Energy Agency (JAEA) and the Korean Atomic Energy Research Institute (KAERI)", the 2012 JAEA/KAERI Joint Seminar on Advanced Irradiation and PIE (post-irradiation examination) Technologies has been held at Mito, Japan from March 28 to 30, 2012. This triennial seminar is the seventh in series of bilateral exchange of irradiation and PIE technologies and research reactor management. S...

  11. Modelling of 28-element UO{sub 2} flux-map critical experiments in ZED-2 using WIMS9A/PANTHER

    Energy Technology Data Exchange (ETDEWEB)

    Sissaoui, M.T.; Kozier, K.S.; Labrie, J.P. [Atomic Energy of Canada Limited (Canada)

    2011-07-01

    The accuracy of WIMS9A/PANTHER in modelling D{sub 2}O-moderated, and H{sub 2}O- or air-cooled, doubly heterogeneous lattices of fuel clusters has been demonstrated using 28-element UO{sub 2} flux-map critical experiments in the ZED-2 facility. Presented here are the predicted k{sub eff} values, coolant void reactivity biases, and the radial and axial flux shapes.

  12. Graphic Design and the Edges of Common Sense. Thinking about design through the conflicting approaches of Wim Crouwel and Jan van Toorn

    OpenAIRE

    Kortteinen, Tuomas

    2015-01-01

    This thesis is an attempt to define two contrasting approaches to graphic design practice and explain the reasoning behind their differing perspectives. The starting point and main subject matter is the public debate between Wim Crouwel and Jan van Toorn that occurred in 1972 and continued in different forms for the following decade. The point of departure for the thesis is that public debates in general, and this one in particular, offer an invaluable view of the implicit assumptions th...

  13. Development of safeguards technology for lab-scale advanced fuel cycle facility at KAERI

    International Nuclear Information System (INIS)

    KAERI (Korea Atomic Energy Research Institute) has been developing the DUPIC (Direct Use of PWR spent fuel in CANDU) fuel cycle and ACP (Advanced Spent Fuel Conditioning Process) technology for the purpose of spent fuel management. A safeguards system has been applied to R and D process for fabricating DUPIC fuel directly with PWR spent fuel material. Safeguards issues to be resolved were identified in the areas such as international cooperation on handling foreign origin nuclear material, technology development of operator's measurement system of bulk handling process of spent fuel material, and built-in C/S system for independent verification of material flow. All those safeguards issues have been finally resolved. The lab-scale DUPIC facility (DFDF) safeguards system was successfully established under the international cooperation program. The ACP has been under development at KAERI since 1997 to tackle the problem of the accumulation of the spent fuel. The concept is to convert the spent oxide fuel into a metallic form in a high temperature molten salt in order to reduce the heat power, volume, and radioactivity of the spent fuel. The main objective of the ACP is to treat the PWR spent fuel for a long-term storage and eventual disposal in a proliferation resistant and cost effective way. Moreover, the electrolytic reduction method of the ACP can contribute to the innovative nuclear energy system as a key technology for the preparation of the metallic fuel. Since the inactive tests of the ACP have been successfully implemented to confirm the validity of the electrolytic reduction technology, a lab-scale hot test will be undertaken in the ACP facility (ACPF) to validate the concept. Based on the results of a safeguards implementation at DFDF hot cell, the reference safeguards design conditions are established for the ACPF. Basically, the nuclear material accounting will be performed by ASNC (ACP Safeguards Neutron Counter), which is the same concept as the

  14. R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyung Min; Cho, Jae Wan; Choi, Young Soo; Eom, Heung Seup; Seo, Yong Chil; Shin, Hoch Ul; Lee, Sung Uk; Kim, Chang Hoi; Jeong, Seung Ho; Kim, Seung Ho [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    equipped with various tools allowing it to scour surfaces, scoop samples and vacuum sludge. To perform cleanup tasks, they built Workhorse that featured system redundancy and had a boom extend able to reach high places, but it was never used because it had too many complexities and to clean and fix. While remote robotics technology has proven to remove the human from the radioactive environment, it is also difficult to make it useful because it may requires skill about remote control and obtaining remote situation awareness regardless of the actual task. The efficiency of the human robot interaction is very important to obtain the overall goal for the emergency response in timely manner. It would be a bottle neck to apply the robotic technology for carrying the emergency response in NPP. Simple remote operation schemes are not adequate, more intelligent autonomous operation schemes are required to enhance the effectiveness of robots for the emergency response. KAERI has been developing various robotic systems for nuclear power plants over than 20 years after the Chernobyl accident. But the majority of the developed robotic systems is for the inspection and maintenance of nuclear power plants during their outage periods. Based on the lessons learned from the Fukushima accident, KAERI has planned R and D projects for developing remote response technologies really applicable in emergency situations of nuclear facilities. This paper presents the R and D strategy to achieve real usability and the purpose and research activity plans of on going three projects derived from the strategy.

  15. R and D strategy on remote response technology for emergency situations of nuclear facilities in KAERI

    International Nuclear Information System (INIS)

    it to scour surfaces, scoop samples and vacuum sludge. To perform cleanup tasks, they built Workhorse that featured system redundancy and had a boom extend able to reach high places, but it was never used because it had too many complexities and to clean and fix. While remote robotics technology has proven to remove the human from the radioactive environment, it is also difficult to make it useful because it may requires skill about remote control and obtaining remote situation awareness regardless of the actual task. The efficiency of the human robot interaction is very important to obtain the overall goal for the emergency response in timely manner. It would be a bottle neck to apply the robotic technology for carrying the emergency response in NPP. Simple remote operation schemes are not adequate, more intelligent autonomous operation schemes are required to enhance the effectiveness of robots for the emergency response. KAERI has been developing various robotic systems for nuclear power plants over than 20 years after the Chernobyl accident. But the majority of the developed robotic systems is for the inspection and maintenance of nuclear power plants during their outage periods. Based on the lessons learned from the Fukushima accident, KAERI has planned R and D projects for developing remote response technologies really applicable in emergency situations of nuclear facilities. This paper presents the R and D strategy to achieve real usability and the purpose and research activity plans of on going three projects derived from the strategy

  16. Design of an engineering scale off-gas trapping system at KAERI

    International Nuclear Information System (INIS)

    KAERI has been developing a high temperature voloxidation process as a head-end process for pyroprocessing technology. This process may remove volatile fission products (Kr, H-3, C-14, I-129 etc.) and other semi-volatiles (Cs, Tc, Te, Mo etc.) that are problematic in the main pyroprocess. Engineering off-gas treatment system was designed to recover the primary semi-volatile products (Cs, Tc, Te, Mo, I, etc.) released from simulated reagents during the high temperature voloxidation process. The off-gas trapping system will trap selectively gaseous nuclides evolved from high temperature voloxidation process, this will also reduce the high level waste due to the separation of Cs. This paper describes design of the off-gas treatment systems for high temperature voloxidation process. Design of an engineering-scale semi-volatile trapping system of 50 kg-SF/batch was done. The gaseous waste arising for off-gas trapping system was estimated considering the release rate of each target fission product. Each unit process in the trapping system is arranged to effectively remove the species of interest by considering the chemical properties of the target fission products to be trapped. Cs and Rb are trapped on a fly ash filter at around 900degC. Tc(Re), Te, Se, and Mo on a calcium filter are trapped at about 700degC, and I on a AgX is trapped at about 250degC. Off-gas trapping system was designed based on the design requirements such as trapping media, fission products to be trapped, design temperatures of the trapping units, optimum operation temperatures and specifications of the filters. Off-gas trapping system was also designed based on the design requirements such as remote operability, accessibility, and flexibility of instrument, separability of trapping basket, material of instrument. (author)

  17. KAERI Activities on the Cooling Performance of Ex-vessel Core Catcher

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Kwang Soon; Park, Rae Joon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Wi, Kyung Jin [Chungnam National University, Daejeon (Korea, Republic of); Thanh, Thuy Nguyen Thi [University of Science and Technology, Daejeon (Korea, Republic of)

    2014-10-15

    the integrity of the ex-vessel core catcher system. KAERI has performed various researches to validate the cooling performance of an ex-vessel core catcher. First, a scaling analysis was performed to design the scaled-down experimental facility and maintain the characteristics of the real natural circulation flow by solving the natural circulation flow loop equation for the cooling channel in the ex-vessel core catcher. Second, boiling-induced natural circulation flow experiments in the cooling channels of the ex-vessel core catcher were investigated. Finally, a new correlation was developed to estimate the natural circulation mass flow rate with the inclined downward facing heating surface. KAERI has performed various researches to validate the cooling performance of the ex-vessel core catcher. First, the scaling analysis was performed to design the scaled-down experimental facility and maintain the characteristics of the real natural circulation flow by solving the natural circulation flow loop equation for the cooling channel in the ex-vessel core catcher. Secondly, boiling-induced natural circulation flow experiments in the cooling channels of the ex-vessel core catcher were investigated. And finally, a new correlation has been developed to estimate the natural circulation mass flow rate with the inclined downward facing heating surface. The circulation mass flux, the quality, and void fraction at the exit of the cooling channel in the experimental facility with the selected orifice coincided exactly with the prototypic core catcher system even though the different void fraction models were applied. In conclusion, a scaling analysis methodology for the natural circulation flow loop was proposed and successfully verified. In the experiment, the effect of the water level, heat flux, heat flux distribution, core catcher vertical side-wall length, and coolant temperature were studied. A natural circulation test was carried out in two stages, one with freely increasing

  18. Recent Research Status on the Microbes in the Radioactive Waste Disposal and Identification of Aerobic Microbes in a Groundwater Sampled from the KAERI Underground Research Tunnel(KURT)

    International Nuclear Information System (INIS)

    In this report, a comprehensive review on the research results and status for the various effects of microbes in the radioactive waste disposal including definition and classification of microbes, and researches related with the waste containers, engineered barriers, natural barriers, natural analogue studies, and radionuclide migration and retardation. Cultivation, isolation, and classification of aerobic microbes found in a groundwater sampled from the KAERI Underground Research Tunnel (KURT) located in the KAERI site have carried out and over 20 microbes were found to be present in the groundwater. Microbial identification by a 16S rDNA genetic analysis of the selected major 10 aerobic microbes was performed and the identified microbes were characterized

  19. Development of the air module for the work information management system. Environmental subsystem (WIMS-ES). Master's thesis

    Energy Technology Data Exchange (ETDEWEB)

    Cantwell, R.A.; Davis, J.S.

    1992-09-01

    The primary objective of this research was to develop the air module for the Work Information Management System Environmental Subsystem (WIMSES). The air module will provide Air Force environmental managers with a management information system (MIS) to control the growing amount of air pollution data required to stay in compliance with the newly amended Clean Air Act. To develop the air module, the Air Force's air pollution management requirements were researched first. These requirements were then compared to the capabilities of existing air pollution MISs used in the Department of Defense, the Environmental Protection Agency, and in commercial industry. The research led to a draft air nodule that tracks a base's source inventory and associated permit, control equipment, and emission information. Each base's data will be fully accessible to headquarters personnel through the fully networked WIMS-ES. The draft air nodule was validated through an Air Staff review, an Air Force review, and finally, a workshop with Air Force air pollution experts. The finalized air module has been forwarded to the WIMS-ES programmers and will become the Air Force-wide air pollution MIS in early 1993.... Air pollution, Environmental management, Data management, Data bases, Management information systems, Information systems.

  20. Verification of KAERI-DySCo for the Dynamic Simulation of VHTR-based SI Hydrogen Production Facilities 2: Hydriodic Aeid Multistage Distillation Column Module

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Youngjoon; Lee, Taehoon; Lee, Kiyoung; Kim, Minhwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    This study focuses on the verification of a simulation module for the hydriodic acid multi-stage distillation column(HI{sub x}MDC) in KAERI-DySCo. To verify the HI{sub x}MDC, a comparison of the results calculated by the HI{sub x}MDC with experimental data obtained from the operation of the 50 NL-H{sub 2}/h scale SI test facility be KIER has been carried out in this work. The VHTR-based sulfur-iodine(SI) process used to produce hydrogen from water requires a multistage distillation column to concentrate a hydriodic acid solution that can be applied to the process, its static and dynamic simulation is essentially demanded. According to this necessity, KAERI has developed a dynamic simulation code(KAERI-DySCo) to analyze the start-up behaviors of the SI process components. On the other hand, a 50 NL-H{sub 2}/h scale SI test facility to be operated under a pressurized environment has been constructed by the scientific research partners of KIER, KIST, and POSCO. In agreement with the steady state clues measured experimentally by KIER, it has been finally confirmed that the HI{sub x}MDC, which is one of the simulation modules in KAERI-DySCo for the dynamic simulation code of VHTR-based SI hydrogen production facilities, is a feasible simulation module able to calculate the start-up dynamic behavior of the multistage hydriodic acid distillation column.

  1. Energy response characteristics of several neutron measuring devices determined by using the scattered neutron calibration fields of KAERI

    International Nuclear Information System (INIS)

    The energy response characteristics of several neutron measuring devices used popularly for radiation protection purpose were determined under the simulated neutron calibration fields which was produced by using the radionuclide neutron sources and the shadow objects to scatter and to moderate the fast neutrons emitted from the source. The simulated neutron calibration fields for the calibration of personal dosemeters and survey meters were constructed in the Radiation Calibration Laboratory (RCL) of Korea Atomic Energy Research Institute (KAERI). The radionuclide sources of 252Cf and 241AmBe were used for producing the neutron calibration fields with little different from the method recommended by ISO. The calibration points of interest were behind the shadow objects and the concrete wall in the irradiation room. In order to characterize the neutron calibration fields at the point of test, the spectral neutron fluence rate was determined by means of the Bonner Multi-sphere Spectrometry System (BMSS) and the measured spectra unfolded using the BUNKI code. The dosimetric quantities were derived from the unfolded spectra and used as the reference value to determine the response of each detector. Five kinds of the active detector (three for detector with heavy moderator, one for detector having two spherical tubes with different size, and a TEPC, Tissue Equivalent Proportional Counter) and a TLD as the passive detector were used in this study. The spectral mean energy at the reference calibration points ranged from 0.1 MeV to 3.44 MeV and the dose rate from 0.12 mSv/hr to 4.62 mSv/hr. This paper shows that the big difference, more than four times in case of TLD, in the response of detector with the neutron field spectra should be corrected when the detector is used for monitoring and the dosimetric data of KAERI 's scattered neutron calibration fields. (author)

  2. The Potential and Beneficial Use of Weigh-In-Motion (WIM) Systems Integrated with Radio Frequency Identification (RFID) Systems for Characterizing Disposal of Waste Debris to Optimize the Waste Shipping Process

    Energy Technology Data Exchange (ETDEWEB)

    Abercrombie, Robert K [ORNL; Buckner Jr, Dooley [ORNL; Newton, David D [ORNL

    2010-01-01

    The Oak Ridge National Laboratory (ORNL) Weigh-In-Motion (WIM) system provides a portable and/or semi-portable means of accurately weighing vehicles and its cargo as each vehicle crosses the scales (while in motion), and determining (1) axle weights and (2) axle spacing for vehicles (for determination of Bridge Formula compliance), (3) total vehicle/cargo weight and (4) longitudinal center of gravity (for safety considerations). The WIM system can also weigh the above statically. Because of the automated nature of the WIM system, it eliminates the introduction of human errors caused by manual computations and data entry, adverse weather conditions, and stress. Individual vehicles can be weighed continuously at low speeds (approximately 3-10 mph) and at intervals of less than one minute. The ORNL WIM system operates and is integrated into the Bethel Jacobs Company Transportation Management and Information System (TMIS, a Radio-Frequency Identification [RFID] enabled information system). The integrated process is as follows: Truck Identification Number and Tare Weight are programmed into a RFID Tag. Handheld RFID devices interact with the RFID Tag, and Electronic Shipping Document is written to the RFID Tag. The RFID tag read by an RFID tower identifies the vehicle and its associated cargo, the specific manifest of radioactive debris for the uniquely identified vehicle. The weight of the cargo (in this case waste debris) is calculated from total vehicle weight information supplied from WIM to TMIS and is further processed into the Information System and kept for historical and archival purposes. The assembled data is the further process in downstream information systems where waste coordination activities at the Y-12 Environmental Management Waste Management Facility (EMWMF) are written to RFID Tag. All cycle time information is monitored by Transportation Operations and Security personnel.

  3. Design study of the KAERI Compton X-ray source depending on the laser intensity in the linear or non-linear regime

    Science.gov (United States)

    Park, Seong Hee; Lee, Ji Young; Lee, Kitae; Jeong, Young Uk; Lee, Byung Cheol; Miginsky, Sergei; Bondarenko, A. V.

    2007-05-01

    Quasi-monochromatic X-rays can be generated via Compton backscattering at the KAERI superconducting (SC) radio-frequency (RF) Linac system. The KAERI SC RF Linac with one 352 MHz cryomodule is now operating at 10 MeV. For a few keV Compton X-rays, an electron beamline is designed at the straight section, just after the SC linac, while an optical beamline is designed and fabricated based on the fiber laser delivery. Both will be installed in fall, 2006. In this paper, we estimate the parameters of Compton X-rays at a given system using three different commercial lasers and suggest the scheme to generate higher harmonics using an intense ultra-short laser.

  4. Synthesis of the turbulent mixing in a rod bundle with vaned spacer grids based on the OECD-KAERI CFD benchmark exercise

    International Nuclear Information System (INIS)

    Highlights: • OECD/KAERI international CFD benchmark exercise was operated by KAERI. • The purpose is to validate relevant CFD codes based on the MATiS-H experiments. • Blind calculation results were synthesized in terms of mean velocity and RMS. • Quality of control volume rather than the number of it was emphasized. • Major findings were followed OECD/NEA CSNI report. - Abstract: The second international CFD benchmark exercise on turbulent mixing in a rod bundle has been launched by OECD/NEA, to validate relevant CFD (Computational Fluid Dynamics) codes and develop problem-specific Best Practice Guidelines (BPG) based on the KAERI (Korea Atomic Energy Research Institute) MATiS-H experiments on the turbulent mixing in a 5 × 5 rod array having two different types of vaned spacer grids: split and swirl types. For this 2nd international benchmark exercise (IBE-2), the MATiS-H testing provided a unique set of experimental data such as axial and lateral velocity components, turbulent intensity, and vorticity information. Blind CFD calculation results were submitted by twenty-five (25) participants to KAERI, who is the host organization of the IBE-2, and then analyzed and synthesized by comparing them with the MATiS-H data. Based on the synthesis of the results from both the experiments and blind CFD calculations for the IBE-2, and also by comparing with the IBE-1 benchmark exercise on the mixing in a T-junction, useful information for simulating this kind of complicated physical problem in a rod bundle was obtained. And some additional Best Practice Guidelines (BPG) are newly proposed. A summary of the synthesis results obtained in the IBE-2 is presented in this paper

  5. First lasing of the KAERI compact far-infrared free-electron laser driven by a magnetron-based microtron

    CERN Document Server

    Jeong Young Uk; Kim, S K; Cho, S O; Cha, B H; Lee, J; Kazakevitch, Grigori M; Vobly, P D; Gavrilov, N G; Kubarev, V V; Kulipanov, G N

    2001-01-01

    The KAERI compact far-infrared (FIR) free-electron laser (FEL) has been operated successfully in the wavelength range of 97-150 mu m. It is the first demonstration of FEL lasing by using a magnetron-based classical microtron. We developed a high precision undulator consisting of 80 periods, with each period being 25 mm. The field strength of the undulator can be changed from 4.5 to 6.8 kG with an amplitude deviation of only 0.05% in r.m.s value. The kinetic energy of the electron beam is 6.5 MeV. The average current and pulse duration of the electron beam macropulses are 45 mA and 5.5 mu s, respectively. The measured power of the FEL with the electron beam parameters was more than 50 W for a FIR macropulse having a duration of 4 mu s. The spectral width of the FEL was measured to be 0.5% of the central wavelength. The FEL system, aside from the racks for the controlling units, is compact enough to be located inside an area of 3x4 m sup 2.

  6. First lasing of the KAERI compact far-infrared free-electron laser driven by a magnetron-based microtron

    Science.gov (United States)

    Jeong, Young U.; Lee, Byung Cheol; Kim, Sun Kook; Cho, Sung Oh; Cha, Byung Heon; Lee, Jongmin; Kazakevitch, Grigori M.; Vobly, Pavel D.; Gavrilov, Nicolai G.; Kubarev, Vitaly V.; Kulipanov, Gennady N.

    2001-12-01

    The KAERI compact far-infrared (FIR) free-electron laser (FEL) has been operated successfully in the wavelength range of 97-150 μm. It is the first demonstration of FEL lasing by using a magnetron-based classical microtron. We developed a high precision undulator consisting of 80 periods, with each period being 25 mm. The field strength of the undulator can be changed from 4.5 to 6.8 kG with an amplitude deviation of only 0.05% in r.m.s value. The kinetic energy of the electron beam is 6.5 MeV. The average current and pulse duration of the electron beam macropulses are 45 mA and 5.5 μs, respectively. The measured power of the FEL with the electron beam parameters was more than 50 W for a FIR macropulse having a duration of 4 μs. The spectral width of the FEL was measured to be 0.5% of the central wavelength. The FEL system, aside from the racks for the controlling units, is compact enough to be located inside an area of 3×4 m 2.

  7. Assessment of MARS 2.0 for direct DVI bypass during LBLOCA reflood using KAERI air-water DVI tests

    International Nuclear Information System (INIS)

    MARS code has been assessed for the direct ECC (Emergency Core Cooling) bypass that occurs during LBLOCA reflood of KNGR (Korean Next Generation Reactor) using the KAERI air-water DVI (Direct Vessel Injection) tests that are 1/50 scale-down tests simulating the LBLOCA reflood of KNGR. Assessment matrix is selected for the single and double DVI configurations with typical LBLOCA reflood conditions, that is, DVI injection velocity of 1.0 ∼ 1.6 m/sec and air injection velocity of 20 ∼ 35 m/sec. First, the MARS calculation is adjusted to match the DVI film distribution with the 1/50 scale test results, then the code assessments are carried out for the selected direct DVI bypass tests using the adjusted DVI film distribution. From the assessments, it has been found that the MARS is capable of predicting the direct DVI bypass phenomena as well as the multi-dimensional thermal hydraulics in the downcomer

  8. Investigation of the development and the effect of an excavation damaged zone at KAERI underground research tunnel

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, S.; Cho, W. J

    2008-01-15

    The understanding of the long term behavior of rock around an underground radioactive waste repository is essential for the safe design and operation of the repository and for assuring the safety and technical feasibility of geological disposal concept. The investigation of the influence of EDZ on rock mass behavior is important for the long term stability, economy, and safety points of view. In the case of underground repository, which requires high level safety criteria, the accurate prediction of the long and short term mechanical, hydraulic, and thermal behaviors is especially important. In this study, the size and characteristics of EDZ developed during the construction of the KAERI underground research tunnel, which was constructed by controlled blasting, were investigated using various methods. Goodman jack test for measuring deformation modulus, Georadar, rock core observation, MPBX, and stressmeter were carried out at KURT. The rock cores from the boreholes were tested in laboratory for estimating the EDZ size. Empirical and theoretical equations were also used for the prediction of EDZ. The results from laboratory and in situ tests were used in three-dimensional hydro-mechanical and thermo-mechanical analysis for the evaluation of the EDZ effect. The understanding of EDZ size and the property changes in EDZ from in situ and laboratory tests will be used for the planning, design, and analysis of in situ experiments in KURT. The results from the EDZ study will be helpful for the system design as well as safety analysis of a radioactive repository.

  9. Proceedings of the 1st JAEA/KAERI Information Exchange Meeting on HTGR and Nuclear Hydrogen Technology; August 28-30, 2006, Oarai Research and Development Center, Japan Atomic Energy Agency, Japan

    OpenAIRE

    原子力基礎工学研究部門 核熱応用工学ユニット

    2007-01-01

    Japan Atomic Energy Agency (JAEA) has completed an implementation with Korea Atomic Energy Research Institute (KAERI) on HTGR and nuclear hydrogen technology, "The Implementation of Cooperative Program in the Field of Peaceful Uses of Nuclear Energy between KAERI and JAEA". To facilitate efficient technology development on HTGR and nuclear hydrogen by the IS process, an information exchange meeting was held at the Oarai Research and Development Center of JAEA on August 28-30, 2006 under Progr...

  10. Proceedings of 7th KAERI-JAEA Information Exchange Meeting on HTGR and Nuclear Hydrogen Technology; November 5th-6th,2015,JAEA Oarai Research and Development Center,Oarai,Japan

    OpenAIRE

    稲葉 良知; T. Lee; 植田 祥平; 笠原 清司; 本多 友貴; Lee, H.; Kim, E.; M.Cho; Bae, K; 坂場 成昭

    2016-01-01

    The information exchange meeting on HTGR and hydrogen production technology between Korea Atomic Energy research Institute (KAERI) and Japan Atomic Energy Agency (JAEA) was held in the Oarai Research and Development Center of JAEA on November 5th - 6th, 2015 based on the cooperative research program of the KAERI-JAEA implementation of "Development of HTGR and Nuclear Hydrogen Technology" under "The Implementation of Cooperative Program in the Field of Peaceful Uses of Nuclear Energy between K...

  11. A study on the impacts of R and D expenditures of Korea Atomic Energy Research Institute on the national economy. A study on the contribution made by KAERI to the national economy

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Kee Hwan; Lee, Man Ki; Song, Ki Dong; Kim, Seung Su; Lim, Chae Young [KAERI, Taejon (Korea, Republic of); Jeong, Ki Ho; Park, Sung Duk; Lee, Yo Han; Jin, Si Il; Yun, Hyun Sook; Jeong Dae Kwon [Kyungpook National Univ., Daegu (Korea, Republic of)

    2004-08-01

    This study analyzes the contribution of KAERI's R and D to the national economy. As a case study, the study also analyzes the economic impacts which KAERI's capacity of independent system design contributes to the national economy through localization of KSNP. The research method is Input-output methods which are frequently employed in evaluating economic impacts of R and D in both domestic and foreign academic areas.

  12. Turbulent mixing in a rod bundle with vaned spacer grids: OECD/NEA–KAERI CFD benchmark exercise test

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Seok-Kyu; Kim, Seok; Song, Chul-Hwa, E-mail: chsong@kaeri.re.kr

    2014-11-15

    Highlights: • Detailed velocity profiles have been examined in a rod bundle with mixing spacer grids. • Mixing characteristics strongly depend on the type of the mixing vane on a spacer grid. • The swirl in subchannels is elliptic and the cross-flow in gaps is vigorous in the split-type. • Swirl-type vanes generate a circular swirl in a subchannel and a weak cross-flow in gaps. • Mixing performance is superior in the case of the split-type compared to the swirl-type. - Abstract: An experimental study titled the 2nd International Benchmark Exercise (IBE-2) has been conducted to provide high-precision data of detailed turbulent flow mixing in a rod bundle for validating the CFD codes being used widely in the nuclear power industry. A 5 × 5 rod bundle having mixing spacer grids was adopted as a test rig, and was contained in a square flow housing with a 170 mm side length and 4670 mm length. The 25 rods in a bundle have dimensions of 25.4 mm in outer diameter and a 3863 mm length. The benchmark experiments have been performed at the MATiS-H water loop facility in KAERI. The axial bulk velocity in a rod bundle was maintained at about 1.50 m/s (equivalent to Re ∼50,000) with loop conditions of 35 °C and 1.57 bar measured upstream of the spacer during the experiments. Detailed measurements of the turbulent flow in the subchannels were accomplished using 2-D LDA at four different distances (0.5, 1, 4 and 10 D{sub H}) from the downstream of the mixing spacer grid. The upstream flow profiles also have been measured at the inlet of the mixing spacer grid for the inlet boundary condition. Precise measurements of the lateral and axial velocities in the subchannels are presented at four downstream distances, as well as the inlet from the mixing spacer grid of two types. Turbulence intensities and vorticities in the subchannels are also evaluated from the velocity measurements.

  13. L’intertexte entre le réel et l’imaginaire dans le cinéma de Wim Wenders

    Directory of Open Access Journals (Sweden)

    Gustavo Coura Guimarães Castro

    2013-04-01

    Full Text Available Cet article interroge la façon dont le cinéma représente à l’écran la frontière qui existe entre le monde imaginaire des personnages et celui qu’on appelle «monde réel». Afin de vérifier la figuration à l’écran de cette relation parfois contradictoire, voir complémentaire, on fera une brève étude du film l’Etat des Choses (1982, de Wim Wenders. Le cinéaste est né en Allemagne, en 1945. Initialement, Wenders a étudié médicine et philosophie pendant deux ans, mais, en 1967, il a changé d’avis afin de poursuivre ses études dans l’audiovisuel. A partir de là, le réalisateur s’est fait connaître comme un des représentants les plus célèbres du «nouveau cinéma allemand». En 1978, il a été invité par Francis Ford Coppola pour participer au tournage du film Hammett. Ainsi, son cinéma a été toujours marqué par cette intersection culturelle entre l’Amérique et l’Europe. Notre objectif, dans cet article, est celui de mette en évidence les croisements du cinéma avec l’art, la relation des sujets avec l’espace, ainsi que les influences d’un sur l’autre dans les représentations cinématographiques. Notre référentiel théorique sera fondé, surtout, sur les notions de «fiction» et de «documentaire» chez François Niney. Nous espérons, à partir de cette réflexion, pouvoir comprendre plus en profondeur la façon dont Wenders travaille dans son film la métaphorisation de la lumière dans les mises en scènes, en proposant, en quelque sorte, un dialogue entre les concepts de «clarté» et d’«ombre», en ayant comme arrière-plan l’idée de fiction.This article shows the way that the cinema represents on the screen the boundaries between the imaginary world of the characters and the one that we used to call “real world”. In order to verify the representation on the screen of this contradictory relationship, sometimes complementary, we will do a brief study of the movie The State

  14. Review of the Safety Concern Related to CANDU Moderator Temperature Distribution and Status of KAERI Moderator Circulation Test (MCT) Experiments

    Energy Technology Data Exchange (ETDEWEB)

    Rhee, Bo W.; Kim, Hyoung T. [Severe Accident and PHWR Safety Research Division, Daejeon (Korea, Republic of); Kim, Tongbeum [University of the Witwatersrand, Johannesburg (South Africa); Im, Sunghyuk [KAIST, Daejeon (Korea, Republic of)

    2015-10-15

    threshold temperature and no further deformation is expected. Consequently, a sufficient condition to ensure fuel channel integrity following a large LOCA, is the avoidance of sustained calandria tubes dryout. If the moderator available subcooling at the onset of a large LOCA is greater than the subcooling requirements, a sustained calandria tube dryout is avoided. The temperature oscillations observed in reactor and in test measurements such as MTF need to be characterized and quantified to show that it does not jeopardize the currently available safety margins. Because of the importance of an accurate prediction of moderator temperature distributions and the related moderator subcooling, a 1/4 scaled-down moderator tank of a CANDU-6 reactor, called Moderator Circulation Test (MCT), was erected at KAERI and the current status of MCT experiment progress is described and further experiments are expected to be carried out to generate the experimental data necessary to validate the computer codes that will be used to analyze the accident analysis of operating CANDU-6 plants.

  15. Joint research project to develop a training course or nuclear policy decision makers and planners in developing countries between KAERI and IAEA

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Suh, I. S.; Lee, H. Y. and others

    2000-12-01

    KAERI developed training course curricula on nuclear power policy and planning for decision makers and planners in developing countries under the assistance of the IAEA. It was utilized two IAEA staff members and a Korean consultation group were utilized for the development of curricula. Curriculum consists of training objectives, training contents in modular basis, detailed contents of each training module, training setting, training duration, session hours, and entry requirements of audience. One is workshop on nuclear energy policy for high-level decision makers in developing countries. The other is training course on nuclear power planning and project management for middle level managers in developing countries. The textbook in English will be printed by the end of February in 2001. Developed curricula will be implemented for Vietnam high level nuclear decision makers, middle level managers in developing countries and north Korea nuclear high level decision makers in 2001. These training courses' curricula and textbook will be utilized as basic technical documents to promote the national nuclear bilateral technical cooperation programs with Morocco, Egypt, Bangladesh, Indonesia, Ukraine, etc.

  16. Conceptual Thermal Hydraulic Design of a 20MW Multipurpose Research Reactor (KAERI/VAEC joint study on a new research reactor for Vietnam)

    Energy Technology Data Exchange (ETDEWEB)

    Chae, Hee Taek; Seo, Chul Gyo; Park, Jong Hark; Park, Cheol [Kaeri, Daejeon (Korea, Republic of); Vinh, Le Vinh; Nghiem, Huynh Ton; Dang, Vo Doan Hai [Dalat Nuclear Research Reactor, Hanoi (Viet Nam)

    2007-08-15

    The conceptual thermal hydraulics design analyses for the 20 MW reference AHR core have been jointly performed by the KAERI and DNRI(VAEC). The preliminary core thermal hydraulic characteristics and safety margins for the AHR core were studied for various core flow rates, fuel assembly powers and core inlet temperatures. Statistical method was applied to the thermal hydraulic design of the reactor core. The MATRA{sub h} subchannel code has been applied to evaluate the thermal hydraulic performances of the AHR and the resulting thermal margins of the core under the forced convection cooling mode during a nominal power operation and the natural circulation mode during a reactor shutdown condition. In addition, typical accident analyses were carried out for a loss of flow accident by a primary pump seizure and a reactivity induced accident by a CAR rod withdrawal during a normal full power operation. The normal full power operation of the AHR was ensured with a sufficient safety margin for the onset of nucleate boiling phenomena. The AHR also had a sufficient natural circulation cooling capability to cool the core without the onset of nucleate boiling in the channel after a normal reactor shutdown and the anticipated transients. It was confirmed by the typical accident analyses that the AHR core was sufficiently protected from the loss of flow by the primary cooling pump seizure and the overpower transients by the CAR withdrawal from the MCHFR and fuel temperature points of view.

  17. Joint research project to develop a training course or nuclear policy decision makers and planners in developing countries between KAERI and IAEA

    International Nuclear Information System (INIS)

    KAERI developed training course curricula on nuclear power policy and planning for decision makers and planners in developing countries under the assistance of the IAEA. It was utilized two IAEA staff members and a Korean consultation group were utilized for the development of curricula. Curriculum consists of training objectives, training contents in modular basis, detailed contents of each training module, training setting, training duration, session hours, and entry requirements of audience. One is workshop on nuclear energy policy for high-level decision makers in developing countries. The other is training course on nuclear power planning and project management for middle level managers in developing countries. The textbook in English will be printed by the end of February in 2001. Developed curricula will be implemented for Vietnam high level nuclear decision makers, middle level managers in developing countries and north Korea nuclear high level decision makers in 2001. These training courses' curricula and textbook will be utilized as basic technical documents to promote the national nuclear bilateral technical cooperation programs with Morocco, Egypt, Bangladesh, Indonesia, Ukraine, etc

  18. 基于WIMS格式多群核数据制作过程的优化分析%Optimization analysis of the production process based on WIMS format multigroup nuclear data

    Institute of Scientific and Technical Information of China (English)

    谢明亮; 陈玉清; 于雷; 时浩

    2015-01-01

    Background:NJOY is used widely nuclear data processing program that can convert the data format of ENDF/B nuclear database into WIMS format of the multi-group cross section database.Purpose: This study aims to produce a multi-group database of WIMS-D format on the basis of the latest release of nuclear evaluation library ENDF/B-VII.1 by using nuclear data processing program NJOY-99.Methods: In allusion to basic fuel cell homogenization calculation benchmark problem of the light water reactor (LWR), taking the 235U and 238U nuclide as the main objects of analysis, the effect on processing time of making cross section library, as well as integral parametersΔKef and data sensitivity of selecting input parameters of the NJOY program were compared and analyzed, which optimized the option of input parameter. Results and Conclusion:The results of validating on benchmark problems showed that the production of the multi-group database was correct, which embodied the high accuracy of calculation and provided the basis data of fuel assembly homogenization calculation for pressurized water reactor.%基于最新释放的ENDF/B-VII.1核评价库,采用核数据加工处理程序NJOY-99制作基于WIMS格式的多群数据库,针对轻水堆(Light Water Reactor, LWR)基本燃料栅元均匀化计算基准题,以235U、238U核素为主要分析对象,对比研究了NJOY程序输入模块参数的选择对截面库制作加工时间、积分量ΔKef 及灵敏度的影响,得到优化的输入参数选择方案。基准例题验证结果表明:所制作的多群数据库是正确的,Kef 计算精度较高,可为压水堆燃料组件均匀化计算提供数据基础。

  19. 基于WIM数据的上海长江大桥钢箱梁的寿命评估%Life Evaluation of Box Girder of Shanghai Yangtze River Bridge Based on WIM Data

    Institute of Scientific and Technical Information of China (English)

    廖霞霞; 胡明敏; 徐昊

    2014-01-01

    Evaluation of the box girder details of Shanghai Yangtze river can provide the basis for the bridge ’ s maintenance and repairment .The research result of “Fatigue stress spectrum study of the steel box girder of Shanghai Yangtze River Bridge ,based on the analysis of WIM data” was used to get all the details of the stress spectrum of steel box girder .Then according to BS 5400 the tenth part ,confirming S-N curve which can reflect the details quality of fatigue .Finally ,estimating the steel box girder’s life with the combination of the Miner fatigue cumulative damage rule .According to the result ,we can know that during the current oper-ating process ,the box girder details have small stress amplitude ,high cycles and small damage magnitude . These details will not bring about fatigue damage .During the current operation ,the structure will keep high safety performance and reliability .Determine the damage point and the size of the damage value is unique in this article .%通过对上海长江大桥细节寿命的估算为大桥的维护和修复提供依据。基于论文“基于WIM数据的上海长江大桥钢箱梁应力谱研究”的研究结果,得到钢箱梁各细节的应力谱,同时参考英国桥梁规范BS 5400第十部分,确定了能够体现细节疲劳性能的 S-N曲线,并结合M iner疲劳累积损伤准则,对大桥钢箱梁细节寿命进行评估。研究结果表明,在现行日常运营过程中,钢箱梁各细节应力幅值较小,循环次数多,损伤量级很小,故细节不会发生疲劳破坏,即结构在现行运营期间保持了很高的安全性和可靠度。

  20. Status of the atomized uranium silicide fuel development at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Kim, C.K.; Kim, K.H.; Park, H.D.; Kuk, I.H. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-08-01

    While developing KMRR fuel fabrication technology an atomizing technique has been applied in order to eliminate the difficulties relating to the tough property of U{sub 3}Si and to take advantage of the rapid solidification effect of atomization. The comparison between the conventionally comminuted powder dispersion fuel and the atomized powder dispersion fuel has been made. As the result, the processes, uranium silicide powdering and heat treatment for U{sub 3}Si transformation, become simplified. The workability, the thermal conductivity and the thermal compatibility of fuel meat have been investigated and found to be improved due to the spherical shape of atomized powder. In this presentation the overall developments of atomized U{sub 3}Si dispersion fuel and the planned activities for applying the atomizing technique to the real fuel fabrication are described.

  1. AMO Database in KAERI and Atomic Structure Studies

    Science.gov (United States)

    Rhee, Yongjoo; Park, H. M.; Kwon, D. H.

    2005-05-01

    Atomic spectroscopy studies carried out at the Laboratory for Quantum Optics in Korea Atomic Energy Research Institute are introduced together with the AMO (Atomic, Molecular, and Optical) database established based upon those studies.

  2. Electron optics of a future SC ERL at KAERI

    Science.gov (United States)

    Bondarenko, A. V.; Han, Y. H.; Jeong, Y. U.; Lee, B. C.; Miginsky, S. V.; Park, S. H.

    2007-05-01

    A project of a high-power FEL at Korea Atomic Energy Research Institute is described. The FEL is driven by a superconducting energy recovery linac. The future ERL will be connected to the existing machine without any modification. It consists of two 180° bents and two straight sections: one is for the FEL, another for a Compton X-ray source. One can choose the regime controlling the lenses. The total ERL is isochronous to avoid any problem with longitudinal beam instability. The total relative emittance degradation through the whole machine is ≈1.5. The FEL will be based on a 2 m helical in-vacuum undulator made of permanent magnets. One mirror of the optical cavity is blind and made of copper, the other one, the outcoupler, is semi-transparent and made of CVD diamond. The expected average power is a few kW, the tuning range 35-70 μm.

  3. AMO research activities and data centre in KAERI

    International Nuclear Information System (INIS)

    Dr. Rhee presented data center activities, which support several experimental and theoretical atomic, molecular and optical (AMO) physical programmes. The activities are mainly for fusion science and high precision trace analysis for nuclear safety. There were also some improvements in the ALADDIN database interface at AMODS, which employ the original FORTRAN ALADDIN codes

  4. Melting decontamination technology development for metallic waste recycling at KAERI

    International Nuclear Information System (INIS)

    The radioactively contaminated metallic wastes have been produced from the decommissioning of both two research reactors in Seoul and an uranium conversion plant in Daejeon. The melting decontamination technology was studied to reduce the radioactive waste volume by self disposal as non radioactive waste. The partitioning of radioisotope cobalt 60 and cesium 137 among a molten ingot, slag and dust phases have been investigated in a plasma are melter. A direct current plasma arc furnace was used to melt contaminated stainless steel, mild steel and aluminum wastes with a acid, neutral and basic slag (SiO2. CaO, Al2O3, Fe2O3, MgO) containing radioactive 60Co and 137Cs, to measure the partitioning phenomena. Calcium oxide and ferric oxide were added to provide an increase in the slag fluidity and oxidative potential respectively. Most of the 60Co remained in the ingot phase and it was barely present in the slag during the steel melting. 60Co decontamination factor was not highly dependent on the slag composition. However, it was found that a highly fluid basic slag is a little effective. The distribution ratio of 60Co into the ingot and the slag phase showed that about 90% to 95% was recovered in the ingots. But in the melting of aluminum wastes, it was contaminated by up to 70% in the slag phase. 137Cs was completely eliminated from the melt of the stainless steel as well as the carbon steel and distributed to the dust phase. The partition remaining in the slag depended on whether the slag was basic or acidic and had a high oxidative flux (Fe2O3). A maximum of 65% of the 137Cs remained in the slag phase with a high slag concentration and basicity. Generally, the137Cs distribution in the slag was between 10% and 25% during a lab scale arc furnace test

  5. On the structure of Lattice code WIMSD-5B

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Won Young; Min, Byung Joo

    2004-03-15

    The WIMS-D code is a freely available thermal reactor physics lattice code used widely for thermal research and power reactor calculation. Now the code WIMS-AECL, developed on the basis of WIMS-D, has been used as one of lattice codes for the cell calculation in Canada and also, in 1998, the latest version WIMSD-5B is released for OECD/NEA Data Bank. While WIMS-KAERI was developed and has been used, originated from WIMS-D, in Korea, it was adjusted for the cell calculation of research reactor HANARO and so it has no confirmaty to CANDU reactor. Therefore, the code development applicable to cell calculation of CANDU reactor is necessary not only for technological independence and but also for the establishment of CANDU safety analysis system. A lattice code WIMSD-5B was analyzed in order to set the system of reactor physics computer codes, to be used in the assessment of void reactivity effect. In order to improve and validate WIMSD-5B code, the analysis of the structure of WIMSD-5B lattice code was made and so its structure, algorithm and the subroutines of WIMSD-5B were presented for the cluster type and the pij method modelling the CANDU-6 fuel

  6. On the structure of Lattice code WIMSD-5B

    International Nuclear Information System (INIS)

    The WIMS-D code is a freely available thermal reactor physics lattice code used widely for thermal research and power reactor calculation. Now the code WIMS-AECL, developed on the basis of WIMS-D, has been used as one of lattice codes for the cell calculation in Canada and also, in 1998, the latest version WIMSD-5B is released for OECD/NEA Data Bank. While WIMS-KAERI was developed and has been used, originated from WIMS-D, in Korea, it was adjusted for the cell calculation of research reactor HANARO and so it has no confirmaty to CANDU reactor. Therefore, the code development applicable to cell calculation of CANDU reactor is necessary not only for technological independence and but also for the establishment of CANDU safety analysis system. A lattice code WIMSD-5B was analyzed in order to set the system of reactor physics computer codes, to be used in the assessment of void reactivity effect. In order to improve and validate WIMSD-5B code, the analysis of the structure of WIMSD-5B lattice code was made and so its structure, algorithm and the subroutines of WIMSD-5B were presented for the cluster type and the pij method modelling the CANDU-6 fuel

  7. Dorstige glastuinbouw moet op elke druppel water letten (interview met Wim Voogt)

    NARCIS (Netherlands)

    Bezemer, J.; Voogt, W.

    2010-01-01

    Hoge kwaliteit water wordt schaarser. Dat dwingt de glastuinbouw zorgvuldig met de teeltfactor water om te gaan en minder afhankelijk van oppervlaktewater te worden. Hemelwater blijft de belangrijkste bron maar 100% dekking is te duur. Omgekeerde osmose blijft de meest aantrekkelijke techniek om aan

  8. Is Wim slim?: Samen een biogas netwerk gebruiken? : 8 december 2014

    NARCIS (Netherlands)

    Hengeveld, E.J.; Bekkering, J.; Gemert, W.J.T. van; Broekhuis, A.A.

    2014-01-01

    berekening van kosten voor biogas transport in een biogas verzamel netwerk; twee layouts worden vergeleken: de ster-layout en de visgraat-layout. Investeringen en operationele kosten, inclusief compressiekosten worden in een contante waarde berekening meegenomen. Flexigas symposium 8 december 2014

  9. An update of the Wims-E data processing routines (WEDRO-1.1)

    International Nuclear Information System (INIS)

    The WEDRO-1.1 report is an addendum to the original WEDRO-1.0 technical report, RTE01-2/2-035 (March 1988), and describes some recent additions and changes incorporated into the code, which in now known as WEDRO-1.1. Attention is also drawn to certain errors present in the coding of WEDRO-1.0 which could have resulted in erroneous output cross-sections. A list of predefined material ID's used in WEDRO-1.1, as well as the keyword description and the format of the output WEDRO interface file, is given in this report. 1 tab., 9 refs

  10. Scientific Design of Large Scale Sodium Thermal-Hydraulic Test Facility in KAERI

    International Nuclear Information System (INIS)

    A full passive decay heat removal system is implemented as an advanced design feature for the SFR which is currently being developed in Korea. Its operation depends purely on the natural circulation in a primary heat transport system and a passive decay heat removal system, and no active component or operator action is required. For the demonstration of the design concept, a large scale sodium thermal-hydraulic test facility is being designed with the plan of installation in 2013. In the experiments, the cooling capability during the long- and short-term periods after reactor shutdown will be demonstrated and also the produced experimental data will be utilized for the assessment and verification of the safety and performance analysis codes. In this paper, the preliminary design features of the test facility are presented along with the design requirements and methodology. (author)

  11. Microstructural Characterization of CdZnTe(CZT) Crystal Ingot Grown by Bridgman Method at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kyu Hong; Kim, Han Soo; Ha, Jang Ho; Kim, Young Soo; Choi, Hyo Jeong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Cd{sub 1-x}Zn{sub x}Te crystal is an important wide band-gap IIVI compound semiconductor which is one of the most attractive radiation materials for room temperature detector, especially for gamma rays. However, the electrical and radiation detection properties of CZT crystal vary widely. They have been attributed to several metallurgical defects such as dislocation, grain- and twin-boundary, Cd vacancy, and secondary phase (Te inclusion and precipitation, etc.). They act as trapping sites of carriers, and significantly degrade the detector's performance. To reduce these defects, doping elements such as Indium is applied. That method compensates Cd vacancies. In this study, 1 inch-diameter In-doped CdZnTe ingots were grown by Vertical Bridgman Method. We conducted several microstructural analyses such as Xray diffraction, edge-pit density (EPD), and ICP-MS analysis

  12. Research activities on radioecology for the past ten years: Experiments and modeling at KAERI

    International Nuclear Information System (INIS)

    Experiments in a greenhouse have been conducted to evaluate the effects of radionuclides on various plants. Transfer factors, translocation factors, and other parameters have been measured particularly for major foodstuffs, such as rice and vegetables. A computer code was established to assess the environment in case of acute radionuclide release by accident. Verification and sensitivity analysis have been carried out for the integrity of this code. (author)

  13. In situ borehole heater test at the KAERI Underground Research Tunnel in granite

    International Nuclear Information System (INIS)

    Highlights: • An in situ heater test was carried for investigating TM behavior in granite. • When the heater temperature was 118 °C, the rock temperature at 0.3 m was 50 °C. • The heater was installed at disturbed rock zone, which is 0.5∼1.5m from the wall. • The influences of seasonal temperature variation and heat convection were observed. • The thermal stress increased almost linearly up to 5 MPa. - Abstract: An in situ borehole heater test was carried out in an underground research tunnel at a shallow depth in granite. During the test, the heater temperature was increased to 90 °C to simulate the thermo-mechanical behavior of crystalline rock under normal underground high-level radioactive waste repository conditions. The air, wall and rock temperatures were measured over a period of about four years. At the end of the test, the heater temperature was increased to 118 °C to simulate abnormal overheating conditions. The peak temperatures at the observation holes located at 0.3 m and 0.6 m from the heater hole were approximately 50 °C and 37 °C, respectively. The temperature measurements allowed observations of the effects of rock joints and heat convection through the tunnel wall on the rock temperature distribution. When the power was shut down, the rock temperatures and stress returned rapidly to the original rock temperature

  14. A study on current status of KAERI's international cooperation programs and strategies for effective implementation

    International Nuclear Information System (INIS)

    This is a report on the status and analysis of standard agreement for technical cooperation, expert mission service and technical staff attachment. This report comprises a total of six chapters. Chapter II discusses the status of the technical cooperation agreement which took effect late 1998, and various other model agreements for technical cooperation. Chapter III provides information on the status, regulations, procedures for the expert mission service, and Chapter IV details the current status of the technical staff attachment and the related procedures. Chapter V deals with the utilization status and analysis of the English Counselor, and Chapter VI is the Conclusion. This report has tow objectives. First, we have never published reference books related to standard agreement for technical cooperation, expert mission service and technical staff attachment necessary for international joint research until now. As a result, the research divisions have often asked many questions to the office of international cooperation. Therefore, we expect that many difficulties will be removed and procedures simplified if the research divisions use this report as a reference book. Second, we plan to use this report reference book for policy decisions after establishing the database. (author). 5 tabs., 9 figs

  15. Recent Progress on Atomic Data for Fusion Plasma in KAERI Nuclear Data Center

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Duckhee; Hwang, In Hyuk; Rhee, Yongjoo; Lee, Youngouk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Atomic structure and collision cross sections are essential data for spectroscopic diagnostics of fusion plasma. We have carried out state-of-the-art calculations on cross sections for electron-impact ionization (EII) cross sections of various atoms and ions. Here we report our recent progress on those calculations and discuss future research plan focusing on the actual need for fusion plasma diagnostics. We have calculated EII cross sections of P-like ions including Fe{sup 11+}, and W ions based on a DWA. Present calculations agree with experiments better than previous other calculations. However, for lowly charged ions, our DWA calculations which uses approximated, non unitary scattering matrix have sizable discrepancies with experiments. Hence unitary corrections would be required to improve EII calculations for lowly charged ions. As well more sophisticated R matrix calculations would be required for EII of those ions in order to test DWA calculations mutually.

  16. Present Status and Results from the KAERI Compact THz FEL Facility

    CERN Document Server

    Jeong, Y U; Lee, B C; Park, S H

    2005-01-01

    We have developed a laboratory-scale users facility with a compact terahertz (THz) free electron laser (FEL). The FEL operates in the wavelength range of 100-1200 μm, which corresponds to 0.3-3 THz. The peak power of the FEL micropulse having 30 ps pulse duration is 1 kW and the pulse energy of the 3-μs-FEL-macropulse is approximately 0.3 mJ. The main application of the FEL is THz imaging for bio-medical researches. Transmitted THz imaging of various samples including bugs have been measured. The samples were scanned by a 2-dimensional stage at the focal point of the THz beam. The bugs were not dry because they were killed just before experiments. We could get the transmitted THz imaging of the bugs at 3 THz with the high power THz FEL. THz spectral characteristics of several materials have been studied by the FEL and a THz FTIR spectrometer. We will introduce recent results on the imaging and spectroscopy by the THz FEL.

  17. A field focused university education in NRI : A case of UST-KAERI

    International Nuclear Information System (INIS)

    The University of Science and Technology (UST) was founded in Oct. 2003 through the approval of the former Ministry of Education and Human Resources Development to nurture R and D professionals in convergence technology, who will lead us into the 21st century, the era of information technology. In the era of 'global talent war', every country competes to secure young scientific/technological leaders who will cope with future global and national agenda. In accordance with this need, advanced countries have diversified their higher level education channels utilizing the representative national research institutes or laboratories in addition to the traditional graduate school. Recently, almost all the advanced countries operate a unique graduate school or university to nurture higher talents based on the national research institutes (NRIs) which lead national strategic R and D fields. They include International Max Planck research school(IMPRS) and International Helmholtz graduate school in Germany, Watson school of the Cold Spring Harbor Lab. and Kellogg school of the Scripps Research Institute in US, Feinberg graduate school of the Weizmann Institute in Israel, SOKENDAI in Japan, and UST in Korea. UST has enormous research facilities and special high tech equipment, and has faculty members who have outstanding research records, which is not common in general universities. With high tech equipment, the excellent faculty members are participating in useful field focused R and D education. Instead of having a rigid department, UST allows flexible opening of a major for new convergence technology. By doing this, UST is responding actively to fast changes in science and technology. UST manages 29 campuses granted as government funded research institutes in the area of science and technology with educational functions. Each campus member and faculty are joining a network related to educating each other and cooperating with different research activities, which is expanding to enhance collaboration with institutions related to diverse areas of research. In addition, to share and reflect the newest trend of research on education, collaborated lectures are operating, which have grafted the know how each of its campus professors. The profiles of these professors are provided to students in a masters, integrative and doctorate program, who apply to enter the university. The students can determine the particular research area with the help of their expected academic advisor in advance, which allows a customized research education for the students

  18. Ultrasonic measurement of water layer thickness by horizontal flow pattern profile in a KAERI HAWL

    International Nuclear Information System (INIS)

    An ultrasonic measurement technique for determining water layer thickness is presented. The technique can obtain information of the water layer thickness in a tube in the form of a horizontal flow pattern profile through the used of a correct quantitative method. The main objective of the present work is to measure the water layer thickness of the flow using an ultrasonic measurement system. Ultrasonic measurement techniques of water layer thickness are produced to measure the variations in water layer thickness in the horizontal stratified flow and vertical annular flow regimes. (author)

  19. High Power Proton Accelerator Development at KAERI and its Vacuum System

    Science.gov (United States)

    Choi, Byung-Ho; Park, Mi Young; Kim, Kui Young; Kim, Kye Ryung; Kim, Jun Yeon; Cho, Yong-Sub

    The Proton Engineering Frontier Project (PEFP), approved and launched by the Korean government in July 2002, includes a 100 MeV proton linear accelerator (linac) development and programs for its utilization and application. The main goals in the first phase of the project, spanning from 2002 to 2005, were the design of a 100 MeV proton linac and the development of a 20 MeV linac consisting of a 50 keV proton injector, a 3 MeV radio frequency quadrupole (RFQ), and a 20 MeV drift tube linac (DTL). The 50 keV injector and 3 MeV RFQ have been installed and tested, and the 20 MeV DTL is being assembled, tuned and under a beam test. At the same time, the utilization programs using the proton beam have been planned, and some are now under way. The vacuum system of the 20 MeV proton linac and its related issues, especially in operation with a high duty, are discussed in detail.

  20. A study on the management of intellectual property for the pending projects in KAERI

    International Nuclear Information System (INIS)

    This study targeted researching a main character of intellectual property and response strategy regarding a nuclear research reactor project in the ANSI region. The study shows that each member country of the ANSI has its own registering system of patent and other intellectual property. Moreover, we confirmed that there was no previously registered patent in Malaysia, Singapore, Thailand, Vietnam, and Indonesia that have an intent to import research reactor. As a result of this study we suggest that registering patent relating a nuclear research reactor not only in potential importing countries but also in major nuclear countries are preferable because this approach is a more basic strategy for technology and market protection. Although major nuclear country or company has own essential or unique patent regarding nuclear side, our registering that type of patent to potential importing countries is also valid for banning rival company's intrusion to the market and get a better position for negotiation with importing country as first register of intellectual property keeps a priority in the country

  1. A Study on the Management of Intellectual Property for the Pending Projects in KAERI

    International Nuclear Information System (INIS)

    This study is to analysis legal status of intellectual property of the Jordan Researching and Training Reactor(JRTR). To get the goals, researching internal and international laws related with intellectual properties and reviewing the JRTR project are performed. Not only technology itself but also human resources joined the project are considered to find best solution for management. This study will be a good base for the JRTR project itself and other similar projects

  2. A Novel Approach to Find Optimized Neutron Energy Group Structure in MOX Thermal Lattices Using Swarm Intelligence

    International Nuclear Information System (INIS)

    Energy group structure has a significant effect on the results of multigroup transport calculations. It is known that UO2-PuO2 (MOX) is a recently developed fuel which consumes recycled plutonium. For such fuel which contains various resonant nuclides, the selection of energy group structure is more crucial comparing to the UO2 fuels. In this paper, in order to improve the accuracy of the integral results in MOX thermal lattices calculated by WIMSD-5B code, a swarm intelligence method is employed to optimize the energy group structure of WIMS library. In this process, the NJOY code system is used to generate the 69 group cross sections of WIMS code for the specified energy structure. In addition, the multiplication factor and spectral indices are compared against the results of continuous energy MCNP-4C code for evaluating the energy group structure. Calculations performed in four different types of H2O moderated UO2-PuO2 (MOX) lattices show that the optimized energy structure obtains more accurate results in comparison with the WIMS original structure

  3. A Novel Approach to Find Optimized Neutron Energy Group Structure in MOX Thermal Lattices Using Swarm Intelligence

    Energy Technology Data Exchange (ETDEWEB)

    Akbari, M.; Khoshahval, F.; Minucheha, A.; Zolfaghari, A. [Shahid Beheshti Univ., Tehran (Iran, Islamic Republic of)

    2013-12-15

    Energy group structure has a significant effect on the results of multigroup transport calculations. It is known that UO{sub 2}-PuO{sub 2} (MOX) is a recently developed fuel which consumes recycled plutonium. For such fuel which contains various resonant nuclides, the selection of energy group structure is more crucial comparing to the UO{sub 2} fuels. In this paper, in order to improve the accuracy of the integral results in MOX thermal lattices calculated by WIMSD-5B code, a swarm intelligence method is employed to optimize the energy group structure of WIMS library. In this process, the NJOY code system is used to generate the 69 group cross sections of WIMS code for the specified energy structure. In addition, the multiplication factor and spectral indices are compared against the results of continuous energy MCNP-4C code for evaluating the energy group structure. Calculations performed in four different types of H{sub 2}O moderated UO{sub 2}-PuO{sub 2} (MOX) lattices show that the optimized energy structure obtains more accurate results in comparison with the WIMS original structure.

  4. Validation of CENDL and JEFF evaluated nuclear data files for TRIGA calculations through the analysis of integral parameters of TRX and BAPL benchmark lattices of thermal reactors

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh)], E-mail: jahirulkhan@yahoo.com; Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2009-10-15

    The aim of this paper is to present the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through the analysis of the integral parameters of TRX and BAPL benchmark lattices of thermal reactors for neutronics analysis of TRIGA Mark-II Research Reactor at AERE, Bangladesh. In this process, the 69-group cross-section library for lattice code WIMS was generated using the basic evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 with the help of nuclear data processing code NJOY99.0. Integral measurements on the thermal reactor lattices TRX-1, TRX-2, BAPL-UO{sub 2}-1, BAPL-UO{sub 2}-2 and BAPL-UO{sub 2}-3 served as standard benchmarks for testing nuclear data files and have also been selected for this analysis. The integral parameters of the said lattices were calculated using the lattice transport code WIMSD-5B based on the generated 69-group cross-section library. The calculated integral parameters were compared to the measured values as well as the results of Monte Carlo Code MCNP. It was found that in most cases, the values of integral parameters show a good agreement with the experiment and MCNP results. Besides, the group constants in WIMS format for the isotopes U-235 and U-238 between two data files have been compared using WIMS library utility code WILLIE and it was found that the group constants are identical with very insignificant difference. Therefore, this analysis reflects the validation of evaluated nuclear data files CENDL-2.2 and JEFF-3.1.1 through benchmarking the integral parameters of TRX and BAPL lattices and can also be essential to implement further neutronic analysis of TRIGA Mark-II research reactor at AERE, Dhaka, Bangladesh.

  5. Proceedings of the JAERI-KAERI Joint Seminar on Post Irradiation Examination; November 9-10, 1992, JAERI Oarai Japan

    OpenAIRE

    材料試験炉部

    1993-01-01

    日本原子力研究所(原研)材料試験炉部は、JAERI-KAERI協力研究協定に基づき、1985年以来、韓国原子力研究所(韓国原研)と照射後試験技術に関する研究、開発協力を進めてきたが、本協定のフェーズIIが多くの成果を得て平成4年11月に完了したので、これまでの研究開発協力のとりまとめを行うために、日韓セミナーを11月9日から2日間日本原子力研究所大洗研究所で開催した。本報告書は、会議に参加した原研、韓国原研の他、中国核工程研究設計院、東北大学金属材料研究所付属材料試験炉利用施設、日本核燃料開発(株)、ニュークリア・デベロップメント(株)の発表論文28件を3つのセッションに分けて収録したものである。...

  6. KAERI software safety guideline for developing safety-critical software in digital instrumentation and control system of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jang Soo; Kim, Jang Yeol; Eum, Heung Seop

    1997-07-01

    Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organization. The requirements for software important to safety of nuclear reactor are described in such positions and standards. Most of them are describing mandatory requirements, what shall be done, for the safety-critical software. The developers of such a software. However, there have been a lot of controversial factors on whether the work practices satisfy the regulatory requirements, and to justify the safety of such a system developed by the work practices, between the licenser and the licensee. We believe it is caused by the reason that there is a gap between the mandatory requirements (What) and the work practices (How). We have developed a guidance to fill such gap, which can be useful for both licenser and licensee to conduct a justification of the safety in the planning phase of developing the software for nuclear reactor protection systems. (author). 67 refs., 13 tabs., 2 figs.

  7. KAERI software safety guideline for developing safety-critical software in digital instrumentation and control system of nuclear power plant

    International Nuclear Information System (INIS)

    Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organization. The requirements for software important to safety of nuclear reactor are described in such positions and standards. Most of them are describing mandatory requirements, what shall be done, for the safety-critical software. The developers of such a software. However, there have been a lot of controversial factors on whether the work practices satisfy the regulatory requirements, and to justify the safety of such a system developed by the work practices, between the licenser and the licensee. We believe it is caused by the reason that there is a gap between the mandatory requirements (What) and the work practices (How). We have developed a guidance to fill such gap, which can be useful for both licenser and licensee to conduct a justification of the safety in the planning phase of developing the software for nuclear reactor protection systems. (author). 67 refs., 13 tabs., 2 figs

  8. KAERI software verification and validation guideline for developing safety-critical software in digital I and C system of NPP

    International Nuclear Information System (INIS)

    This technical report is to present V and V guideline development methodology for safety-critical software in NPP safety system. Therefore it is to present V and V guideline of planning phase for the NPP safety system in addition to critical safety items, for example, independence philosophy, software safety analysis concept, commercial off the shelf (COTS) software evaluation criteria, inter-relationships between other safety assurance organizations, including the concepts of existing industrial standard, IEEE Std-1012, IEEE Std-1059. This technical report includes scope of V and V guideline, guideline framework as part of acceptance criteria, V and V activities and task entrance as part of V and V activity and exit criteria, review and audit, testing and QA records of V and V material and configuration management, software verification and validation plan production etc., and safety-critical software V and V methodology. (author). 11 refs

  9. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M., E-mail: sarker_md@yahoo.co [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2010-03-15

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, k{sub eff} and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  10. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    International Nuclear Information System (INIS)

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, keff and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  11. The calculational VVER burnup Credit Benchmark No.3 results with the ENDF/B-VI rev.5 (1999)

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez Gual, Maritza [Centro de Tecnologia Nuclear, La Habana (Cuba). E-mail: mrgual@ctn.isctn.edu.cu

    2000-07-01

    The purpose of this papers to present the results of CB3 phase of the VVER calculational benchmark with the recent evaluated nuclear data library ENDF/B-VI Rev.5 (1999). This results are compared with the obtained from the other participants in the calculations (Czech Republic, Finland, Hungary, Slovaquia, Spain and the United Kingdom). The phase (CB3) of the VVER calculation benchmark is similar to the Phase II-A of the OECD/NEA/INSC BUC Working Group benchmark for PWR. The cases without burnup profile (BP) were performed with the WIMS/D-4 code. The rest of the cases have been carried with DOTIII discrete ordinates code. The neutron library used was the ENDF/B-VI rev. 5 (1999). The WIMS/D-4 (69 groups) is used to collapse cross sections from the ENDF/B-VI Rev. 5 (1999) to 36 groups working library for 2-D calculations. This work also comprises the results of CB1 (obtained with ENDF/B-VI rev. 5 (1999), too) and CB3 for cases with Burnup of 30 MWd/TU and cooling time of 1 and 5 years and for case with Burnup of 40 MWd/TU and cooling time of 1 year. (author)

  12. Immigrants' attitudes towards welfare redistribution. An exploration of role of government preferences among immigrants and natives across 18 European welfare states / Tim Reeskens, Wim van Oorschot

    Index Scriptorium Estoniae

    Reeskens, Tim

    2015-01-01

    Artiklis käsitletakse pagulaste arvamusi heaoluriigi kohta 18 Euroopa riigis (sh Eesti), täpsemalt, kuidas nad suhtuvad saadavatesse sotsiaaltoetustesse, võrreldakse ka pagulaste hoiakuid põlisrahvastiku omadega. Aluseks 2008. aasta Euroopa sotsiaaluuringu heaolu hoiakute moodul

  13. Income inequality and depression: the role of social comparisons and coping resources / Ioana van Deurzen, Erik van Ingen; Wim J. H. van Oorschot

    Index Scriptorium Estoniae

    Deurzen, Ioana van

    2015-01-01

    Artiklis käsitletakse sissetulekute ebavõrdsuse ja depressiooni seoseid, pöörates tähelepanu riikidevahelistele erinevustele ja seda mõjutavatele faktoritele Euroopa riikides, sh Eesti. Aluseks on Euroopa sotsiaaluuringu (2006/2007) andmed

  14. Indian advanced heavy water reactor for thorium utilisation and nuclear data requirements and status

    International Nuclear Information System (INIS)

    BARC is embarking on thorium utilisation program in a concerted and consistent manner to achieve all round capabilities in the entire Thorium cycle under the Advanced Heavy Water Reactor (AHWR) development program. Upgrading our nuclear data capability for thorium cycle is one of the main tasks of this program. This paper gives a brief overview of the physics design features of the AHWR. The basic starting point of the analysis has been the lattice simulation of the fuel cluster employing the WIMS-D4 code package with 1986 version of 69 group library. For the analysis of thorium cycle, the present multi group version contains the three major isotopes viz., 232Th, 233U and 233Pa. To correctly evaluate the fuel cycle we require many more isotopes of the Th burnup chain. With the help of NDS, IAEA, many other isotopes of interest in AHWR, actinides in the thorium burnup chain, burnable absorbers, etc., were generated. Some of them were added to the WIMS-D4 library and the results are discussed. The WIMS-D4 library is also being updated as part of the IAEA coordinated research project on Final Stage of WLUP with international cooperation. India is also taking part in CRP. The evaluation of AHWR lattice with this new library is presented. Some comments regarding the fission product data being used in WIMS libraries are given, which are tuned to U-Pu cycles. The measurements for 233U are rather old. Measurements in high energies are also very sparse. More attention by nuclear data community is required in this regard as well. India has also begun a modest program to assess the ADS concepts, with the aim of employing thermal reactor systems, such as AHWR. A one way coupled booster reactor concept is being analysed with available code systems and nuclear data. A brief summary of this concept is also being discussed in this paper. A general survey on the quality of the evaluated nuclear data of the major and minor isotopes of thorium cycle is also given. A major

  15. 77 FR 34367 - Proposed Subsequent Arrangement

    Science.gov (United States)

    2012-06-11

    ... Institute (KAERI), in accordance with the plan contained in documents KAERI/AR-889/2011, ``Post-Irradiation Examination and R&D Programs Using Irradiated Fuels at KAERI,'' dated June 2011, and KAERI/ AR-919/2012, ``DUPIC Fuel Fabrication Using Spent PWR Fuel at KAERI,'' dated February 2012. These facilities are...

  16. Proceedings of the 3rd JAERI-KAERI Joint Seminar on Post Irradiation Examination Technology; March 25-26, 1999, JAERI Oarai, Japan

    OpenAIRE

    材料試験炉部

    1999-01-01

    原研材料試験炉部は、韓国原研核燃料サイクル研究試験チームと、原子力の平和利用分野における研究協力実施取り決め(計画3照射後試験技術の開発)に基づき、照射後試験に関連する情報交換を実施してきた。これらの成果のとりまとめとして第3回日韓セミナーを1999年3月25日から2日間、大洗研で開催した。会議には、原研、韓国原研のほか、漢陽大、JNC、東北大金研施設、NFD、NDC等、総勢84名の参加者を得て、照射後試験の現状と将来計画、照射後試験技術、照射後試験データの評価等に関する計33件の講演があり、高速実験炉用燃料棒の再組立法開発、韓国商用炉破損燃料の原因推定等、最新の報告がなされた。また、次世代の照射後試験に対するナノレベルPIE技術、試験空間や利用に関する柔軟性の確保、さらに施設間の相互協力と国際協力の重要性も指摘された。...

  17. Assessment of MARS for downcomer multi-dimensional thermal hydraulics during LBLOCA reflood using KAERI air-water direct vessel injection tests

    International Nuclear Information System (INIS)

    The MARS code has been assessed for the downcomer multi-dimensional thermal hydraulics during a large break loss-of-coolant accident (LBLOCA) reflood of Korean Next Generation Reactor (KNGR) that adopted an upper direct vessel injection (DVI) design. Direct DVI bypass and downcomer level sweep-out tests carried out at 1/50-scale air-water DVI test facility are simulated to examine the capability of MARS. Test conditions are selected such that they represent typical reflood conditions of KNGR, that is, DVI injection velocities of 1.0 ∼ 1.6 m/sec and air injection velocities of 18.0 ∼ 35.0 m/sec, for single and double DVI configurations. MARS calculation is first adjusted to the experimental DVI film distribution that largely affects air-water interaction in a scaled-down downcomer, then, the code is assessed for the selected test matrix. With some improvements of MARS thermal-hydraulic (T/H) models, it has been demonstrated that the MARS code is capable of simulating the direct DVI bypass and downcomer level sweep-out as well as the multi-dimensional thermal hydraulics in downcomer, where condensation effect is excluded. (authors)

  18. Development calculational procedures for the neutron physics design of advanced pressurized water reactors (APWR) with tight triangular lattices in hexagonal fuel assemblies

    International Nuclear Information System (INIS)

    The new procedures for the calculation of infinite reactor zones build a synthesis of wellknown fast breeder (FBR) and light water reactor (LWR) methods. The data libraries are based on the 69 energy group structure of the WIMS code for thermal reactors and use the flexible storage mode of the FBR libraries. For the calculation of effective cross sections in the energy of neutron resonances, being very important in the APWR with its strongly epithermal neutron spectrum, several options are available. In most applications improved selfshielding tabulation formalisms (f-factor concept) are used. For more accurate investigations the fine flux programs ULFISP (own development) or RESABK (IKE, Stuttgart) may be selected. All cross section calculations use a modified version of the FBR code GRUCAL. Particularly the calculation of voided lattices may be improved at 69 groups with the program REMOCO or with a new 334 group library. The new calculational procedures could be qualified for a large number of LWR, APWR and FBR applications. The fuel assembly and whole core calculations are performed with available FBR methods. A new reactor core simulation program ARCOSI has been developed for the investigation of an APWR equilibrium core. The required cross sections come from fast interpolations of fuel assembly data on code-own libraries. The whole core calculations are performed with the fast nodal code HEXNODK, adopted from KWU. All calculational procedures are part of the powerful FBR code system KAPROS. (orig.)

  19. Evaluation of significance of Zr bound in ZrH{sub x} for its possible inclusion in the WIMSD-5 cross section library

    Energy Technology Data Exchange (ETDEWEB)

    Bhyuian, S.I.; Sarker, M.M.; Chakrobortty, T.K.; Khan, M.J.H. [Institute of Nuclear Science and Technology, AERE, Dhaka, (Bangladesh); Kulikowska, Teresa [Institute of Atomic Energy, Swierk, Otwock (Poland)

    2001-03-01

    The principal objective of this study was to evaluate the significance of a separate data for Zirconium bound in Zirconium hydride rather than as a free atom and its possible inclusion in the WIMSD library. A TRIGA research reactor benchmark input specified for WIMSD-5 was prepared. The calculations have been performed by the WIMSD-5B code and the ANL version of WIMSD code. In the ANL version, two sets of data for Hydrogen were available: for Hydrogen bound in water and Hydrogen bound in Zirconium hydride. For Zirconium, the available data were for Zirconium natural and Zirconium bound in Zirconium hydride prepared without taking into account the P{sub 1} correction. A separate data for Zirconium bound for Zirconium hydride with P{sub 1} correction was prepared for the WIMSD-5B code at INST, AERE, Savar. The cross section data for all the elements of the benchmark input have been processed by NJOY94.10+ based on ENDF/B-VI library and incorporated in the 69-group WIMS library. All the calculations have been carried out applying 69 energy groups in the main transport routine with subsequent condensation to 7 group. Four cases namely (i) diffusion, (ii) B{sub 1} with P{sub 1} thermal scattering matrices for H and O in water only, (iii) as above but with a P{sub 1} matrix also for H bound in ZrHx, (iv) as above but with a P{sub 1} matrix also for Zr bound in ZrHx were studied. It is seen that the differences in cross sections are negligible although the overall effect in K-eff is up to 700 pcm in the case of ANL, and in our case, the effect is even stronger. The possible cause of this inconsistency could be the absence of P{sub 1} matrices for all the principal materials for the benchmark input in the WIMSD library. The author of the WIMS recommends the usage of P{sub 1} matrices only if they are available for all principal isotopes of a material. No material is treated separately on the level of leakage calculations and the contribution from the first order is

  20. Comparison of neutron cross sections for selected fission products and isotopic composition analyses with burnup

    Energy Technology Data Exchange (ETDEWEB)

    Kim, D. H.; Gil, C. S.; Kim, J. D.; Jang, J. H.; Lee, Y. D. [KAERI, Taejon (Korea)

    2003-10-01

    The neutron absorption cross sections for 18 fission products evaluated within the framework of the KAERI-BNL international collaboration have been compared with the ENDF/B-VI release 7. Also, the influence of the new evaluations on isotopic compositions of the fission products as a function of burnup has been analyzed through the OECD/NEA burnup credit criticality benchmarks (Phase 1B) and the LWR/Pu recycling benchmarks. These calculations were performed by WIMSD-5B with the 69 group libraries prepared from three evaluated nuclear data libraries: ENDF/B-VI.7, ENDF/B-VI.8 including new evaluations in resonance region covering thermal region, and ENDF/B-VII expected including those in upper resonance region up to 20 MeV. For Xe-131, the composition calculated with ENDF/B-VI.8 shows maximum difference of 4.78% compared to ENDF/B-VI.7. However, the isotopic compositions of all fission products calculated with ENDF/B-VII shows no differences compared to ENDF/B-VI.7.

  1. Comparisons of Neutron Cross Sections and Isotopic Composition Calculations for Fission-Product Evaluations

    Science.gov (United States)

    Kim, Do Heon; Gil, Choong-Sup; Chang, Jonghwa; Lee, Yong-Deok

    2005-05-01

    The neutron absorption cross sections for 18 fission products evaluated within the framework of the KAERI (Korea Atomic Energy Research Institute)-BNL (Brookhaven National Laboratory) international collaboration have been compared with ENDF/B-VI.7. Also, the influence of the new evaluations on the isotopic composition calculations of the fission products has been estimated through the OECD/NEA burnup credit criticality benchmarks (Phase 1B) and the LWR/Pu recycling benchmarks. These calculations were performed by WIMSD-5B with the 69-group libraries prepared from three evaluated nuclear data libraries: ENDF/B-VI.7, ENDF/B-VI.8 including the new evaluations in the resonance region covering the thermal region, and the expected ENDF/B-VII including those in the upper resonance region up to 20 MeV. For Xe-131, the composition calculated with ENDF/B-VI.8 shows a maximum difference of 5.02% compared to ENDF/B-VI.7. However, the isotopic compositions of all the fission products calculated with the expected ENDF/B-VII show no differences when compared to ENDF/B-VI.7 for the thermal reactor benchmark cases.

  2. Validation of Decommissioning Engineering System Application against KRR-2

    International Nuclear Information System (INIS)

    KAERI is the only expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant) decommission. This paper contains validation results of the KAERI DES by using KRR-2 decommissioning data. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DES application program. One of decommissioning experience data, KRR-2 was used for KAERI DES validation and it successfully is reflected in KAERI DES

  3. Adapting and implementing the Wine in Moderation-Art de Vivre programme in Argentina

    Directory of Open Access Journals (Sweden)

    Alvarez Natalia

    2014-01-01

    Full Text Available The Wine in Moderation-Art de Vivre (WIM programme was officially launched in 2008 as the wine sector's contribution to the EU Alcohol & Health Forum, within the framework of the EU strategy to support Member States in reducing alcohol-related harm. Building on the values of the “wine culture” and founded on information backed by science, broad education & self-regulation, WIM aims at promoting moderate and responsible behavior in the consumption of wine as a social and cultural norm. Considering the global and national trends in the wine market, the drinking patterns and the alcohol & health policy, Bodegas de Argentina (BAAC decided to mobilize concrete actions to contribute to the reduction of alcohol related harm, by adapting and implementing the WIM programme in Argentina. BAAC decided to engage the whole national wine value chain in the WIM programme and empower them with necessary knowledge and tools to properly implement it and disseminate the WIM message. The first step was to adapt the WIM programme and message to the cultural and linguistic context respecting the programme's common approach and creating an action plan with 2 main phases. With the Argentinean wine value chain participating in WIM and having the proper skills to do, the challenge now lies in reaching consumer. The successful implementation in Argentina has set a milestone in WIM's international development.

  4. Hybrid bayesian networks for traffic load models from weigh-in-motion data

    NARCIS (Netherlands)

    Morales-Nápoles, O.; Steenbergen, R.D.J.M.

    2012-01-01

    The Weigh-in-Motion (WIM) systems are used, among other applications, in pavement and bridge engineering, in infrastructure monitoring and assessment and inspection and reinforcement strategies. In the Netherlands and some other countries, the video-WIM system was implemented for pre-selection, and

  5. 基于WIMS和MCNP耦合程序的医院中子照射器Ⅰ型堆燃耗计算%The burnup calculation for in-hospital neutron irradiator mark 1 reactor based on coupled code of WIMS and MCNP

    Institute of Scientific and Technical Information of China (English)

    郭和伟; 江新标; 赵柱民; 陈立新; 张信一; 周永茂

    2012-01-01

    建立了基于WIMS和MCNP的临界-燃耗耦合计算方法,并对此方法进行了验算.通过栅元和组件问题的分析计算以及西安脉冲堆燃耗实验对比,验证了此耦合程序的可靠性和正确性.最后应用此耦合程序对医院中子照射器Ⅰ型堆的燃耗进行了计算和分析.%Numerical calculation for the equivalent surface source of the thermal neutron duct of in-hospital neutron irradiator mark 1 (IHNI-1) reactor is carried out using MCNP Monte Carlo code. Cold clean criticality of B-core is searched. Neutron beam parameters at the exit of thermal neutron duct are calculated. Equivalent neutron and -y surface sources for BNCT are built using equivalent surface source model. And these sources are reliable to calculate absorbed dose distribution in equivalent model of head quickly.

  6. Description and user manual of the WIMSLIC, FIXER and COMPA programs; Descripcion y manual del usuario de los programas WIMSLIC, FIXER y COMPA

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1992-08-15

    In this work the WIMS library and those WIMSLIC, FIXER and COMPA codes that are used to give him maintenance or to create a new one, the way to use them and its scopes are described. The objective of WIMSLIC, is the one of generating data nuclear with the WIMS code format, uses those results obtained with the NJOY system and the one POWR module, the FIXER function is to generate a new WIMS library or to already modify an existent, using the results of the one WIMSLIC code or those obtained with NJOY and WIMSR, while the COMPA function is to compare data groups with WIMS format. In the Appendix 1 the files of data are had that would use to generate a new library of WIMS that contain nuclear data for U-235, U-238, H-1, 0-16 and Al-27. In the Appendix 2 one has the listing of the programs before mentioned. (Author)

  7. Development of chemical flocculant for wastewater treatment

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jang Jin; Shin, J. M.; Lee, H. H.; Kim, M. J.; Yang, M. S.; Park, H. S

    2000-12-01

    Reagents 'KAERI-I and KAERI-II' which were developed as coagulants for industrial wastewater treatment in the study showed far superior performance to the existing inorganic coagulants such as Alum and Iron salt(FeSO4) when compared to their wastewater treatment performance in color and COD removal. Besides, it was not frozen at -25 deg C {approx} -30 deg C. When reagents 'KAERI-I and KAERI-II' were used as coagulant for wastewater treatment, the proper dosage was ranged from 0.1% to 0.5%(v/v) and proper pH range was 10.5 {approx} 11.5 in the area of alkaline pH.Reagents 'KAERI-I and KAERI-II' showed good performance with 95% or more removal of color-causing material and 60% or more removal of COD.

  8. Development of chemical flocculant for wastewater treatment

    International Nuclear Information System (INIS)

    Reagents 'KAERI-I and KAERI-II' which were developed as coagulants for industrial wastewater treatment in the study showed far superior performance to the existing inorganic coagulants such as Alum and Iron salt(FeSO4) when compared to their wastewater treatment performance in color and COD removal. Besides, it was not frozen at -25 deg C ∼ -30 deg C. When reagents 'KAERI-I and KAERI-II' were used as coagulant for wastewater treatment, the proper dosage was ranged from 0.1% to 0.5%(v/v) and proper pH range was 10.5 ∼ 11.5 in the area of alkaline pH.Reagents 'KAERI-I and KAERI-II' showed good performance with 95% or more removal of color-causing material and 60% or more removal of COD

  9. Heating of the Warm Ionized Medium by Low-Energy Cosmic Rays

    CERN Document Server

    Walker, Mark A

    2015-01-01

    In light of evidence for a high ionization rate due to Low-Energy Cosmic Rays (LECR), in diffuse molecular gas in the solar neighbourhood, we evaluate their heat input to the Warm Ionized Medium (WIM). LECR are much more effective at heating plasma than they are at heating neutrals. We show that the upper end of the measured ionization rates corresponds to a local LECR heating rate sufficient to maintain the WIM against radiative cooling, independent of the nature of the ionizing particles or the detailed shape of their spectrum. Elsewhere in the Galaxy the LECR heating rates may be higher than measured locally. In particular, higher fluxes of LECR have been suggested for the inner Galactic disk, based on the observed hard X-ray emission, with correspondingly larger heating rates implied for the WIM. We conclude that LECR play an important, perhaps dominant role in the thermal balance of the WIM.

  10. Heating of the Warm Ionized Medium by Low-energy Cosmic Rays

    Science.gov (United States)

    Walker, Mark A.

    2016-02-01

    In light of evidence for a high ionization rate due to low-energy cosmic rays (LECR) in diffuse molecular gas in the solar neighborhood, we evaluate their heat input to the warm ionized medium (WIM). LECR are much more effective at heating plasma than they are at heating neutrals. We show that the upper end of the measured ionization rates corresponds to a local LECR heating rate sufficient to maintain the WIM against radiative cooling, independent of the nature of the ionizing particles or the detailed shape of their spectrum. Elsewhere in the Galaxy the LECR heating rates may be higher than those measured locally. In particular, higher fluxes of LECR have been suggested for the inner Galactic disk, based on the observed hard X-ray emission, with correspondingly larger heating rates implied for the WIM. We conclude that LECR play an important and perhaps dominant role in the thermal balance of the WIM.

  11. Euro stabiilsuse looja lahkus / Tõnis Arnover

    Index Scriptorium Estoniae

    Arnover, Tõnis, 1952-

    2005-01-01

    Suri Euroopa Keskpanga ekspresident Wim Duisenberg. Duisenberg leiti südamerikke tõttu uppununa oma maja basseinist Lõuna-Prantsusmaal. Duisenbergi tegevusest Keskpanga juhina. Lisa: Euroopa Keskpanga juht paistis varakult silma

  12. Sakslaste stiliseeritud hullus / Erkki Luuk

    Index Scriptorium Estoniae

    Luuk, Erkki, 1971-

    2004-01-01

    PÖFFi Suvekino prorgramm "Oberhauseni lapsed" saksa 1960-1970. aastate uuenduslikest mängufilmidest : Alexander Kluge "Artistid tsirkusekupli all : lootusetus", Rainer Werner Fassbinderi "13 kuud aastas", Wim Wendersi "Valeliigutus" ja "Ameerika sõber"

  13. SPS tunnels fill up

    CERN Multimedia

    1974-01-01

    Here the installation of a 25 tons beam dump. Wim Middelkoop stands near the wall (2nd on the left); Peter Sievers stands on the left behind the magnet; Eric Geiger is 3rd along the wall on the right.

  14. Water Well Locations - MO 2012 Certified Wells (SHP)

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This data set provides information about wells that are certified by the State of Missouri. The parent data set is the Wellhead Information Management System (WIMS)...

  15. Weigh-in-Motion Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  16. Automatic Traffic Recorder (ATR) Stations

    Data.gov (United States)

    Department of Homeland Security — The data included in the GIS Traffic Stations Version database have been assimilated from station description files provided by FHWA for Weigh-in-Motion (WIM), and...

  17. Paris, Texas. Saksamaal ja sinu peas / Kairi Prints

    Index Scriptorium Estoniae

    Prints, Kairi

    2010-01-01

    6.- 12. oktoobrini Tallinnas ja Tartus toimuval filmifestivalil "Uus Saksa Kino" saab vaadata Wim Wendersi muusikadokumentaale. "Film ja filosoofia" rubriigis koha- ja rahvusespetsiifika eksistentsist tänapäeva filmikunstis ja W. Wendersi filmist "Paris, Texas" (USA 1984)

  18. Teel tagasi laste juurde / Jaak Lõhmus

    Index Scriptorium Estoniae

    Lõhmus, Jaak

    2005-01-01

    Cannes'i 58. filmifestivalilt : Jean-Pierre ja Luc Dardenne'i "Laps" ("L'Enfant"), Jim Jarmuschi "Murtud lilled" ("Broken Flowers"), Wim Wendersi "Ära tule koputama" ("Don't Come Knocking"), Michael Haneke "Varjatud" ("Cache")

  19. Film Premiere: Arrows of time at exploratorium

    CERN Multimedia

    2007-01-01

    "Join award-wimming artist and filmmaker Ken McMullen for a uniqude presentation of films engaging ideas at the forefront of science and culture on Sunday, Apri 29 at 2pm at the Exploratorium." (1/3 page)

  20. The Turbulent Warm Ionized Medium: Emission Measure Distribution and MHD Simulations

    OpenAIRE

    Hill, Alex S.; Benjamin, Robert A.; Kowal, Grzegorz; Reynolds, Ronald J.; Haffner, L. Matthew; Lazarian, Alex

    2008-01-01

    We present an analysis of the distribution of H-alpha emission measures for the warm ionized medium (WIM) of the Galaxy using data from the Wisconsin H-Alpha Mapper (WHAM) Northern Sky Survey. Our sample is restricted to Galactic latitudes |b| > 10. We removed sightlines intersecting nineteen high-latititude classical H II regions, leaving only sightlines that sample the diffuse WIM. The distribution of EM sin |b| for the full sample is poorly characterized by a single normal distribution, bu...

  1. Current Status of Research Activities Related to THM-Coupled Processes in Buffer

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heui Joo; Lee, Changsoo; Choi, Young Chul; Lee, Minsoo; Kim, Jin Seop [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    For the purpose of enhancing the understanding of THM-coupled behavior in and around buffer, a computer code, KAERI-SIMULATOR, is being developed and verified by participating in Decovalex-2015 project. The THM data collected from this facility will be used to validate the KAERI-SIMULATOR.

  2. Current Status of Research Activities Related to THM-Coupled Processes in Buffer

    International Nuclear Information System (INIS)

    For the purpose of enhancing the understanding of THM-coupled behavior in and around buffer, a computer code, KAERI-SIMULATOR, is being developed and verified by participating in Decovalex-2015 project. The THM data collected from this facility will be used to validate the KAERI-SIMULATOR

  3. Development of DUPIC safeguards neutron counter

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Gil; Cha, Hong Ryul; Kim, Ho Dong; Hong, Jong Sook; Kang, Hee Young

    1999-08-01

    KAERI, in cooperation with LANL, developed DSNC (DUPIC Safeguards Neutron Counter) for safeguards implementing on DUPIC process which is under development by KAERI for direct use of spent PWR fuel in CANDU reactors. DSNC is a well-type neutron coincidence counter with substantial shielding to protect system from high gamma radiation of spent fuel. General development procedures in terms of design, manufacturing, fabrication, cold and hot test, performance test for DSNC authentication by KAERI-IAEA-LANL are described in this report. It is expected that the techniques related DSNC development and associated neutron detection and evaluation method could be applied for safeguards improvement. (Author). 20 refs., 16 tabs. 98 figs.

  4. Participation in the 1999 IAEA interlaboratory comparison on chemical analysis of groundwater

    Energy Technology Data Exchange (ETDEWEB)

    Joe, Kih Soo; Choi, Kwang Soon; Han, Sun Ho; Suh, Moo Yul; Park, Kyung Kyun; Choi, Ke Chun; Kim, Won Ho

    2000-08-01

    KAERI analytical laboratory participated in the 1999 IAEA interlaboratory comparison on chemical analysis of groundwater organized by IAEA Hydrology Laboratory(RAS/8/084). 13 items such as pH, electroconductivity, HCO{sub 3}, Cl, SO{sub 4}, NO{sub 3}, SiO{sub 2}, B, Li, Na, K, Ca, Mg were analyzed. The result of this program showed that KAERI laboratory was ranked within 10% range from top level. An analytical expert in KAERI attended the 'Consultants' Meeting' at IAEA headquater and prepared the guideline for chemical analysis of groundwater.

  5. ORNL Automated-In-Motion Evaluation Environment (AIMVEE) User Training and Testing Materials - U.S. Copyright TXu 1-797-273

    Energy Technology Data Exchange (ETDEWEB)

    Abercrombie, Robert K [ORNL; Sheldon, Frederick T [ORNL

    2012-01-01

    The AIMVEE/WIM system electronically retrieves deployment information, identifies vehicle automatically, and determines total weight, individual wheel weight, individual axle weights, axle spacing, and center-of-balance for any wheeled vehicle in motion. The AIMVEE/WIM system can also perform these functions statically for both wheel vehicles and cargo with information. The AIMVEE/WIM system incorporates digital images and applies cubing algorithms to determine length, width, height for cubic dimensions of both vehicle and cargo. Once all this information is stored, it electronically links to data collection and dissemination systems to provide actual weight and measurement information for planning, deployment, and in-transit visibility. The Static Scale Conversion (SSC) system is an unique enhancement to the AIMVEE/WIM system. It enables a SSC to weigh and measure vehicles and cargo dynamically (i.e., as they pass over the large scale and is included in the AIMVEE computer code base. The material copyrighted is the ORNL Automated-In-Motion Vehicle Evaluation Environment (AIMVEE)/Weigh-In-Motion User Training and Testing material. It includes instructional material in the set-up, operation and tear-down of the AIMVEE/WIM system. It also includes a final exam associated with the training.

  6. The Vertical Structure of Warm Ionised Gas in the Milky Way

    CERN Document Server

    Gaensler, B M; Chatterjee, S; Mao, S A

    2008-01-01

    We present a new joint analysis of pulsar dispersion measures and diffuse H-alpha emission in the Milky Way, which we use to derive the density, pressure and filling factor of the thick disk component of the warm ionised medium (WIM) as a function of height above the Galactic disk. By excluding sightlines at low Galactic latitude that are contaminated by HII regions and spiral arms, we find that the exponential scale-height of free electrons in the diffuse WIM is 1830 (+120, -250) pc, a factor of two larger than has been derived in previous studies. The corresponding inconsistent scale heights for dispersion measure and emission measure imply that the vertical profiles of mass and pressure in the WIM are decoupled, and that the filling factor of WIM clouds is a geometric response to the competing environmental influences of thermal and non-thermal processes. Extrapolating the properties of the thick-disk WIM to mid-plane, we infer a volume-averaged electron density 0.014 +- 0.001 cm^-3, produced by clouds of ...

  7. Numerical simulations of a propeller wake impacting

    Energy Technology Data Exchange (ETDEWEB)

    Hi, M.; Veitch, B.; Bose, N. [Memorial Univ. of Newfoundland, Faculty of Engineering and Applied Science, St. John' s, Newfoundland (Canada)]. E-mail: moqinhe@engr.mun.ca; Bruce, C.; Liu, P. [National Research Council Canada, Inst. for Ocean Technology, St. John' s, Newfoundland (Canada)

    2005-07-01

    This paper introduces a newly developed Wake Impingement Model (WIM) that aims to simulate of the dynamic loads induced by a three dimensional, unsteady, and strong vortical propeller wake. Simulations of loads on an ice class, tractor type podded propeller in straight ahead motion are presented consisting of mean loads on the propeller and side force on the pod and strut. The side force fluctuations for three different advance coefficients have also been predicted. These simulations were carried out by using a panel code, PROPELLA, with or without WIM. Simulated results were compared with and without WIM and with experimental data. The comparison of the propeller open water characteristics of two simulated results shown there is almost no difference between predictions with and without WIM. It was found by comparing with experimental data that the simulations of the side force on the pod and strut with WIM successfully captured the fluctuation which was dominated by the component at the blade passing frequency, although this was at a reduced level compared with the measurements. (author)

  8. Use of Finite Elements Analysis for a Weigh-in-Motion Sensor Design

    Directory of Open Access Journals (Sweden)

    Viorel Goanta

    2012-05-01

    Full Text Available High speed weigh-in-motion (WIM sensors are utilized as components of complex traffic monitoring and measurement systems. They should be able to determine the weights on wheels, axles and vehicle gross weights, and to help the classification of vehicles (depending on the number of axles. WIM sensors must meet the following main requirements: good accuracy, high endurance, low price and easy installation in the road structure. It is not advisable to use cheap materials in constructing these devices for lower prices, since the sensors are normally working in harsh environmental conditions such as temperatures between –40 °C and +70 °C, dust, temporary water immersion, shocks and vibrations. Consequently, less expensive manufacturing technologies are recommended. Because the installation cost in the road structure is high and proportional to the WIM sensor cross section (especially with its thickness, the device needs to be made as flat as possible. The WIM sensor model presented and analyzed in this paper uses a spring element equipped with strain gages. Using Finite Element Analysis (FEA, the authors have attempted to obtain a more sensitive, reliable, lower profile and overall cheaper elastic element for a new WIM sensor.

  9. Development of technical information processing systems

    International Nuclear Information System (INIS)

    The major goal of this project is to develop a more efficient information management system by connecting the KAREI serials database which enable the users to access from their own laboratory facilities through KAREI-NET. The importance of this project is to make the serials information of KAERI easily accessible to users as valuable resources for R and D activities. The results of the project are as follows. 1) Development of the serials database and retrieval system enabled us to access to the serials holding information through KAERI-NET. 2) The database construction establishes a foundation for the management of 1,600 serials held in KAERI. 3) The system can be applied not only to KAERI but also to similar medium-level libraries. (Author)

  10. CANDU RU fuel manufacturing basic technology development and advanced fuel verification tests

    International Nuclear Information System (INIS)

    A PHWR advanced fuel named the CANFLEX fuel has been developed through a KAERI/AECL joint Program. The KAERI made fuel bundle was tested at the KAERI Hot Test Loop for the performance verification of the bundle design. The major test activities were the fuel bundle cross-flow test, the endurance fretting/vibration test, the freon CHF test, and the fuel bundle heat-up test. KAERI also has developing a more advanced PHWR fuel, the CANFLEX-RU fuel, using recovered uranium to extend fuel burn-up in the CANDU reactors. For the purpose of proving safety of the RU handling techniques and appraising feasibility of the CANFLEX-RU fuel fabrication in near future, a physical, chemical and radiological characterization of the RU powder and pellets was performed. (author). 54 refs., 46 tabs., 62 figs

  11. Korea signs for 2nd CANDU at Wolsong

    International Nuclear Information System (INIS)

    The sale of a second CANDU 6 reactor to Korea for the Wolsong site is discussed in relation to nuclear power in Korea, the Korean economy generally, Canadian trade with Korea, and cooperation between AECL and KAERI

  12. CANDU RU fuel manufacturing basic technology development and advanced fuel verification tests

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chang Hwan; Chang, S.K.; Hong, S.D. [and others

    1999-04-01

    A PHWR advanced fuel named the CANFLEX fuel has been developed through a KAERI/AECL joint Program. The KAERI made fuel bundle was tested at the KAERI Hot Test Loop for the performance verification of the bundle design. The major test activities were the fuel bundle cross-flow test, the endurance fretting/vibration test, the freon CHF test, and the fuel bundle heat-up test. KAERI also has developing a more advanced PHWR fuel, the CANFLEX-RU fuel, using recovered uranium to extend fuel burn-up in the CANDU reactors. For the purpose of proving safety of the RU handling techniques and appraising feasibility of the CANFLEX-RU fuel fabrication in near future, a physical, chemical and radiological characterization of the RU powder and pellets was performed. (author). 54 refs., 46 tabs., 62 figs.

  13. Process Faults Analysis and Design Considerations for Pyroprocess Hot Cell Safety

    Energy Technology Data Exchange (ETDEWEB)

    You, G. S.; Choung, W. M.; Ku, J. H.; Moon, S. I.; Kim, H. D. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    KAERI (Korea Atomic Energy Research Institute) has been studied the pyroprocess since 1997. For demonstration of pyroprocess, KAERI developed two facilities, the ACPF (Advanced spent fuel Conditioning Process Facility) and the PRIDE (PyRoprocess-Integrated inactive DEmonstration facility). From 2013 KAERI performs a pre-conceptual design of the ESPF (Engineering-Scale Pyroprocess Facility). In this paper, the process faults analysis and design considerations for pyroprocess hot cell safety are described. KAERI has been developing a pyroprocess for conditioning and reutilization of PWR spent nuclear fuels. The safety evaluations of the pyroprocess facilities were performed to confirm the safe design. The process safety as one of the safety evaluations was analyzed by the faults tree method. The corresponding safe design considerations for each fault type were also considered.

  14. Optic Fiber-Based Dynamic Pressure Sensor

    Institute of Scientific and Technical Information of China (English)

    Jiu-Lin Gan; Hai-Wen Cai; Jian-Xin Geng; Zheng-Qing Pan; Rong-Hui Qu; Zu-Jie Fang

    2008-01-01

    Weigh-in-Motion(WIM) technique is the process of measuring the dynamic tire forces of a moving vehicle and estimating the corresponding tire loads of the static vehicle. Compared with the static weigh station, WIM station is an efficient and cost effective choice that will minimize unneccessary stops and delay for truckers. The way to turn birefringence of single-mode fiber into a prime quality for a powerful and reliable sensor is shown. Preliminary results for the development of a weigh-in-motion (WIM) technique based on sagnac-loop sensor are presented. After a brief description of the sensor and its principle of operation, the theoretical model is developed. Then, a full characterization made in static conditions is presented.

  15. A Simple Weighted Integration Method for Calculating Surface Tension Force to Suppress Parasitic Flow in the Level Set Approach%权重积分方法计算界面张力消除表面"寄生"流

    Institute of Scientific and Technical Information of China (English)

    王剑峰; 杨超; 毛在砂

    2006-01-01

    Parasitic flows may occur in the numerical simulation of incompressible multiphase flow due to errors in the calculation of surface tension terms, specifically for the curvature and unit normal vector. An improved method for calculating the surface tension based on the level set approach is proposed, in which the contribution of not only the center node but also the rest area of a control volume to the calculation of surface tension is considered in a balanced manner. The weighted integration method (WIM) is more consistent with the concept of a banded interface in the level set method. It is applied to the temporal evolution of a two-dimensional neutrally buoyant liquid drop and a buoyancy driven deformable bubble in an immiscible fluid for the validation of WIM. The results show that the parasitic flows are evidently suppressed by the weighted integration method. The weight factors for WIM in 3-D cases are also suggested.

  16. Evidence for dust emission in the Warm Ionised Medium using WHAM data

    CERN Document Server

    Lagache, G; Reynolds, R J; Tufte, S L

    1999-01-01

    We have used the WHAM H_alpha survey and Leiden/Dwingeloo HI data to decompose the Far-infrared emission (from 100 to 1000 micron) at high Galactic latitude into components associated with the Warm Ionised Medium (WIM) and the Warm Neutral Medium (WNM). This decomposition is possible for the first time thanks to preliminary WHAM data that cover a significant fraction of the sky (about 10%). We confirm the first detection of dust emission from the WIM (Lagache et al. 1999) and show that the WIM dust temperature and emissivity are very similar to those in the WNM. The analysis suggests moreover that about 25% of the far-IR dust emission at high galactic latitude is uncorrelated with the HI gas. The decomposition again reveals a Cosmic Far-Infrared Background (CFIRB) which is determined for the first time from 100 to 1000 micron using two independant gas tracers.

  17. Analysis of benchmarks on the reactivity temperature coefficient using new libraries based on ENDF/B-VI (release 5) and JEF2-2 data

    Energy Technology Data Exchange (ETDEWEB)

    Erradi, L.; Htet, A.; Chakir, E

    2001-06-01

    This paper presents, the analysis of discrepancies between calculation and experiments in the prediction of isothermal moderator temperature coefficient of a set of lattice experiments, using WIMSD4, WIMSD5B and APOLLO1 lattice codes. In this analysis we have used the original cross sections libraries (CEA-86 library for APOLLO1 and both of 1981 and 1986 libraries for WIMS) and the updated ones based on JEF2.2 data for APOLLO code and both of ENDF/B6 and JEF2.2 data for WIMS code. We have also analysed the numerical benchmark proposed by Mosteller to evaluate the accuracy in predicting Doppler coefficient in light water type lattices. This study on Doppler coefficient was performed using, in addition to APOLLO and WIMS codes, the Monte Carlo code MCNP4B for which a new library based on ENDF/B6 nuclear data file, have been processed using the NJOY system.

  18. Analysis of benchmarks on the reactivity temperature coefficient using new libraries based on ENDF/B-VI (release 5) and JEF2-2 data

    CERN Document Server

    Erradi, L; Chakir, E

    2001-01-01

    This paper presents, the analysis of discrepancies between calculation and experiments in the prediction of isothermal moderator temperature coefficient of a set of lattice experiments, using WIMSD4, WIMSD5B and APOLLO1 lattice codes. In this analysis we have used the original cross sections libraries (CEA-86 library for APOLLO1 and both of 1981 and 1986 libraries for WIMS) and the updated ones based on JEF2.2 data for APOLLO code and both of ENDF/B6 and JEF2.2 data for WIMS code. We have also analysed the numerical benchmark proposed by Mosteller to evaluate the accuracy in predicting Doppler coefficient in light water type lattices. This study on Doppler coefficient was performed using, in addition to APOLLO and WIMS codes, the Monte Carlo code MCNP4B for which a new library based on ENDF/B6 nuclear data file, have been processed using the NJOY system.

  19. Novel weigh-in-motion system based on FBGs

    Institute of Scientific and Technical Information of China (English)

    LIU Quan-jie; JIANG Ming-shun; LI Yan-hua; YANG Hong-mei; ZENG Li

    2009-01-01

    In this weigh-in-motion (WIM) research, a novel fiber Bragg grating (FBG)-based weigh-in-motion (WIM) system was introduced. The design derived from the idea using in-service bridge abutments as the weigh scale. The bridge beam was replaced by a piece of steel plate which supports the weight of the traveling vehicle. All weights would be finally transferred into the tubes where four FBGs were attached and could record the weight-induced strains by shifting their Bragg wavelengths. The system identification algorithm based on parameters estimation was initiated. Over 40-ton load had been applied on the system and the experimental results showed a good repeatability and linearity. The system resolution had been achieved as low as 10 kg. Compared with other designs of fiber-optic WIM systems, this design is easy and reliable.

  20. Establishment of ANSI N13.11 X-ray radiation fields for personal dosimetry performance test by computation and experiment.

    OpenAIRE

    Kim, J L; Kim, B. H.(Seoul National University, 151-742, Seoul, South Korea); Chang, S Y; J. K. Lee

    1997-01-01

    This paper describes establishment by computational and experimental methods of the American National Standard Institute (ANSI) N13.11 X-ray radiation fields by the Korea Atomic Energy Research Institute (KAERI). These fields were used in the standard irradiations of various personal dosimeters for the personal dosimetry performance test program performed by the Ministry of Science and Technology of Korea in the autumn of 1995. Theoretical X-ray spectra produced from two KAERI X-ray generator...

  1. Country presentation

    International Nuclear Information System (INIS)

    The development of the Web-Portal for the ANENT is one of the action plans under activity 1 led by KAERI, ROK. The web-based networking is intended to establish an effective and sustainable focal point. KAERI had developed the Web-Portal for the ANENT and ANENT members were requested to evaluate the Web-Portal. Malaysia has applied SWOT analysis to evaluate the Web-Portal, analyzing the strengths, weaknesses, opportunities, threats, challenges and the way forward

  2. FLYSAFE, nowcasting of in flight icing supporting aircrew decision making process

    Science.gov (United States)

    Drouin, A.; Le Bot, C.

    2009-09-01

    FLYSAFE is an Integrated Project of the 6th framework of the European Commission with the aim to improve flight safety through the development of a Next Generation Integrated Surveillance System (NGISS). The NGISS provides information to the flight crew on the three major external hazards for aviation: weather, air traffic and terrain. The NGISS has the capability of displaying data about all three hazards on a single display screen, facilitating rapid pilot appreciation of the situation by the flight crew. Weather Information Management Systems (WIMS) were developed to provide the NGISS and the flight crew with weather related information on in-flight icing, thunderstorms, wake-vortex and clear-air turbulence. These products are generated on the ground from observations and model forecasts. WIMS supply relevant information on three different scales: global, regional and local (over airport Terminal Manoeuvring Area). Within the flysafe program, around 120 hours of flight trials were performed during February 2008 and August 2008. Two aircraft were involved each with separate objectives : - to assess FLYSAFE's innovative solutions for the data-link, on-board data fusion, data-display, and data-updates during flight; - to evaluate the new weather information management systems (in flight icing and thunderstorms) using in-situ measurements recorded on board the test aircraft. In this presentation we will focus on the in-flight icing nowcasting system developed at Météo France in the framework of FLYSAFE: the local ICE WIMS. The local ICE WIMS is based on data fusion. The most relevant information for icing detection is extracted from the numerical weather prediction model, the infra-red and visible satellite imagery and the ground weather radar reflectivities. After a presentation of the local ICE WIMS, we detail the evaluation of the local ICE WIMS performed using the winter and summer flight trial data.

  3. Fabrication of a CANFLEX-RU designed bundle for power ramp irradiation test in NRU

    International Nuclear Information System (INIS)

    The BDL-443 CANFLEX-RU bundle AKW was fabricated at Korea Atomic Energy Research Institute (KAERI) for power ramp irradiation testing in NRU reactor. The bundle was fabricated with IDR and ADU fuel pellets in adjacent elements and contains fuel pellets enriched to 1.65 wt% 235U in the outer and intermediate rings and also contains pellets enriched to 2.00 wt% 235U in the inner ring. This bundle does not have a center element to allow for insertion on a hanger bar. KAERI produced the IDR pellets with the IDR-source UO2 powder supplied by BNFL. ADU pellets were fabricated and supplied by AECL. Bundle kits (Zircaloy-4 end plates, end plugs, and sheaths with brazed appendages) manufactured at KAERI earlier in 1996 were used for the fabrication of the bundle. The CANFLEX bundle was fabricated successfully at KAERI according to the QA provisions specified in references and as per relevant KAERI drawings and technical specification. This report covers the fabrication activities performed at KAERI. Fabrication processes performed at AECL will be documented in a separate report

  4. Englemøtet over Berlin

    DEFF Research Database (Denmark)

    Ørjasæter, Kristin

    2006-01-01

    This reading of Dag Solstads novel 16.07.41 (2002) is focussed on the presentation of Berlin in the text. The article also a discusses the angel-theme that can be find in this novel as well as in Wim Wenders Der himmel über Berlin (1987).......This reading of Dag Solstads novel 16.07.41 (2002) is focussed on the presentation of Berlin in the text. The article also a discusses the angel-theme that can be find in this novel as well as in Wim Wenders Der himmel über Berlin (1987)....

  5. An outstanding guest

    CERN Multimedia

    2004-01-01

    The person celebrating CERN's 25th anniversary whose photograph we published last week was not just any guest. Readers have pointed out that it was Wim Klein, whose remarkable abilities are part of CERN's history. Well known as one of the best "human calculators", Wim was recruited by CERN in 1957 to verify computer programs, which at the time were still stumbling. Moreover, he regularly beat their speed in calculating and gave breath-taking demonstrations. During one such demonstration in September 1973, he calculated the 19th root of a 133-digit number in less than 2 minutes !

  6. Prototype Weigh-In-Motion Performance

    Energy Technology Data Exchange (ETDEWEB)

    Abercrombie, Robert K [ORNL; Beshears, David L [ORNL; Hively, Lee M [ORNL; Scudiere, Matthew B [ORNL; Sheldon, Frederick T [ORNL

    2006-10-01

    Oak Ridge National Laboratory (ORNL) has developed and patented methods to weigh slowly moving vehicles. We have used this technology to produce a portable weigh-in-motion system that is robust and accurate. This report documents the performance of the second-generation portable weigh-in-motion prototype (WIM Gen II). The results of three modes of weight determination are compared in this report: WIM Gen II dynamic mode, WIM Gen II stop-and-go mode, and static (parked) mode on in-ground, static scales. The WIM dynamic mode measures axle weights as the vehicle passes over the system at speeds of 3 to 7 miles per hour (1.3 to 3.1 meters/second). The WIM stop-and-go mode measures the weight of each axle of the vehicle as the axles are successively positioned on a side-by-side pair of WIM measurement pads. In both measurement modes the center of balance (CB) and the total weight are obtained by a straight-forward calculation from axle weights and axle spacings. The performance metric is measurement error (in percent), which is defined as 100 x (sample standard deviation)/(average); see Appendix A for details. We have insufficient data to show that this metric is predictive. This report details the results of weight measurements performed in May 2005 at two sites using different types of vehicles at each site. In addition to the weight measurements, the testing enabled refinements to the test methodology and facilitated an assessment of the influence of vehicle speed on the dynamic-mode measurements. The initial test at the National Transportation Research Center in Knoxville, TN, involved measurements of passenger and light-duty commercial vehicles. A subsequent test at the Arrival/Departure Airfield Control Group (A/DACG) facility in Ft. Bragg, NC, involved military vehicles with gross weights between 3,000 and 75,000 pounds (1,356 to 33,900 kilograms) with a 20,000-pound (9,040 kilograms) limit per axle. For each vehicle, four or more separate measurements were done

  7. Eestlased kaotasid Telekomi aktsiatega kaks ja pool miljardit / Erkki Erilaid

    Index Scriptorium Estoniae

    Erilaid, Erkki

    2001-01-01

    Eesti Telekomi aktsia püstitas uue odavusrekordi, kukkudes päevaga 6,35% 44,25 kroonini. Diagramm: Eesti Telekom taas rekordmadal. Vt. samas: Kangus, Aivo. Rasked valikud. Arvamust avaldavad: Wim Duisenberg, Siim Kallas ja Horst Koehler

  8. Cross sections for fuel depletion and radioisotope production calculations in TRIGA reactors

    International Nuclear Information System (INIS)

    For TRIGA Reactors, the fuel depletion and isotopic inventory calculations, depends on the computer code and in the cross sections of some important actinides used. Among these we have U-235, U-238, Pu-239, Pu-240 and Pu-241. We choose ORIGEN2, a code with a good reputation in this kind of calculations, we observed the cross sections for these actinides in the libraries that we have (PWR's and BWR), the fission cross section for U-235 was about 50 barns. We used a PWR library and our results were not satisfactory, specially for standard elements. We decided to calculate cross sections more suitable for our reactor, for that purpose we simulate the standard and FLIP TRIGA cells with the transport code WIMS. We used the fuel average flux and COLAPS (a home made program), to generate suitable cross sections for ORIGEN2, by collapsing the WIMS library cross sections of these nuclides. For the radioisotope production studies using the Central Thimble, we simulate the A and B rings and used the A average flux to collapse cross sections. For these studies, the required nuclides sometimes are not present in WIMS library, for them we are planning to process the ENDF/B data, with NJOY system, and include the cross sections to WIMS library or to collapse them using the appropriate average-flux and the program COLAPS. (author)

  9. Neutronics and thermal hydraulics feedback models of the Harwell materials testing reactors DIDO and PLUTO: I Neutronics analysis

    International Nuclear Information System (INIS)

    Neutronics modelling of the Harwell MTRs DIDO and PLUTO has been achieved in the WIMS-E framework using (r,z) and (x,y) two dimensional diffusion theory. The modelling takes into account fuel burnup and the presence of the coarse control arms and experimental rigs. The modelling is validated by comparisons with measurements of thermal and fast flux distributions. (author)

  10. Neutronics and thermal hydraulics modelling of the Harwell Materials Testing Reactors DIDO and PLUTO

    International Nuclear Information System (INIS)

    A detailed 2-D cylindrical diffusion theory neutronics model is presented for the Harwell reactors DIDO and PLUTO, based on the WIMS-E program. The model for these highly asymmetric reactors allows for the presence of the various control systems, experimental rigs and fuel burnup. Comparisons made with measurements of burnup and of radial and axial flux distributions validate the approach. (author)

  11. Analysis of axle and vehicle load properties through Bayesian networks based on weigh-in-motion data

    NARCIS (Netherlands)

    Morales Napoles, O.; Steenbergen, R.D.J.M.

    2014-01-01

    Weigh-in-Motion (WIM) systems are used, among other applications, in pavement and bridge reliability. The system measures quantities such as individual axle load, vehicular loads, vehicle speed, vehicle length and number ofaxles. Because ofthe nature ofúamc configuration, the quantities measured are

  12. Atheïstische religiositeit : Een pragmatische analyse in de geest van William James, Erich Fromm en Leo Apostel

    NARCIS (Netherlands)

    Moer, Van Wim

    2012-01-01

    Atheïsme en religiositeit lijken elkaars absolute tegenpolen. Filosoof Wim Van Moer stelt deze intuïtieve, ook onder atheïsten wijdverspreide overtuiging ter discussie. Deze analyse onthult dat de religieuze ervaring niet verbonden hoeft te zijn met een geloof in een bovennatuurlijke entiteit of rea

  13. The wisconsin Ha mapper: a new look at the warm ionized medium

    Directory of Open Access Journals (Sweden)

    L. M. Haffner

    2000-01-01

    Full Text Available El relevamiento en H-Alpha de Wisconsin (WHAM ha cubierto todo el cielo del norte en H desde Kitt Peak, Arizona. Usando un espectr ometro Fabry-Perot de alta transmisividad, con etal on doble de 15 cm y un CCD de alta sensibilidad, el relevamiento WHAM ha obtenido el primer mapa con velocidades calibradas en H en emisi on de nuestra Galaxia. Una zona amplia, que incluye el brazo Local (Ori on y el brazo de Perseo, tambi en ha sido observada por el WHAM en las l neas de [S II] y [N II]. Estos nuevos datos muestrean directamente y por primera vez, las condiciones f sicas a gran escala del medio ionizado tibio (WIM. Las tendencias de los cocientes de l neas sugieren que las variaciones en la temperatura son muestreadas por los mapas de [N II]/H y [S II]/H . Dado que estos cocientes se incrementan fuertemente en regiones alejadas del plano Gal actico, revelan un incremento sustancial en la temperatura del WIM del halo. Adem as de este resultado, los datos revelan una nueva region H II excitada por una estrella B, dan una medida de la escala de altura de los electrones del WIM y, del cociente [S II]/[N II], proveen nueva informaci on sobre la ionizaci on del WIM.

  14. Sorteerwater gereinigd met ozon

    NARCIS (Netherlands)

    PPO Fruit,

    2009-01-01

    Energie uit de lucht wordt het tegenwoordig ook wel genoemd. Futuroloog Wim de Ridder weet het zeker : uit zonne-energie gehaalde elektriciteit wordt steeds goedkoper. Over zo'n tien jaar komt er een omslag en wordt het mogelijk stroom voor een habbekrats te produceren

  15. Näitused / Mari Sobolev

    Index Scriptorium Estoniae

    Sobolev, Mari, 1968-

    1998-01-01

    Tallinna XI graafikatriennaal. Rotermanni soolaladu: "Puudutus"; Kunstihoone: "Puutujad"; Rahvusraamatukogu: Laste ja noorte graafikanäitus; Kastellaanimaja galerii: Wim Lamboo (s. 1949) "Eesti kunstnike portreed 1997" (fotograafia); Tallinna Botaanikaaed: "Maised rõõmud"; Rahvusraamatukogu: Antanas Sutkus (s. 1939) "Pro memoria" (fotograafia); Tammsaare majamuuseum: Eve Pärnaste "Ülelend" (maalid); Haapsalu Linnagalerii: Paul Allik "Seisundid" (aktimaalid).

  16. Access, Equity, and Opportunity. Women in Machining: A Model Program.

    Science.gov (United States)

    Warner, Heather

    The Women in Machining (WIM) program is a Machine Action Project (MAP) initiative that was developed in response to a local skilled metalworking labor shortage, despite a virtual absence of women and people of color from area shops. The project identified post-war stereotypes and other barriers that must be addressed if women are to have an equal…

  17. The numerical benchmark CB2-S, final evaluation

    International Nuclear Information System (INIS)

    In this paper are final results of numerical benchmark CB2-S compared (activity, gamma and neutron sources, concentration of important nuclides and decay heat). The participants are: Vladimir Chrapciak (SCALE), Ludmila Markova (SCALE), Svetlana Zabrodskaja (SCALA), Pavel Mikolas (WIMS). Eva Tinkova (HELIOS) and Maria Manolova (SCALE) (Authors)

  18. Ion-Neutral Collisions in the Interstellar Medium: Wave Damping and Elimination of Collisionless Processes

    Science.gov (United States)

    Spangler, Steven R.; Savage, Allison H.; Redfield, Seth

    2011-09-01

    Most phases of the interstellar medium contain neutral atoms in addition to ions and electrons. This introduces differences in plasma physics processes in those media relative to the solar corona and the solar wind at a heliocentric distance of 1 astronomical unit. In this paper, we consider two well-diagnosed, partially-ionized interstellar plasmas. The first is the Warm Ionized Medium (WIM) which is probably the most extensive phase in terms of volume. The second is the gas of the Local Clouds of the Very Local Interstellar Medium (VLISM). Ion-neutral interactions seem to be important in both media. In the WIM, ion-neutral collisions are relatively rare, but sufficiently frequent to damp magnetohydrodynamic (MHD) waves (as well as propagating MHD eddies) within less than a parsec of the site of generation. This result raises interesting questions about the sources of turbulence in the WIM. In the case of the VLISM, the ion-neutral collision frequency is higher than that in the WIM, because the hydrogen is partially neutral rather than fully ionized. We present results showing that prominent features of coronal and solar wind turbulence seem to be absent in VLISM turbulence. For example, ion temperature does not depend on ion mass. This difference may be due to ion-neutral collisions, which distribute power from more effectively heated massive ions such as iron to other ion species and neutral atoms.

  19. Diplomacy Central%透视欧洲央行新掌门人--特莱切特

    Institute of Scientific and Technical Information of China (English)

    2003-01-01

    @@ The European Central Bank has a new president:Conservative Jean-Claude Trichet is expected to weigh his words more carefully than his predecessor Wim Duisenberg. Apart from that, he will probably not change the policies of the Central Bank much.

  20. Study of power distribution in the CZP, HFP and normal operation states of VVER-1000 (Bushehr) nuclear reactor core by coupling nuclear codes

    International Nuclear Information System (INIS)

    Highlights: • Simulation of one-sixth of VVER-1000 reactor core by WIMS-D4 based on core symmetry. • Obtaining the cross sections of some nuclides by WIMS-D4 from BOC to EOC. • Transferring the obtained cross sections into CITATION as inputs for codes coupling. • Obtaining neutron fluxes and power by CITATION and program cycle in the CZP and HFP. • Distribution depiction of neutron fluxes and power in CZP, HFP and normal operation. - Abstract: In this research, the simulation of one-sixth of VVER-1000 (Bushehr) reactor core is carried out by WIMS-D4 nuclear code, based on symmetry of core and also by information obtained from FSAR. The cross sections of some nuclides are obtained by WIMS-D4 from the beginning of cycle (BOC) to the end of cycle (EOC), and they are transferred into the CITATION code as inputs. In the next stage, the amounts of neutron fluxes and power of reactor core are obtained by CITATION code in the CZP and HFP states. Then, the received products are returned again into the extended program cycle, thereby distributions of neutron fluxes and power are finally depicted. In the meantime, the space distribution of neutron fluxes and power throughout the core are presented during the normal operation by this simulation. It can be inferred that if the reactor operation continues, a flat power distribution will be made in the reactor core that might cause maximum power

  1. Rock-hard coatings

    NARCIS (Netherlands)

    Muller, M.

    2007-01-01

    Aircraft jet engines have to be able to withstand infernal conditions. Extreme heat and bitter cold tax coatings to the limit. Materials expert Dr Ir. Wim Sloof fits atoms together to develop rock-hard coatings. The latest invention in this field is known as ceramic matrix composites. Sloof has sign

  2. An Assessment of Resonance Treatment in WIMSD-5B

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Won Young; You, Guk Jong; Min, Byung Joo; Park, Joo Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    WIMSD-5B is a lattice code with a depletion capability for the analysis of reactor physics problems related to a design and safety. It is released from the OECD/NEA Data Bank in 1998 and is now being used widely for thermal research and power reactor calculations. The purpose of this study is to assess and improve the resonance treatment method in WIMSD- 5B, through the introduction of a new method with a high accuracy in treating the resonance, as one of the development works for WIMS/CANDU, which is being developed for replacing WIMS-AECL, for the physics analysis of CANDU reactors. In this article, we specifically describe the recent improvements in the resonance integral method using the Carlvik's approximation. As a result, a comparison for the resonance calculation on the CANDU-6 fuel lattice was performed between the WIMSD-5B code and the WIMS/CANDU code with the 69-energy groups of the ENDF/B-VI nuclear data library and the WIMS-AECL code with the 89-energy group of the ENDF/B-VI nuclear data library.

  3. Progress on Developing an Interface Program between WIMSD-5B and RFSP

    Energy Technology Data Exchange (ETDEWEB)

    You, Guk Jong; Kim, Won Young; Park, Joo Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    WIMS (Winfrith Improved Multigroup Scheme) code is a multi-group transport code for the reactor lattice calculations which includes a fuel depletion or burn-up routine. The code, created at the United Kingdom Atomic Energy Authority Establishment, Winfrith (AEEW), was intended to perform the lattice calculations with an acceptable accuracy for the analysis of the experiments in a wide range of geometries. As one of its branches, WIMSD-5B is a code which was released from OECD/NEA Data Bank in 1998 and now has been used widely for thermal research and power reactor calculation. Also one of WIMS codes, WIMS-AECL, has been developed by AECL in Canada as an independent version of the original AEEW code. While WIMS-AECL produces a data file which can generate the information required by other code such as RFSP, WIMSD-5B does not. The data file is used for the reactor analysis by WIMSAECL in connection with RFSP. This study is to develop an interface data file (Tape 16) of WIMSD-5B with RFSP and to develop a process utility to provide the group collapsing and cell average cross-section generation for a CANDU-6 core analysis on the WINDOW system. With this utility, the physics analysis of a CANDU-6 reactor will be performed by RFSP code using the lattice parameters generated by WIMSD-5B.

  4. Notitie over het uitplanten van korstmossen

    NARCIS (Netherlands)

    Geraerdts, W.H.J.M.; Ketner-Oostra, H.G.M.

    2006-01-01

    In de voormalige tuin van Wim Geraedts (Wijchen, Gelderland) blijkt het uitplanten van korstmossen een sukses te zijn. Het gaat om enkele Cladonia-soorten, een Cladina- en twee Peltigera-soorten. Het biotoop waarin ze uitgezet zijn, ligt op een wal van heideplaggen om een kunstmatig hoogveentje met

  5. 妙用imagex快速给Vista减肥

    Institute of Scientific and Technical Information of China (English)

    俞木发

    2007-01-01

    第1步把Vista安装光盘中的install.wim文件复制到“e:\\”下,然后启动命令提示符窗口,执行命令“imagex/apply e:\\install.wim 1 j:\\vista”,将install.wim的第一部分提取到j:\\vista下。

  6. Our Hitler - A Film by Hans-Jürgen Syberberg

    NARCIS (Netherlands)

    T. Elsaesser

    2012-01-01

    A good deal of the interest aroused by the so-called New German Cinema in the 1970s and 1980s was generated by the impression - as well as the expectation - that the films of Werner Herzog, Rainer Werner Fassbinder, Hans-Jürgen Syberberg, Wim Wenders, and others were not just another European new wa

  7. Excitation of the diffuse ionized gas in galaxies

    Directory of Open Access Journals (Sweden)

    Crystal L. Martin

    2000-01-01

    Full Text Available Se revisan las propiedades del gas ionizado difuso (DIG en galaxias cercanas con formaci on estelar, enfatizando la evidencia para un mecanismo de excitaci on adicional a la fotoionizaci on estelar. Discuto la pregunta frecuentemente hecha sobre si el DIG en galaxias externas es similar al medio ionizado tibio (WIM descrito en esta reuni on por Reynolds y Ha ner.

  8. Excitation of the diffuse ionized gas in galaxies

    OpenAIRE

    Martin, Crystal L.

    2000-01-01

    Se revisan las propiedades del gas ionizado difuso (DIG) en galaxias cercanas con formaci on estelar, enfatizando la evidencia para un mecanismo de excitaci on adicional a la fotoionizaci on estelar. Discuto la pregunta frecuentemente hecha sobre si el DIG en galaxias externas es similar al medio ionizado tibio (WIM) descrito en esta reuni on por Reynolds y Ha ner.

  9. Warm ionized gas in CALIFA early-type galaxies. 2D emission-line patterns and kinematics for 32 galaxies

    Science.gov (United States)

    Gomes, J. M.; Papaderos, P.; Kehrig, C.; Vílchez, J. M.; Lehnert, M. D.; Sánchez, S. F.; Ziegler, B.; Breda, I.; Dos Reis, S. N.; Iglesias-Páramo, J.; Bland-Hawthorn, J.; Galbany, L.; Bomans, D. J.; Rosales-Ortega, F. F.; Cid Fernandes, R.; Walcher, C. J.; Falcón-Barroso, J.; García-Benito, R.; Márquez, I.; Del Olmo, A.; Masegosa, J.; Mollá, M.; Marino, R. A.; González Delgado, R. M.; López-Sánchez, Á. R.; Califa Collaboration

    2016-04-01

    Context. The morphological, spectroscopic, and kinematical properties of the warm interstellar medium (wim) in early-type galaxies (ETGs) hold key observational constraints to nuclear activity and the buildup history of these massive, quiescent systems. High-quality integral field spectroscopy (IFS) data with a wide spectral and spatial coverage, such as those from the CALIFA survey, offer an unprecedented opportunity for advancing our understanding of the wim in ETGs. Aims: This article centers on a 2D investigation of the wim component in 32 nearby (≲150 Mpc) ETGs from CALIFA, complementing a previous 1D analysis of the same sample. Methods: The analysis presented here includes Hα intensity and equivalent width (EW) maps and radial profiles, diagnostic emission-line ratios, and ionized-gas and stellar kinematics. It is supplemented by τ-ratio maps, which are a more efficient means to quantify the role of photoionization by the post-AGB stellar component than alternative mechanisms (e.g., AGN, low-level star formation). Results: Confirming and strengthening our previous conclusions, we find that ETGs span a broad continuous sequence in the properties of their wim, exemplified by two characteristic classes. The first (type i) comprises systems with a nearly constant EW(Hα) in their extranuclear component, which quantitatively agrees with (but is no proof of) the hypothesis that photoionization by the post-AGB stellar component is the main driver of extended wim emission. The second class (type ii) stands for virtually wim-evacuated ETGs with a very low (≤0.5 Å), outwardly increasing EW(Hα). These two classes appear indistinguishable from one another by their LINER-specific emission-line ratios in their extranuclear component. Here we extend the tentative classification we proposed previously by the type i+, which is assigned to a subset of type i ETGs exhibiting ongoing low-level star-forming activity in their periphery. This finding along with faint

  10. The relationship between fatty acid profiles in milk identified by Fourier transform infrared spectroscopy and onset of luteal activity in Norwegian dairy cattle.

    Science.gov (United States)

    Martin, A D; Afseth, N K; Kohler, A; Randby, Å; Eknæs, M; Waldmann, A; Dørum, G; Måge, I; Reksen, O

    2015-08-01

    To investigate the feasibility of milk fatty acids as predictors of onset of luteal activity (OLA), 87 lactations taken from 73 healthy Norwegian Red cattle were surveyed over 2 winter housing seasons. The feasibility of using frozen milk samples for dry-film Fourier transform infrared (FTIR) determination of milk samples was also tested. Morning milk samples were collected thrice weekly (Monday, Wednesday, Friday) for the first 10 wk in milk (WIM). These samples had bronopol (2-bromo-2-nitropropane-1,3-diol) added to them before being frozen at -20°C, thawed, and analyzed by ELISA to determine progesterone concentration and the concentrations of the milk fatty acids C4:0, C14:0, C16:0, C18:0, and cis-9 C18:1 as a proportion of total milk fatty acid content using dry-film FTIR, and averaged by WIM. Onset of luteal activity was defined as the first day that milk progesterone concentrations were >3 ng/mL for 2 successive measurements; the study population was categorized as early (n=47) or late (n=40) OLA, using the median value of 21 DIM as the cutoff. Further milk samples were collected 6 times weekly, from morning and afternoon milkings, these were pooled by WIM, and one proportional sample was analyzed fresh for fat, protein, and lactose content by the dairy company Tine SA, using traditional FTIR spectrography in the wet phase of milk. Daily energy-balance calculations were performed in 42 lactations and averaged by WIM. Animals experiencing late OLA had a more negative energy balance in WIM 1, 3, 4, and 5, with the greatest differences been seen in WIM 3 and 4. A higher proportion of the fatty acids were medium chained, C14:0 and C16:0, in the early than in the late OLA group from WIM 1. In WIM 4, the proportion of total fatty acid content that was C16:0 predicted late OLA, with 74% sensitivity and 80% specificity. The long-chain proportion of the fatty acids C18:0 and cis-9 C18:1 were lower in the early than in the late OLA group. Differences were greatest in

  11. 串联集装箱动态单箱称重系统研究%Research of Tandem Container's Weigh-in-motion System for a Single Container

    Institute of Scientific and Technical Information of China (English)

    刘忠杰; 何锋; 宋小波; 周培莹; 朱擎飞; 蒋欣晟

    2012-01-01

    提出了一种基于串联式集装箱的动态单箱称重系统的设计方法.首先,介绍了该系统的硬件组成结构,构建了动态称重系统的模型;其次,采用RBF神经网络对系统模型进行了仿真,并建立了重心偏移自适应修正算法;最后,以Visual Studio 2010为开发环境研发了一套动态单箱称重软件,该软件操作简单、实用性强,提高了集装箱动态称重效率.整个系统实现了模型构建、数据采集、算法仿真、数据存储、查询和打印等功能,并且称重误差率控制在3%以内,有较好的商业应用前景.%A weigh-in-motion (WIM) for a single container system based on tandem container was proposed. First, the composition structure of hardware in this system was introduced, and WIM model was established. Next, RBF neural network was used to simulated WIM model, and then a self-adjusting algorithm of gravity migration was founded. Finally, a WIM software for a single container with Visual Studio 2010 was developed. This software was simply operated and pragmatic, and also the efficiency of WIM was improved. In the whole system, model-building , data collection, Algorithm simulation, data storage, selection and printing are realized, and error ration of this system was less than 3% , therefore it has better business prospect in practice.

  12. New generation polyphase resonant converter-modulators for the Korean atomic energy research institute

    International Nuclear Information System (INIS)

    This paper will present operational data and performance parameters of the newest generation polyphase resonant high voltage converter modulator (HVCM) as developed and delivered to the KAERI 100 MeV ''PEFP'' accelerator (1). The KAERI design realizes improvements from the SNS and SLAC designs (2). To improve the IGBT switching performance at 20 kHz for the KAERI system, the HVCM utilizes the typical zero-voltage-switching (ZVS) at turn on and as well as artificial zero-current-switching (ZCS) at turn-off. The new technique of artificial ZCS technique should result in a 6 fold reduction of IGBT switching losses (3). This improves the HCVM conversion efficiency to better than 95% at full average power, which is 500 kW for the KAERI two klystron 105 kV, 50 A application. The artificial ZCS is accomplished by placing a resonant RLC circuit across the input busswork to the resonant boost transformer. This secondary resonant circuit provides a damped ''kick-back'' to assist in IGBT commutation. As the transformer input busswork is extremely low inductance (< 10 nH), the single RLC network acts like it is across each of the four IGBT collector-emitter terminals of the H-bridge switching network. We will review these topological improvements and the overall system as delivered to the KAERI accelerator and provide details of the operational results.

  13. Fabrication of CANFLEX bundle kit for irradiation test in NRU

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Moon Sung; Kwon, Hyuk Il; Ji, Chul Goo; Chang, Ho Il; Sim, Ki Seob; Suk, Ho Chun

    1997-10-01

    CANFLEX bundle kit was prepared at KAERI for the fabrication of complete bundle at AECL. Completed bundle will be used for irradiation test in NRU. Provisions in the `Quality Assurance Manual for HWR Fuel Projects,` `Manufacturing Plan` and `Quality Verification, Inspection and Test Plan` were implemented as appropriately for the preparation of CANFLEX kit. A set of CANFLEX kit consist of 43 fuel sheath of two different sizes with spacers, bearing pads and buttons attached, 2 pieces of end plates and 86 pieces of end caps with two different sizes. All the documents utilized as references for the fabrication such as drawings, specifications, operating instructions, QC instructions and supplier`s certificates are specified in this report. Especially, suppliers` certificates and inspection reports for the purchased material as well as KAERI`s inspection report are integrated as attachments to this report. Attached to this report are supplier`s certificates and KAERI inspection reports for the procured materials and KAERI QC inspection reports for tubes, pads, spacers, buttons, end caps, end plates and fuel sheath. (author). 37 refs.

  14. ADS National Programmes: Republic of Korea

    International Nuclear Information System (INIS)

    ADS research of Korea was carried out at KAERI (Korea Atomic Energy Research Institute) for the transmutation of long lived nuclides in spent fuels. The KAERI ADS system was called HYPER (HYbrid Power Extraction Reactor). The HYPER research was carried out as a 10 year nuclear research programme funded by the government. The ADS research of KAERI consisted of 3 phases. A basic concept of HYPER was established in the first phase (1997– 2000) of the development. The key technologies related to HYPER was studied in the second phase (2001–2003) while upgrading the design. The conceptual design of HYPER core was completed in the third phase (2004–2006). The research of key technologies was continued in the third phase. The research results can be summarized in three categories: Design and analysis; Fuel experiment; Pb-Bi experiment

  15. The study for the high qualification of international nuclear training

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Byong Chull; Kim, Hyun Jin

    2012-12-15

    It is suggested how to reach high qualification of KAERI international nuclear training and how to play a leading role for new paradigm on the international training on the world. 1. The formulation of the core nuclear training framework- The systematic formulation of nuclear training framework based on the existing turning course design 2. Planning and operation of KAERI- Excellent Technology Series training course- The advertisement for KAERI Excellent Technology through the continuous international training and the future market development on the world for the nuclear technology 3. e-Learning training contents development- e-Learning training contents development to play a leading role for new training paradigm on the world and to overcome the limit of time/spacy.

  16. Development of Silver-exchanged Adsorbents for the Removal of Fission Iodine from Alkaline Dissolution

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Taewoon; Lee, Seung-Kon; Lee, Suseung; Lee, Jun Sig [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Most of the iodine exists in the caustic dissolution as iodide form. KAERI is developing LEU-based fission 99 Mo production process which is connected to the new research reactor, which is being constructed in Kijang, Busan, Korea. In KAERI process, silver-exchanged adsorbent is used to adsorb iodide from the solution. Adsorbed iodide can be recovered and recycled for radiopharmaceuticals. In KAERI process, silver-exchanged adsorbent is used to adsorb iodide from the solution. Adsorbed iodide can be recovered and recycled for radiopharmaceuticals. Synthesis of silver-doped alumina is conducted in two ways. One is using the ascorbic acid as a reducing agent. However, this method is impossible to control.

  17. Numerical investigation of the radiation characteristics of a variable-period helical undulator

    Science.gov (United States)

    Lee, Kitae; Mun, Jungho; Hee Park, Seong; Jang, Kyu-Ha; Uk Jeong, Young; Vinokurov, Nikolay A.

    2015-03-01

    A helical undulator with a variable-period capability has been developed at the Korea Atomic Energy Research Institute (KAERI) to generate high power radiation in the terahertz range. A simulation code for the spontaneous emission from an electron beam inside an undulator has been developed to characterize the performance of the undulator. In the case of the KAERI undulator, there is a non-negligible high-order harmonics in the longitudinal field distribution compared with a bifilar one.The axial velocity modulation by the high-order harmonics in the field distribution has been found to lead to small deviation of the spectrum of spontaneous emission from the KAERI undulator with respect to the bifilars one. The gain functions obtained from the spontaneous emission spectra according to the Madey theory, show similar shapes for both undulators.

  18. Study on promotion of venture business

    International Nuclear Information System (INIS)

    This study reviewed the concepts of venture business and surveyed venture business support system nationwide. The venture business support system is summarized in depth to help the pre-entrepreneurs under establishing venture business. This study also reviewed the technology management system of KAERI and surveyed its historical accomplishment of technology transfer. Then, this study suggested its future direction by surveying the system of advanced countries and also suggested the measures to meet the future direction. The main finding of this study is that the direct investment to venture business by KAERI could greatly contribute to promoting venture business. Therefore, the government and KAERI should make efforts to change the technology management system toward the direct investment. Finally, this study concluded by offering policy suggestions to the government on improvement of technology management system

  19. Development of Nuclear Control and Management Information Treatment System

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, J. G.; Lee, B. D.; So, D. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    To implement obligations under the Non-Proliferation Treaty (NPT) and the bilateral agreements more effectively, we proposed a computerized system named the Nuclear Control and Management Information Treatment System (NCAMITS) as a part of the Nuclear Transparency Enhancement Project at the Korea Atomic Energy Research Institute (KAERI). The database system is designed not only to undertake the facility-level accounting for and control of nuclear material at KAERI, but also to meet the requirements of the State (National) System of Accounting and Control (SSAC). Since the NCAMITS will provide services for the facility operators as well as the safeguard information managers at KAERI, the development of the system is supposed to accommodate the end-user's convenience and the manager's sophisticated specifications as well.

  20. A Procedure for Determination of Degradation Acceptance Criteria for Structures and Passive Components in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Nie, J.; Braverman, J.; Hofmayer, C.; Choun, Y-S.; Hahm, D.; Choi, I-K.

    2012-01-30

    The Korea Atomic Energy Research Institute (KAERI) has been collaborating with Brookhaven National Laboratory since 2007 to develop a realistic seismic risk evaluation system which includes the consideration of aging of structures and components in nuclear power plants (NPPs). This collaboration program aims at providing technical support to a five-year KAERI research project, which includes three specific areas that are essential to seismic probabilistic risk assessment: (1) probabilistic seismic hazard analysis, (2) seismic fragility analysis including the effects of aging, and (3) a plant seismic risk analysis. The understanding and assessment of age-related degradations of structures, systems, and components and their impact on plant safety is the major goal of this KAERI-BNL collaboration. Four annual reports have been published before this report as a result of the collaboration research.

  1. Development of Voloxidation Process for Treatment of LWR Spent Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. J.; Jung, I. H.; Shin, J. M. (and others)

    2007-08-15

    The objective of the project is to develop a process which provides a means to recover fuel from the cladding, and to simplify downstream processes by recovering volatile fission products. This work focuses on the process development in three areas ; the measurement and assessment of the release behavior for the volatile and semi-volatile fission products from the voloxidation process, the assessment of techniques to trap and recover gaseous fission products, and the development of process cycles to optimize fuel cladding separation and fuel particle size. High temperature adsorption method of KAERI was adopted in the co-design of OTS for hot experiment in INL. KAERI supplied 6 sets of filter for hot experiment. Three hot experiment in INL hot cell from the 25th of November for two weeks with attaching 4 KAERI staffs had been carried out. The results were promising. For example, trapping efficiency of Cs was 95% and that of I was 99%, etc.

  2. An International Peer Review of the Programme for the Deep Geological Disposal of High Level Radioactive Waste from Pyro-Processing in the Republic of Korea. Report of an IAEA International Review Team

    International Nuclear Information System (INIS)

    The development of a radioactive waste disposal system is indispensable in maintaining the sustainability of nuclear energy. The Korea Atomic Energy Research Institute (KAERI) has studied the direct geological disposal of spent nuclear fuel since 1997. KAERI has also focused on the development of processes suitable for reducing the volume of spent nuclear fuel and the recycling of valuable fissile material. One of the most promising technologies investigated by KAERI is the pyro-processing of spent nuclear fuel followed by the geological disposal of the generated high level waste (HLW). Since 2007, KAERI has been running a research programme focusing on the recycling of spent nuclear fuel, as well as studies aimed at the development of a relevant geological disposal system able to accept the resulting HLW. The core aims of the KAERI study were to characterize the geological media, design a repository system and assess the overall safety of the disposal system. The development of pyro-processing technology is ongoing and has not yet been demonstrated at the commercial level. Thus, the government of the Republic of Korea requested an assessment of the technical feasibility of this technology. The assessment also included the appraisal of a disposal solution for waste generated by pyro-processing. With regard to the latter, KAERI requested that the IAEA review the status of the disposal project within the Waste Management Assessment and Technical Review Programme (WATRP). Peer reviews are increasingly being acknowledged as an important element in building broader stakeholder confidence in the safety and viability of related facilities. This report presents the consensus view of the international group of experts convened by the IAEA to perform the review

  3. Application of TSH bioindicator for studying the biological efficiency of radiation

    International Nuclear Information System (INIS)

    Dose response relationships for various endpoints (gene and lethal mutations, cell cycle alterations) in somatic cells of Tradescantia clone 4430 were established for X-rays and for mixed fast and thermal neutrons from Cf-252 source of KAERI and from U-120 cyclotron of INP. This was a pilot experiment to check if it is possible to establish the relative biological effectiveness values for Cf-252 irradiated TSH cells, with and without boron ion pretreatment, in conditions of mutual KAERI-INP experiment. When T-4430 was pretreated with boron ion, there was and enhancement in biological efficacy of neutron form Cf-252 source. 2 tabs., 7 figs., 7 refs. (Author)

  4. Optimum nuclear design of target fuel rod for Mo-99 production in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myung Hyun [Kyung Hee University, Seoul (Korea)

    1998-04-01

    Nuclear target design for Mo-99 production in HANARO was performed, KAERI proposed target design was analyzed and its feasibility was shown. Three commercial target designs of Cintichem, ANL and KAERI were tested for the HANARO irradiation an d they all satisfied with design specification. A parametric study was done for target design options and Mo-99 yields ratio and surface heat flux were compared. Tested parameters were target fuel thickness, irradiation location, target axial length, packing density of powder fuel, size of target radius, target geometry, fuel enrichment, fuel composition, and cladding material. Optimized target fuel was designed for both LEU and HEU options. (author). 17 refs., 33 figs., 42 tabs.

  5. Thermal conductivity modeling of U-Mo/Al dispersion fuel

    Science.gov (United States)

    Kim, Yeon Soo; Cho, Byoung Jin; Sohn, Dong-Seong; Park, Jong Man

    2015-11-01

    A dataset for the thermal conductivity of U-Mo/Al dispersion fuel made available by KAERI was reanalyzed. Using this dataset, an analytical model was obtained by expanding the Bruggeman model. The newly developed model incorporates thermal resistances at the interface between the U-Mo particles and the Al matrix and the defects within the Al matrix (grain boundaries, cracks, and dislocations). The interfacial resistances are expressed as functions of U-Mo particle size and Al grain size obtained empirically by fitting to measured data from KAERI. The model was then validated against an independently measured dataset from ANL.

  6. A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Kazakhstan

    Energy Technology Data Exchange (ETDEWEB)

    Ryh, Sipyo; Kim, Cheoljung; Yoo, Bungduk; Lee, Yongjoo; Kim, Hansoo; Yoon, Sungwon; Jeong, Hwansam; Jeong, Gijung

    2005-01-15

    The ultimate goal of this investigation to promote a collaboration of R and D for Nuclear Energy Technology Development between Korea and Kazakhstan. To understand the research power of the Kazakhstan, we visited the INP(Institute of Nuclear Physics) which is one of the branch of Nation Cuclear Center-Repunlic Kazakhstan. We presented the present status of the nuclear energy related research in KAERI. The director of international cooperation in the ministry of Mineral resources, the director of INP and vice director of IAE had visited KAERI, KIRAM and discussed about potential cooperation in nuclear research related field.

  7. Development of Wall-to-Fluid Heat Transfer Package for the SPACE Code

    International Nuclear Information System (INIS)

    A SPACE code which has a multi-dimensional analysis capability by incorporating a dispersed liquid phase into the thermo-hydraulic field equations is under development for a safety analysis of PWRs. Several research and industrial organizations are participating in the collaboration for the development program, including KAERI, KOPEC, KNF, and KEPRI. The main task of KAERI is to develop physical models and correlation packages for constitutive equations; a wall heat transfer package, a wall and interfacial friction package, an interfacial heat and mass transfer package and a flow regime selection package. This paper describes the development program for a wall-to-fluid heat transfer package for the SPACE code

  8. The korea multi-purpose research reactor

    International Nuclear Information System (INIS)

    This paper presents and discusses background and status of the design of the 30MW Korea Multi-purpose Research Reactor(KMRR) which is planed to achieve its first criticality in December, 19992, at Daeduk site of the Korea Advanced Energy Research Institute (KAERI). KAERI playing the leading role in Korea's nuclear technology development takes the total responsibility for its design, construction and operation. Number of Korean nuclear industries are, also, actively participating in the project while making the most of their expertise in relevant areas. (Author)

  9. The square boundary version of the WIMSE module W-PIJ

    International Nuclear Information System (INIS)

    W-PIJ is one component of the modular reactor physics code scheme known as WIMS-E. Its purpose is to read cross section data from a WIMS-E interface, a two dimensional cluster geometry from user input, and to calculate the associated region to region first flight neutron collision probabilities. These it writes back to the interface as data for a solution module which can calculate fluxes. Recent modifications to the code have provided better data checking facilities including a lineprinter geometry plotting option, and the option of an explicit square outer boundary. This report briefly describes the modifications that have been made to the code and includes a complete user guide to all options, old and new. (author)

  10. Halpha and [S II] emission from warm ionized gas in the Scutum-Centaurus Arm

    CERN Document Server

    Hill, Alex S; Haffner, L Matthew; Gostisha, Martin; Barger, Kathleen A

    2014-01-01

    We present Wisconsin H-Alpha Mapper [S II] {\\lambda}6716 and H{\\alpha} spectroscopic maps of the warm ionized medium (WIM) in the Scutum-Centaurus Arm at Galactic longitudes 310{\\deg} = 100 R. The line ratio is better correlated with H{\\alpha} intensity than with height above the plane, indicating that the physical conditions within the WIM vary systematically with electron density. We argue that the variation of the line ratio with height is a consequence of the decrease of electron density with height. Our results reinforce the well-established picture in which the diffuse H{\\alpha} emission is due primarily to emission from in situ photoionized gas, with scattered light only a minor contributor.

  11. Evaluation of the DRAGON code for VHTR design analysis.

    Energy Technology Data Exchange (ETDEWEB)

    Taiwo, T. A.; Kim, T. K.; Nuclear Engineering Division

    2006-01-12

    This letter report summarizes three activities that were undertaken in FY 2005 to gather information on the DRAGON code and to perform limited evaluations of the code performance when used in the analysis of the Very High Temperature Reactor (VHTR) designs. These activities include: (1) Use of the code to model the fuel elements of the helium-cooled and liquid-salt-cooled VHTR designs. Results were compared to those from another deterministic lattice code (WIMS8) and a Monte Carlo code (MCNP). (2) The preliminary assessment of the nuclear data library currently used with the code and libraries that have been provided by the IAEA WIMS-D4 Library Update Project (WLUP). (3) DRAGON workshop held to discuss the code capabilities for modeling the VHTR.

  12. Assessment of CANDU reactor physics effects using a simplified whole-core MCNP model

    Energy Technology Data Exchange (ETDEWEB)

    Kozier, K.S

    2002-07-01

    A whole-core Monte Carlo n-particle (MCNP) model of a simplified CANDU reactor was developed and used to study core configurations and reactor physics phenomena of interest in CANDU safety analysis. The resulting reactivity data were compared with values derived from corresponding WIMS-AECL/RFSP, two-neutron-energy-group diffusion theory core simulations, thereby extending the range of CANDU-related code-to-code benchmark comparisons to include whole-core representations. These comparisons show a systematic discrepancy of about 6 mk between the respective absolute k{sub eff} values, but very good agreement to within about -0.15 {+-} 0.06 mk for the reactivity perturbation induced by G-core checkerboard coolant voiding. These findings are generally consistent with the results of much simpler uniform-lattice comparisons involving only WIMS-AECL and MCNP. In addition, MCNP fission-energy tallies were used to evaluate other core-wide properties, such as fuel bundle and total-channel power distributions, as well as intra-bundle details, such as outer-fuel-ring relative power densities and outer-ring fuel element azimuthal power variations, which cannot be determined directly from WIMS-AECL/RFSP core calculations. The average MCNP values for the ratio of outer fuel element to average fuel element power density agreed well with corresponding values derived from WIMS-AECL lattice-cell cases, showing a small systematic discrepancy of about 0.5 %, independent of fuel bum-up. For fuel bundles containing the highest-power fuel elements, the maximum peak-to-average outer-element azimuthal power variation was about 2.5% for cases where a statistically significant trend was observed, while much larger peak-to-average outer-element azimuthal power variations of up to around 42% were observed in low-power fuel bundles at the core/radial-neutron-reflector interface. (author)

  13. TRIGLAV - a computer programme for research reactor calculation

    Energy Technology Data Exchange (ETDEWEB)

    Persic, A.; Ravnik, M.; Slavic, S.; Zagar, T. (J.Stefan Institute, Ljubljana (Slovenia))

    1999-12-15

    TRIGLAV is a new computer programme for burn-up calculation of mixed core of research reactors. The code is based on diffusion model in two dimensions and iterative procedure is applied for its solution. The material data used in the model are calculated with the transport programme WIMS. In regard to fission density distribution and energy produced by the reactor the burn-up increment of fuel elements is determined. (orig.)

  14. Use of the 'DRAGON' program for the calculation of reactivity devices

    International Nuclear Information System (INIS)

    DRAGON is a computer program developed at the Ecole Polytechnique of the University of Montreal and adopted by AECL for the transport calculations associated to reactivity devices. This report presents aspects of the implementation in NASA of the DRAGON program. Some cases of interest were evaluated. Comparisons with results of known programs as WIMS D5, and with experiments were done. a) Embalse (CANDU 6) cell without burnup and leakage. Calculations of macroscopic cross sections with WIMS and DRAGON show very good agreement with smaller differences in the thermal constants. b) Embalse fresh cell with different leakage options. c) Embalse cell with leakage and burnup. A comparison of k-infinity and k-effective with WIMS and DRAGON as a function of burnup shows that the differences ((D-W)/D) for fresh fuel are -0.17% roughly constant up to about 2500 MWd/tU, and then decrease to -0.06 % for 8500 MWd/tU. Experiments made in 1977 in ZED-2 critical facility, reported in [3], were used as a benchmark for the cell and supercell DRAGON calculations. Calculated fluxes were compared with experimental values and the agreement is so good. d) ZED-2 cell calculation. The measured buckling was used as geometric buckling. This case can be considered an experimental verification. The calculated reactivity with DRAGON is about 2 mk, and can be considered satisfactory. WIMS k-effective value is about one mk higher. e) Supercell calculations for ZED-2 vertical and horizontal tube and rod adjuster using 2D and 3D models were done. Comparisons between measured and calculated fluxes in the vicinity of the adjuster rods. Incremental cross sections for these adjusters were calculated using different options. f) ZED-2 reactor calculations with PUMA reveal a good concordance with critical heights measured in experiments. The report describes also particular features of the code and recommendations regarding its use that may be useful for new users. (author)

  15. Book Reviews

    OpenAIRE

    Hans Antlöv; Harry A. Poeze; Holk H. Dengel; H.A.J. Klooster; Gill, Ronald G.; George Hotze; Chr.G.F. de Jong; Alle G. Hoekema; Liaw Yock Fang; Jan van der Putten; Brigitte Müller; Helmut Buchholt; M. Hekker; James J. Fox; Janet Carsten

    1996-01-01

    - R. Anderson Sutton, Wim van Zanten, Ethnomusicology in the Netherlands: present situation and traces of the past. Leiden: Centre of Non-Western Studies, Leiden University, 1995, ix + 330 pp. [Oideion; The performing arts worldwide 2. Special Issue]., Marjolijn van Roon (eds.) - T.E. Behrend, Willem Remmelink, The Chinese War and the collapse of the Javanese state, 1725-1743. Leiden: KITLV Press, 1994, 297 pp. [Verhandelingen 162]. - Erik Brandt, Eric Venbrux, A death in the Tiwi Islands; Co...

  16. Specifications for reactor physics experiments on CANFLEX-RU fuel

    International Nuclear Information System (INIS)

    This is to describe reactor physics experiments to be performed in the ZED-2 reactor to study CANFLEX-RU fuel bundles in CANDU-type fuel channels. The experiments are to provide benchmark quality validation data for the computer codes and associated nuclear databases used for physics calculations, in particular WIMS-AECL. Such validation data is likely to be a requirement by the regulator as condition for licensing a CANDU reactor based on an enriched fuel cycle

  17. Confirmation of delayed menarche based on regression evaluation of age at menarche for age at MPV of height in female ball game players

    OpenAIRE

    Fujii, Katsunori; Demura, Schinichi

    2005-01-01

    A general delay in menarche in female athletes has been confirmed based on comparisons of mean ages between athletes and non-athletes; however, it has not been possible to judge such delays individually. If delayed menarche could be evaluated for an individual, the athlete could be advised as to necessary precautions. In this study, the age at maximum peak velocity (MPV) of height, adopted as an index of physical maturation, was identified by the wavelet interpolation method (WIM). The relati...

  18. Impact of Overweight Traffic on Pavement Life Using Weigh-In-Motion Data and Mechanistic-Empirical Pavement Analysis

    OpenAIRE

    Wang, Hao; Zhao, Jingnan; Wang, Zilong

    2015-01-01

    The objective of this study is to evaluate the impact of overweight traffic on pavement life using mechanistic-empirical analysis approach. The state-of-practice mechanistic-empirical pavement design and analysis software (Pavement-ME) was used to predict pavement life under different traffic loading scenarios. Field performance data at the sites where the WIM data were collected were analyzed to estimate the pavement service life at field condition. The pavement structures considered in the ...

  19. Static and dynamic weighing of vehicles

    OpenAIRE

    Meluš, Ladislav

    2014-01-01

    The work discusses the basic principles used in systems of static and dynamic weighing vehicles and is formally divided into a theoretical part and a practical part. The theoretical part describes the basic principles of strain weighing, types and functions of truck scales, related standards and evaluate the properties currently available types of scales. In the practical part contains a conceptual design of automated weighing station based WIM (Weighing in motion).

  20. Pertempuran Ideologi Desainer Grafis Modernisme dan Postmodernisme dalam Konteks Font Helvetica

    Directory of Open Access Journals (Sweden)

    Irwan Harnoko

    2013-03-01

    Full Text Available This article discusses the mindset of modernism designers: Massimo Vignelli, Wim Crouwel as opposed to the perspective of postmodernism designers: Paula Scher and David Carson on Helvetica font. This discussion becomes interesting because the leaders of the two sides are the key figures in the world of graphic design. Their opinions on Helvetica font can be used as a guide to study worlds graphic design, due to they dominate the mindset of contemporary designers.

  1. System and method for identifying, validating, weighing and characterizing moving or stationary vehicles and cargo

    Science.gov (United States)

    Beshears, David L.; Batsell, Stephen G.; Abercrombie, Robert K.; Scudiere, Matthew B.; White, Clifford P.

    2007-12-04

    An asset identification and information infrastructure management (AI3M) device having an automated identification technology system (AIT), a Transportation Coordinators' Automated Information for Movements System II (TC-AIMS II), a weigh-in-motion system (WIM-II), and an Automated Air Load Planning system (AALPS) all in electronic communication for measuring and calculating actual asset characteristics, either statically or in-motion, and further calculating an actual load plan.

  2. Interprofessional team management in pediatric critical care: some challenges and possible solutions

    OpenAIRE

    Stocker M.; Pilgrim SB; Burmester M.; Allen ML; Gijselaers WH

    2016-01-01

    Martin Stocker,1 Sina B Pilgrim,2 Margarita Burmester,3 Meredith L Allen,4 Wim H Gijselaers5 1Neonatal and Pediatric Intensive Care Unit, Children's Hospital Lucerne, Lucerne, 2Pediatric Intensive Care, University Children's Hospital Berne, Berne, Switzerland; 3Pediatric Intensive Care Unit, Royal Brompton Hospital, London, UK; 4Department of Pediatrics, The Royal Children's Hospital, Victoria, Australia; 5Educational Research and Development, School of Business and Ec...

  3. Reticular basement membrane in asthma and COPD: Similar thickness, yet different composition

    OpenAIRE

    Jeroen JW Liesker; Ten Hacken, Nick H.; Mieke Zeinstra-Smith; Rutgers, Steven R; Dirkje S Postma; et al.

    2009-01-01

    Jeroen JW Liesker1, Nick H Ten Hacken1, Mieke Zeinstra-Smith2, Steven R Rutgers1, Dirkje S Postma1, Wim Timens21Department of Pulmonology; 2Department of Pathology, University Medical Center Groningen, University of Groningen, Groningen, The Netherlands Background: Reticular basement membrane (RBM) thickening has been variably associated with asthma and chronic obstructive pulmonary disease (COPD). Even if RBM thickness is similar in both diseases, its composition might still differ. Objectiv...

  4. Accelerating Into the Future: From 0 to GeV in a Few Centimeters (LBNL Summer Lecture Series)

    International Nuclear Information System (INIS)

    Summer Lecture Series 2008: By exciting electric fields in plasma-based waveguides, lasers accelerate electrons in a fraction of the distance conventional accelerators require. The Accelerator and Fusion Research Division's LOASIS program, headed by Wim Leemans, has used 40-trillion-watt laser pulses to deliver billion-electron-volt (1 GeV) electron beams within centimeters. Leemans looks ahead to BELLA, 10-GeV accelerating modules that could power a future linear collider.

  5. Accelerating Into the Future: From 0 to GeV in a Few Centimeters (LBNL Summer Lecture Series)

    Energy Technology Data Exchange (ETDEWEB)

    Leemans, Wim [LOASIS Program, AFRD

    2008-07-08

    Summer Lecture Series 2008: By exciting electric fields in plasma-based waveguides, lasers accelerate electrons in a fraction of the distance conventional accelerators require. The Accelerator and Fusion Research Division's LOASIS program, headed by Wim Leemans, has used 40-trillion-watt laser pulses to deliver billion-electron-volt (1 GeV) electron beams within centimeters. Leemans looks ahead to BELLA, 10-GeV accelerating modules that could power a future linear collider.

  6. Kinetic study of the Tehran research reactor core with low enriched fuel

    Energy Technology Data Exchange (ETDEWEB)

    Pazirandeh, A.; Afshar Bakeshloo, A. [Tehran Univ. (Iran, Islamic Republic of). Physics Dept.; Bartsch, G. [Technische Univ. Berlin (Germany). Inst. fuer Energietechnik

    1997-11-01

    For evaluating the performance of the newly refuelled Tehran Research Reactor core with low enriched uranium fuel (LEU) in transient states a two group time dependent diffusion equation code (COSTANZA) was used. This paper presents results of calculations of the fast transients, revealing the steady performance of the core and fuel integrity during transient for a probable reactivity insertion of less than or equal dollar 1.5/0.5 s. The temperature dependant reactivity coefficients of the Doppler resonance broadening effect and of the moderator absorption cross section change and density dilution were calculated using cell-averaged 69 energy group WIMS-D/4 for two main libraries, old library and WIMKAL88, to 13 groups. The two group parameters for the COSTANZA code were also obtained by WIMS-D/4. (orig.) [Deutsch] Zur Bewertung der Leistungsfaehigkeit des neu beladenen Teheraner Forschungsreaktors mit niedrig angereichertem Uranbrennstoff bei Reaktivitaetstransienten wurde ein 2-Gruppen zeitabhaengiges Diffusionsprogramm COSTANZA verwendet. In der vorliegenden Arbeit werden Ergebnisse der Berechnung schneller Transienten vorgestellt, die das Verhalten des Reaktorkerns bzw. die Integritaet der Brennstaebe waehrend der Transienten fuer eine Reaktivitaetsaenderung von kleiner oder gleich Dollar 1.5/0.5 s zeigen. Die temperaturabhaengigen Reaktivitaetskoeffizienten der Doppler-Verbreitung im Brennstoff sowie der Dichteaenderung und der Neutronenabsorption im Moderator wurden mit Hilfe zellengemittelter 69 Energie-Gruppen der Datenbank WIMS-D/4 und fuer 13 Energiegruppen mit der Datenbank WIMKAL 88 ermittelt. Die Zweigruppendaten fuer das COSTANZA-Programm wurden ebenfalls mit Hilfe von WIMS-D/4 bestimmt. (orig.)

  7. Delta's zoeken steun bij elkaar

    OpenAIRE

    Driel, van, L.

    2012-01-01

    Wereldwijd staan delta’s onder druk door bevolkingsgroei, industrialisatie en klimaatverandering. In de Delta Alliance zijn nu tien delta’s uit Noord- en Zuid-Amerika, Afrika, Azië en Nederland verenigd, en een tiental andere Afrikaanse en Aziatische delta’s zoeken nog aansluiting. ‘Men wil weten hoe andere delta’s met problemen omgaan’, verklaart programmamanager Wim van Driel de belangstelling. In juni 2011 is de stichting Delta Alliance International opgericht om het geheel meer slagkracht...

  8. Book Reviews

    OpenAIRE

    Redactie KITLV

    2008-01-01

    Michael Williams; Deforesting the earth; From prehistory to global crisis (Greg Bankoff) Alexander Adelaar, Nikolaus P. Himmelmann (eds); The Austronesian languages of Asia and Madagascar (René van den Berg) Wim Ravesteijn, Jan Kop (eds); Bouwen in de archipel; Burgerlijke Openbare Werken in Nederlands-Indië en Indonesië 1800-2000 (Freek Colombijn) Susan Rodgers; Print, poetics, and politics; A Sumatran epic in the colonial Indies and New Order Indonesia (Bern...

  9. Uus poliitiline kriitika Ameerika filmis / Mathura

    Index Scriptorium Estoniae

    Mathura, pseud., 1973-

    2006-01-01

    Uued USA mängufilmid, mis on kriitilised oma riigi agressiivse poliitika suhtes : "Süriaana" ("Syriana") : režissöör Stephen Gaghan, "München" ("Munich") : režissöör Steven Spielberg, "Kahuriliha" ("Jarhead") : režissöör Sam Mendes, "Küllusemaa" ("Land of Plenty") : režissöör Wim Wenders

  10. A Special Fiber Optic Sensor for Measuring Wheel Loads of Vehicles on Highways

    OpenAIRE

    Garrick, Norman W.; Amlan Sen; Malla, Ramesh B.

    2008-01-01

    This paper presents results from an investigation on a special optical fiber as a load sensor for application in Weigh-in-Motion (WIM) systems to measure wheel loads of vehicles traveling at normal speed on highways. The fiber used has a unique design with two concentric light guiding regions of different effective optical path lengths, which has the potential to enable direct measurement of magnitudes as well as locations of forces acting at multiple points along a single fiber. The optical ...

  11. Formation and evolution of magma-poor margins, an example of the West Iberia margin

    Science.gov (United States)

    Perez-Gussinye, Marta; Andres-Martinez, Miguel; Morgan, Jason P.; Ranero, Cesar R.; Reston, Tim

    2016-04-01

    The West Iberia-Newfoundland (WIM-NF) conjugate margins have been geophysically and geologically surveyed for the last 30 years and have arguably become a paradigm for magma-poor extensional margins. Here we present a coherent picture of the WIM-NF rift to drift evolution that emerges from these observations and numerical modeling, and point out important differences that may exist with other magma-poor margins world-wide. The WIM-NF is characterized by a continental crust that thins asymmetrically and a wide and symmetric continent-ocean transition (COT) interpreted to consist of exhumed and serpentinised mantle with magmatic products increasing oceanward. The architectural evolution of these margins is mainly dominated by cooling under very slow extension velocities (uplift and weakening of the hanginwall of the active fault, where a new fault forms. This continued process leads to the formation of an array of sequential faults that dip and become younger oceanward. Here we show that these processes acting in concert: 1) reproduce the margin asymmetry observed at the WIM-NF, 2) explain the fault geometry evolution from planar, to listric to detachment like by having one common Andersonian framework, 3) lead to the symmetric exhumation of mantle with little magmatism, and 4) explain the younging of the syn-rift towards the basin centre and imply that unconformities separating syn- and post-rift may be diachronous and younger towards the ocean. Finally, we show that different lower crustal rheologies lead to different patterns of extension and to an abrupt transition to oceanic crust, even at magma-poor margins.

  12. WIMSCORE

    International Nuclear Information System (INIS)

    A code was developed for producing group constants and other data needed for reactor core burnup calculations. The code named WIMSCORE gets its input from WIMS output files and evaluates it to be served as input to the diffusion-burnup codes TDB, TRITON and CITATION. The purpose of this code is to facilitate the automation of data transfer between codes which is otherwise a very time-consuming and bound-to-error process. (author)

  13. Russki "Tjulpan" pokoril lazurnõi bereg / Maria Davtjan, Tatjana Pinskaja

    Index Scriptorium Estoniae

    Davtjan, Maria

    2008-01-01

    61. Cannes'i filmifestival on lõppenud. Vaatenurga preemia sai Kasahstani režissöör Sergei Dvortsevoi filmi "Tulp" ("Tjulpan") eest. Lisatud ka lühiintervjuu režissööriga. Ka mõnest filmist, nii auhinnatuist (Steven Soderbergh'i "Che", Clint Eastwoodi "Changeling") kui ilmajäänuist (Atom Egoyani "Adoration", Wim Wendersi "Palermo Shooting"), Sharon Stone'i juhitud heategevast AIDSi ravi toetavast oksjonist

  14. Study for 228Th reduction in thermal reactor with Th-U fuel cycls

    Institute of Scientific and Technical Information of China (English)

    1999-01-01

    By using computercode WIMS/CENDL, the effects of some parameters, core configuration such as fuel element structure, neutron flux and burn-up, are discussed in thispaper.It is shown that high neutron flux, small fuel rod diameter,large volume ratio of coolant to fuel, seed-blank heterogeneous corearrangement and 231Pa chemical separation are necessary for reducing 228Th production in reactor.

  15. Maintenance and fabrication of electronic equipment

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kwang Soo; Jeong, Jong Eun; Park, Kwang Hyun; Hong, Suk Bong; Moon, Je Sun; Choi, Myung Jin; Kim, Seung Bok; Kim, Jeong Bok [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-12-01

    Solving the maintenance and repair problems of electronic instruments, we have supported the research and development work, and reduced operation costs of the pilot plants in KAERI. In addition, we have improved the maintainability of instruments to use effectively. 18 tabs., 17 figs., 13 refs. (Author) .new.

  16. A Study on the Development of the FEP and Scenario for the HLW Disposal in Korea

    International Nuclear Information System (INIS)

    The impacts influenced on the performance and safety of a repository are classified as units of Features, Events, and Processes (FEP), for the total system performance assessment (TSPA) related to the permanent disposal of HLW. The importance is evaluated in consideration of the frequency, consequence, regulation, suitability of a specific site, etc. and then these are grouped as a similar FEP. A scenario describing the migration of radionuclide from the repository to the biosphere is derived from understanding the interaction among these groups. KAERI has developed the KAERI FEP lists by review and collation of the foreign studies. The KAERI FEP list has been reviewed by several Korean experts. The five major scenarios describing possible future evolutions of the geological disposal system have been developed by RES and PID methods. Also the CYPRUS which is a KAERI integrated database management system for the total system performance assessment (TSPA) related to the permanent disposal of HLW has been developed and the results of the FEP and scenario development have been uploaded in this system.

  17. Maintenance and fabrication of electronic equipment

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kwang Soo; Jeong, Jong Eun; Park, Kwang Hyeon; Hong, Suk Bong; Moon, Je Sun; Choi, Myeong Jin; Kim, Seung Bok; Kim, Jeong Bok [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    Solving the maintenance and repair problems of electronic instruments, we have supported the research and development work, and reduced operation costs of the pilot plants in KAERI. In addition, we have imposed the maintainability of instruments to use effectively. 15 tabs., 14 figs., 14 refs. (Author) .new.

  18. Establishment of Korea-Russia bilateral research collaboration for studies on biological effects of cosmic ray and space radiation

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Juwoon; Kim, Dongho; Choi, Jongil; Song, Beomseok; Kim, Jaekyung; Kang, Oilhyun; Lee, Yoonjong; Kim, Jinhong; Jo, Minho

    2011-04-15

    {Omicron} KAERI-IBMP joint workshop on countermeasure and application researches to space environments - Sharing of state-of-the-art researches on space radiobiology using bio-satellites (BION-M1, Photon-soil) and ISS module (Bio-risk) was conducted - Sharing and discussion of state-of-the-art researches on dosimetry of space radiation and its affect on organisms were conducted. {Omicron} Making a contract on KAERI-IBMP Joint Research using Bio-risk module - Contract on KAERI-IBMP Joint Research to evaluate effect of space environment (microgravity and space radiation) on fermentative fungi (Aspergillus oryzae), Algae (Nostoc sp.), and plant seeds (rice, Arabidopsis thaliana, Brachypodium distachyon) was made in November, 2010. {Omicron} Discussion on new Joint Researches on evaluation of space radiation on organisms - Final step on Bion-M projects in terms of evaluation of physiological changes of lactic acid bacteria consumed by Mouse - Discussing new joint research on evaluation of physiological changes of primate by space radiation {Omicron} Establishment and management of the practical working group to invite a branch office of the IBMP in Korea - The system and the working group to implement cooperating researches between KAERI-IBMP on space radiation were established.

  19. Maintenance and fabrication of electronic equipment

    International Nuclear Information System (INIS)

    Solving the maintenance and repair problems of electronic instruments, we have supported the research and development work, and reduced operation cost of the pilot plants in KAERI. In addition, we have improved the maintainability of instruments to use effectively. (author). 10 refs., 18 tabs., 8 figs

  20. Maintenance and fabrication of electronic equipment

    International Nuclear Information System (INIS)

    Providing technical support to the maintenance and repair problems of electronic instruments, we have assisted the research and development work, and reduced operation cost of the pilot plants in KAERI. In addition, we have improved the performance of the data processing system of RMS, and also modified the cyclic box using PLC which is a facility for airborne monitoring in radiation area. (author)

  1. 78 FR 72072 - Proposed Subsequent Arrangement

    Science.gov (United States)

    2013-12-02

    ... at and was prepared by KAERI, will be used for the irradiation test of full-size fuel plates in the... Concerning Civil Uses of Atomic Energy and the Agreement for Cooperation in the Peaceful Uses of Nuclear.... Sean Oehlbert, Office of Nonproliferation and International Security, National Nuclear...

  2. Operation of the radioactive waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kil Jeong; Ahn, Seom Jin; Lee, Kang Moo; Lee, Young Hee; Sohn, Jong Sik; Bae, Sang Min; Kang, Kwon Ho; Lim, Kil Sung; Sohn, Young Joon; Kim, Tae Kook; Jeong, Kyung Hwan; Wi, Geum San; Park, Seung Chul; Park, Young Woong; Yoon, Bong Keun

    1996-12-01

    The radioactive wasted generated at Korea Atomic Energy Research Institute (KAERI) in 1996 are about 118m{sup 3} of liquid waste and 204 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. In 1996, 100.5m{sup 3} of liquid waste was treated. (author). 84 tabs., 103 figs.

  3. Establishment of Research Infrastructure for National Advanced Radiation Technology

    Energy Technology Data Exchange (ETDEWEB)

    Kuk, Il Hiun; Byun, Myung Woo; Jeong, Il Yun; and others

    2007-07-15

    Construction of fundamental analysis system for RT/RFT advancement and pilot scale laboratory/facility for industry support and Assembly/installation of 30 MeV cyclotron for RI production and research utilizing positron beam, and construction of /distribution system for industrial and medical purpose were carried out for fast settlement for research environment of ARTI (a Jeongeup branch of KAERI)

  4. Maintenance and fabrication of electronic equipment

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kwang Soo; Chung, Chong Eun; Park, Kwang Hyeon; Hong, Suk Boong; Moon, Je Sun; Choi, Myung Jin; Kim, Seung Bok; Kim, Jung Bok

    1996-12-01

    Solving the maintenance and repair problems of electronic instruments, we have supported the research and development work, and reduced operation cost of the pilot plants in KAERI. In addition, we have improved the maintainability of instruments to use effectively. (author). 10 refs., 18 tabs., 8 figs.

  5. Atomic and molecular databases in Japan and Asia

    Science.gov (United States)

    Murakami, Izumi; Kato, Takako

    2000-11-01

    Atomic and molecular data activities and databases in Japan and Asia are introduced. In China IAPCM has a database on windows95/NT. In Korea KAERI has A+M databases with original engines. In Japan JAERI shows evaluated data as graphs on WWW and NIFS offers numerical A+M databases on WWW. .

  6. Decontamination and decommissioning technology development of nuclear facilities

    International Nuclear Information System (INIS)

    Removal behaviour of an oxide which is similar in structure and composition to that on internal system of steam generator were investigated in low concentration chemical decontamination process [KAERI process]. In the AP solution (oxidative dissolution step), Cr dissolved fastly from the oxide in early stage and then dissolved very slowly in later stage. Dissolution behaviours of Fe from the oxides in the reductive dissolution process were similar to those of Cr in the oxidative dissolution process. Oxide dissolution behaviour in each process were discussed. In twice cyclic application of the oxidative and the reductive dissolution process(KAERI decontamination process), about 50% of the oxide was removed by chemical dissolution, about 40% by particulate detachment. The rest 10% oxide could be completely removed by ultrasonic decontamination. Corrosion acceptance guideline was established for the decontamination of domestic PWRs' steam generator. In the KAERI decontamination process, general corrosion to an Inconel-600 and 304 stainless steel was about 2.4 and 1.0% of general corrosion limit, respectively. And localized corrosion was not observed. Those results indicated that the KAERI decontamination process assured integrity of KNUs' steam generator. To evaluate the radioactive inventory for the decommissioning of nuclear facilities, general calculation methods of radioactive inventory, calculation and measurement of contact exposure rate, and confirmation of those results were reviewed. Feasibility for application of the above methods was examined by taking examples of radioactive inventory estimation in the Shippingport nuclear reactor vessel. (Author)

  7. Operation of the radioactive waste treatment facility

    International Nuclear Information System (INIS)

    The radioactive wasted generated at Korea Atomic Energy Research Institute (KAERI) in 1996 are about 118m3 of liquid waste and 204 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. In 1996, 100.5m3 of liquid waste was treated. (author). 84 tabs., 103 figs

  8. Analysis of the IAEA Coordinated Research Project (CRP) benchmark problem phase IV for liquid metal fast reactors

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ki Bog; Song, Hoon; Jang, Jin Wook [and others

    2003-06-01

    The purpose of this document is to report the calculation results based on the K-CORE system developed by KAERI and to compare the results performed by the each participant for the IAEA CRP Phase 4 of BN-600 full Mixed OXide (MOX) fueled core benchmark analyses. The K-CORE calculational methods employed in the benchmark analyses are explained. The benchmark results carried out by KAERI and the results of other participants are collected and inter-compared. According to comparison results, the k-eff and the fuel Doppler coefficients of KAERI shows a little bit higher than the other's values mainly due to using JEF 2.2 cross section data library as described in sensitivity analysis. The fuel density coefficients and the effective delayed neutron fraction and the neutron lifetime show good agreement compared with the other participants' values. Even though the KAERI results for the steel Doppler and sodium density coefficients, exists in the range of minimum and maximum values between the participants, there are big discrepancies in reactivity coefficients. So the prediction of reactivity coefficients requires further investigation, and the study of Phase5, Phase 6 will be continuously performed.

  9. Maintenance and fabrication of electronic equipment

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chong Eun; Moon, Byung Soo; Hong, Suk Boong; Kim, Jung Bok

    1999-12-01

    Providing technical support to the maintenance and repair problems of electronic instruments, we have assisted the research and development work, and reduced operation cost of the pilot plants in KAERI. In addition, we have improved the performance of the data processing system of RMS, and also modified the cyclic box using PLC which is a facility for airborne monitoring in radiation area. (author)

  10. Calculating Program for Decommissioning Work Productivity based on Decommissioning Activity Experience Data

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Seung-Kook; Park, Hee-Seong; Moon, Jei-kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist.

  11. Burn-Up Dependence of Bubble Morphology of Uranium Silicide Dispersion Fuels Used in Research Reactor

    International Nuclear Information System (INIS)

    Burn-up dependence of fission gas bubble morphology of U3Si2-Al and U3Si-Al dispersion fuels are reviewed with the data of ANL(Argonne Nation Laboratory) and KAERI(Korea Atomic Energy Research Institute

  12. Sampling optimization for high-speed weigh-in-motion measurements using in-pavement strain-based sensors

    International Nuclear Information System (INIS)

    Weigh-in-motion (WIM) measurement has been widely used for weight enforcement, pavement design, freight management, and intelligent transportation systems to monitor traffic in real-time. However, to use such sensors effectively, vehicles must exit the traffic stream and slow down to match their current capabilities. Hence, agencies need devices with higher vehicle passing speed capabilities to enable continuous weight measurements at mainline speeds. The current practices for data acquisition at such high speeds are fragmented. Deployment configurations and settings depend mainly on the experiences of operation engineers. To assure adequate data, most practitioners use very high frequency measurements that result in redundant samples, thereby diminishing the potential for real-time processing. The larger data memory requirements from higher sample rates also increase storage and processing costs. The field lacks a sampling design or standard to guide appropriate data acquisition of high-speed WIM measurements. This study develops the appropriate sample rate requirements as a function of the vehicle speed. Simulations and field experiments validate the methods developed. The results will serve as guidelines for future high-speed WIM measurements using in-pavement strain-based sensors. (paper)

  13. The warm ionized gas in CALIFA early-type galaxies: 2D emission-line patterns and kinematics for 32 galaxies

    CERN Document Server

    Gomes, J M; Kehrig, C; Vílchez, J M; Lehnert, M D; Sánchez, S F; Ziegler, B; Breda, I; Reis, S N dos; Iglesias-Páramo, J; Bland-Hawthorn, J; Galbany, L; Bomans, D J; Rosales-Ortega, F F; Fernandes, R Cid; Walcher, C J; Falcón-Barroso, J; García-Benito, R; Márquez, I; del Olmo, A; Masegosa, J; Mollá, M; Marino, R A; Delgado, R M González; López-Sánchez, Á R

    2015-01-01

    The morphological, spectroscopic and kinematical properties of the warm interstellar medium (wim) in early-type galaxies (ETGs) hold key observational constraints to nuclear activity and the buildup history of these massive, quiescent systems. High-quality integral field spectroscopy (IFS) data with a wide spectral and spatial coverage, such as those from the CALIFA survey, offer an unprecedented opportunity for advancing our understanding of the wim in ETGs. This article centers on a 2D investigation of the wim component in 32 nearby (<~150Mpc) ETGs from CALIFA, complementing a previous 1D analysis of the same sample (Papaderos et al. 2013; P13). We include here H\\alpha\\ intensity and equivalent width (EW) maps and radial profiles, diagnostic emission-line ratios, besides ionized-gas and stellar kinematics. This study is supplemented by \\tau-ratio maps as an efficient means to quantify the role of photoionization by pAGB stars, as compared to other mechanisms (e.g., AGN, low-level star formation). Additio...

  14. TRIGA MARK-II source term

    Energy Technology Data Exchange (ETDEWEB)

    Usang, M. D., E-mail: mark-dennis@nuclearmalaysia.gov.my; Hamzah, N. S., E-mail: mark-dennis@nuclearmalaysia.gov.my; Abi, M. J. B., E-mail: mark-dennis@nuclearmalaysia.gov.my; Rawi, M. Z. M. Rawi, E-mail: mark-dennis@nuclearmalaysia.gov.my; Abu, M. P., E-mail: mark-dennis@nuclearmalaysia.gov.my [Bahagian Teknologi Reaktor, Agensi Nuklear Malaysia, 43000 Kajang (Malaysia)

    2014-02-12

    ORIGEN 2.2 are employed to obtain data regarding γ source term and the radio-activity of irradiated TRIGA fuel. The fuel composition are specified in grams for use as input data. Three types of fuel are irradiated in the reactor, each differs from the other in terms of the amount of Uranium compared to the total weight. Each fuel are irradiated for 365 days with 50 days time step. We obtain results on the total radioactivity of the fuel, the composition of activated materials, composition of fission products and the photon spectrum of the burned fuel. We investigate the differences of results using BWR and PWR library for ORIGEN. Finally, we compare the composition of major nuclides after 1 year irradiation of both ORIGEN library with results from WIMS. We found only minor disagreements between the yields of PWR and BWR libraries. In comparison with WIMS, the errors are a little bit more pronounced. To overcome this errors, the irradiation power used in ORIGEN could be increased a little, so that the differences in the yield of ORIGEN and WIMS could be reduced. A more permanent solution is to use a different code altogether to simulate burnup such as DRAGON and ORIGEN-S. The result of this study are essential for the design of radiation shielding from the fuel.

  15. TRIGA MARK-II source term

    Science.gov (United States)

    Usang, M. D.; Hamzah, N. S.; J. B., Abi M.; M. Z., M. Rawi; Abu, M. P.

    2014-02-01

    ORIGEN 2.2 are employed to obtain data regarding γ source term and the radio-activity of irradiated TRIGA fuel. The fuel composition are specified in grams for use as input data. Three types of fuel are irradiated in the reactor, each differs from the other in terms of the amount of Uranium compared to the total weight. Each fuel are irradiated for 365 days with 50 days time step. We obtain results on the total radioactivity of the fuel, the composition of activated materials, composition of fission products and the photon spectrum of the burned fuel. We investigate the differences of results using BWR and PWR library for ORIGEN. Finally, we compare the composition of major nuclides after 1 year irradiation of both ORIGEN library with results from WIMS. We found only minor disagreements between the yields of PWR and BWR libraries. In comparison with WIMS, the errors are a little bit more pronounced. To overcome this errors, the irradiation power used in ORIGEN could be increased a little, so that the differences in the yield of ORIGEN and WIMS could be reduced. A more permanent solution is to use a different code altogether to simulate burnup such as DRAGON and ORIGEN-S. The result of this study are essential for the design of radiation shielding from the fuel.

  16. Obtaining the neutronic and thermal hydraulic parameters of the VVER-1000 Bushehr nuclear reactor core by coupling nuclear codes

    International Nuclear Information System (INIS)

    In this research, the simulation of one-sixth of the VVER-1000 reactor core is carried out by the WIMS-D4 nuclear code, based on the symmetry of the core and information obtained from the Final Safety Analysis Report. The atomic densities of some important nuclear materials and fission poisons are calculated by the WIMS-D4 code at the end of the first fuel cycle. In addition, the cross sections of some nuclides are obtained by WIMS-D4, and they are transferred into the CITATION code as inputs. In the next stage, neutron flux and reactor power are calculated by the CITATION code in Cold Zero Power and Hot Full Power status, and subsequently the heat flux of the core is obtained. Then the results are returned again into the extended program cycle. Finally, the heat flux of the core is inputted into the COBRA code, and the temperatures of fuel, clad and coolant are calculated along the various distances applying the COBRA thermal hydraulic code, through the results of the CITATION code and also initial data as default created from the Final Safety Analysis Report. In conclusion, there are some interesting outcomes resulting form the obtained results.

  17. Extended nebular emission in CALIFA early-type galaxies

    CERN Document Server

    Gomes, J M; Kehrig, C; Vílchez, J M; Lehnert, M D

    2015-01-01

    The morphological, spectroscopic and kinematical properties of the warm interstellar medium (wim) in early-type galaxies (ETGs) hold key observational constraints to nuclear activity and the buildup history of these massive quiescent systems. High-quality integral field spectroscopy (IFS) data with a wide spectral and spatial coverage, such as those from the CALIFA survey, offer a precious opportunity for advancing our understanding in this respect. We use deep IFS data from CALIFA (califa.caha.es) to study the wim over the entire extent and optical spectral range of 32 nearby ETGs. We find that all ETGs in our sample show faint (H\\alpha\\ equivalent width EW~0.5...2 {\\AA}) extranuclear nebular emission extending out to >= 2 Petrosian_50 radii. Confirming and strengthening our conclusions in Papaderos et al. (2013) we argue that ETGs span a broad continuous sequence with regard to the properties of their wim, and they can be roughly subdivided into two characteristic classes. The first one (type i) comprises E...

  18. AN overview of the FLYSAFE datalink solution for the exchange of weather information: supporting aircrew decision making processes.

    Science.gov (United States)

    Mirza, A.; Drouin, A.

    2009-09-01

    FLYSAFE is an Integrated Project of the 6th framework of the European Commission with the aim to improve flight safety through the development of an avionics solution the Next Generation Integrated Surveillance System (NGISS), which is supported by a ground based network of Weather Information Management Systems (WIMS) and access points in the form of the Ground Weather Processor (GWP). The NGISS provides information to the flight crew on the three major external hazards for aviation: weather, air traffic and terrain. The NGISS has the capability of displaying data about all three hazards on a single display screen, facilitating rapid appreciation of the situation by the flight crew. Weather Information Management Systems (WIMS) were developed to provide the NGISS and the flight crew with weather related information on in-flight icing, thunderstorms and clear-air turbulence. These products are generated on the ground from observations and model forecasts. WIMS will supply relevant information on three different scales: global, regional and local (over airport Terminal Manoeuvring Area). The Ground Weather Processor is a client-server architecture that utilises open source components, which include a geospatial database and web feature services. The GWP stores Weather Objects generated by the WIMS. An aviation user can retrieve on-demand all Weather Objects that intersect the volume of space that is of interest to them. The Weather Objects are fused with in-situ observation data and can be used by the flight management system to propose a route to avoid the hazard. In addition they can be used to display the current hazardous weather to the Flight Crew thereby raising their awareness. Within the FLYSAFE program, around 120 hours of flight trials were performed during February 2008 and August 2008. Two aircraft were involved each with separate objectives: - to assess FLYSAFE's innovative solutions for the data-link, on-board data-fusion and data-display and data

  19. Biological efficiency of interaction between various radiation and chemicals

    International Nuclear Information System (INIS)

    This research project has been carried out jointly with INP (Poland) to develop technologies to assess the biological efficiency of interaction between radiation and chemicals. Through the cooperative project, KAERI and INP have established wide variety of bioassay techniques applicable to radiation bioscience, human monitoring, molecular epidemiology and environmental science. The joint experiment, in special, made it possible to utilize the merits of both institutes and to upgrade and verify KAERI's current technology level. All results of the cooperative research will be jointly published in high standard scientific journals listed in the Science Citation Index (SCI), which can make the role of fundamental basis for improving relationship between Korea and Poland. Research skills such as Trad-MCN assay, SCGE assay, immunohistochemical assay and molecular assay developed through joint research will be further elaborated and will be continuously used for the collaboration between two institutes

  20. Prompt gamma activation analysis of boron in reference materials using diffracted polychromatic neutron beam

    International Nuclear Information System (INIS)

    Boron concentrations were analyzed for standard reference materials by prompt gamma activation analysis (PGAA). The measurements were performed at the SNU-KAERI PGAA facility installed at Hanaro, the research reactor of Korea Atomic Energy Research Institute (KAERI). The facility uses a diffracted polychromatic beam with a neutron flux of 7.9 x 107 n/cm2 s. Elemental sensitivity for boron was calibrated from the prompt gamma-ray spectra of boric acid samples containing 2-45 μg boron. The sensitivity of 2131 cps/mg-B was obtained from the linearity of the boron peak count rate versus the boron mass. The detection limit for boron was estimated to be 67 ng from an empty sample bag spectrum for a counting time of 10,000 s. The measured boron concentrations for standard reference materials showed good consistency with the certified or information values

  1. Prompt gamma activation analysis of boron in reference materials using diffracted polychromatic neutron beam

    Science.gov (United States)

    Byun, S. H.; Sun, G. M.; Choi, H. D.

    2004-01-01

    Boron concentrations were analyzed for standard reference materials by prompt gamma activation analysis (PGAA). The measurements were performed at the SNU-KAERI PGAA facility installed at Hanaro, the research reactor of Korea Atomic Energy Research Institute (KAERI). The facility uses a diffracted polychromatic beam with a neutron flux of 7.9 × 10 7 n/cm 2 s. Elemental sensitivity for boron was calibrated from the prompt gamma-ray spectra of boric acid samples containing 2-45 μg boron. The sensitivity of 2131 cps/mg-B was obtained from the linearity of the boron peak count rate versus the boron mass. The detection limit for boron was estimated to be 67 ng from an empty sample bag spectrum for a counting time of 10,000 s. The measured boron concentrations for standard reference materials showed good consistency with the certified or information values.

  2. A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Central Asia

    International Nuclear Information System (INIS)

    The goal of this research work is to promote the cooperation in the field of nuclear related works with Kazakhstan and Uzbekistan which are main countries in the central Asia. To make a basis on exchanging researchers, a staff in KAERI had visited INP NNC RK, touring research reactors, and make a discussion with the staffs in INP. With this, there is a efforts to make an arrangement between KAERI and NNC RK, signing will be made in near futures. To understand the level of nuclear technology in Uzbekistan, Dr. Rho had made a trip to INP. He visited the Gamma-radiation facility, a research reactor. In Nov. 2005, the chairman of Science Academy visited Korea to discuss the future cooperation in the field of peaceful use of the nuclear energy. By doing so, Korea will make an effort to cooperate with countries in the Central Asia

  3. Development of a preliminary PIRT (Phenomena Identification and Ranking Table) of thermal-hydraulic phenomena for 330MWt SMART integral reactor

    International Nuclear Information System (INIS)

    The work reported in this document identifies the thermal-hydraulic phenomena that are expected to occur during a number of key transients in a 330 MWt SMART integral reactor which is under development at KAERI. The result of this efforts is based on the current design concept of SMART integral reactor. Although the design is still evolving, the preliminary Phenomena Identification and Ranking Table (PIRT) has been developed based on the experts' knowledge and experience. The preliminary PIRT has been developed by the consensus of KAERI expert panelists and AHP (Analytical Hierarchy Process). Preliminary PIRT developed in this report is intended for use to identify and integrate development areas of further experimental tests needed and thermal-hydraulic models and correlations and code improvements for the safety analysis of the SMART integral reactor. (author). 7 refs., 21 tabs., 22 figs

  4. Test Results of a Network Switch Device for SMART MMIS

    International Nuclear Information System (INIS)

    SMART MMIS has been designed using fully digitalized systems. Non-safety instrumentation and control (I and C) systems are designed based on commercially distributed control systems. The safety I and C systems are designed using a new platform, which was developed and validated by KAERI. Safety I and C systems are modularized using the platform and communicate with each other using a communication board (CMB) and network switching device (NSD). The NSD of this paper has a deterministic behavior for industrial or nuclear application, where process data or control data has to be delivered within a certain time limit. The NSD has been developed and tested at KAERI since 2009. This paper presents the development and test results of the NSD

  5. Status of Fast Reactor and Pyroprocess Technology Development in the Republic of Korea

    International Nuclear Information System (INIS)

    A fast reactor system with pyroprocess technology is one of the most promising options for electricity generation, with an efficient utilization of uranium resources and a reduction of radioactive wastes. On the experience gained during the development of the conceptual designs for KALIMER reactors, Korea Atomic Energy Research Institute (KAERI) is currently developing advanced sodium cooled fast reactor (SFR) design concepts that can better meet the Generation IV technology goals. The long term SFR development plan will be carried out with the aim of constructing an advanced SFR demonstration plant by 2028. For the development of pyroprocess technology, KAERI is currently establishing a pyroprocess integrated inactive demonstration facility (PRIDE), a mock-up facility for pyroprocessing, to produce the engineering data to be incorporated into the design of an engineering scale pyrochemical process facility, which is scheduled to be constructed by 2016. (author)

  6. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Geun Sik and others

    2001-02-01

    Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry.

  7. Shielding and Criticality Safety Analysis of KSC-1 Cask for the High Burnup PWR Spent Fuels

    International Nuclear Information System (INIS)

    KSC-1 (KAERI Shipping Cask-1) was designed and manufactured with a pure domestic technology in 1985 in order to transport a PWR spent fuel assembly from nuclear power plant to PIEF (Post-Irradiation Examination Facility) of KAERI. Since the first transportation of the fuel assembly from Kori-1 NPP was carried out by the cask in 1987, 19 shipments for the PWR spent fuels have been done successfully by now. Maximum discharge burnup of PWR in Korea has been extended from the late 1990s in order to reduce the cost of power generation. From this cause, allowable design values of the initial enrichment and the cooling time for the cask have been changed three times: year 2003, 2007 and 2010. Radiation shielding and criticality of KSC-1 were analyzed for all the PWR fuel type irradiated in Korea NPP to renew the design approval

  8. Shielding and Criticality Safety Analysis of KSC-1 Cask for the High Burnup PWR Spent Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Hyoung Mun; Jang, Jung Nam; Hwang, Yong Hwa; Kwon, In Chan; Min, Duck Kee; Chun, Yong Bum [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    KSC-1 (KAERI Shipping Cask-1) was designed and manufactured with a pure domestic technology in 1985 in order to transport a PWR spent fuel assembly from nuclear power plant to PIEF (Post-Irradiation Examination Facility) of KAERI. Since the first transportation of the fuel assembly from Kori-1 NPP was carried out by the cask in 1987, 19 shipments for the PWR spent fuels have been done successfully by now. Maximum discharge burnup of PWR in Korea has been extended from the late 1990s in order to reduce the cost of power generation. From this cause, allowable design values of the initial enrichment and the cooling time for the cask have been changed three times: year 2003, 2007 and 2010. Radiation shielding and criticality of KSC-1 were analyzed for all the PWR fuel type irradiated in Korea NPP to renew the design approval

  9. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho

    2000-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author)

  10. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho; Lee, M.H. [and others

    1999-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul research reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul research reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul research reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author). 3 refs., 50 tabs., 12 figs.

  11. Design report for cask transportation equipment

    International Nuclear Information System (INIS)

    In Korea, the spent fuels stored in the spent fuel storage pools in the domestic nuclear power plants significantly affects the continuation of the power plant operation. To solve this problem, KAERI has developed KSC-4 spent fuel shipping cask, which can transport 4 PWR spent fuel assemblies. Besides the development of the cask, KAERI developed transportation equipment which needed to use of KSC-4 cask. These equipment consist of cask handling tools such as lifting yoke, lid handling tool and spent fuel handling tool, etc. and transportation equipment such as trailer. In this report the usages, structures and functions of these tools and equipment were described, and the safety evaluation was carried out for each equipment

  12. Technical cooperation for the wider uses of Ho-166 therapeutic agents in European countries

    CERN Document Server

    Park, K B; Choi, S M; Han, K H; Hong, Y D; Park, W W; Shin, B C

    2002-01-01

    Czech has put their priority in developing the radiopharmaceuticals based on reactor produced Ho-166 and a related fabrication will be extended to other EU conturies including Germany, France, etc after a development of project. The collaboration will be based on the mutual agreement for developing the between research institutes, industries and academic institutes and further researches should be followed by the issue of developing radiopharmaceuticals using Ho-166. To strengthen the collaboration, detailed discussions for the practical collaboration have been made through the visitation to the research institution of each counter part. For implementing the collaboration between NPI and KAERI, an institutional basis technical cooperation agreement(TCA) will be concluded. Furthermore, agreement for the substantial collaboration on Ho-166 related researches will be made after the conclusion of the TCA. It will accelerate the commercialization of KAERI developed Ho-166 therapeutic agents into other European cou...

  13. Basic requirements for a preliminary conceptual design of the Korea advanced pyroprocess facility (KAPF)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ho Hee; Ko, Won Il; Chang, Hong Lae; Song, Dae Yong; Kwon, Eun Ha; Lee, Jung Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-12-15

    Korea Atomic Energy Research Institute (KAERI) has been developing technologies for pyroprocessing for spent PWR fuels. This study is part of a long term R and D program in Korea to develop an advanced recycle system that has the potential to meet and exceed the proliferation resistance, waste minimization, resource minimization, safety and economic goals of approved Korean Government energy policy, as well as the Generation IV International Forum (GIF) program. To support this R and D program, KAERI requires that an independent estimate be made of the conceptual design and cost for construction and operation of a 'Korea Advanced Pyroprocessing Facility', This document describes the basic requirements for preliminary conceptual design of the Korea Advanced Pyroprocess Facility (KAPF). The presented requirements will be modified to be more effective and feasible on an engineering basis during the subsequent design process.

  14. A Study to Promote a Collaboration of R and D for Nuclear Energy Technology Development between Korea and Central Asia

    Energy Technology Data Exchange (ETDEWEB)

    Rho, Si Pyo; Kim, Cheol Jung; Yoo, Bung Duk; Kim, Jae Woo; Lee, Myung Ho; Kim, Kyung Pyo

    2006-02-15

    The goal of this research work is to promote the cooperation in the field of nuclear related works with Kazakhstan and Uzbekistan which are main countries in the central Asia. To make a basis on exchanging researchers, a staff in KAERI had visited INP NNC RK, touring research reactors, and make a discussion with the staffs in INP. With this, there is a efforts to make an arrangement between KAERI and NNC RK, signing will be made in near futures. To understand the level of nuclear technology in Uzbekistan, Dr. Rho had made a trip to INP. He visited the Gamma-radiation facility, a research reactor. In Nov. 2005, the chairman of Science Academy visited Korea to discuss the future cooperation in the field of peaceful use of the nuclear energy. By doing so, Korea will make an effort to cooperate with countries in the Central Asia.

  15. Management of radioactive waste packaging drum

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Il-Sik; Shon, Kang J. S.; Lee, Y. H.; Song, I. T.; Lee, B. C.; Kim, K. J. [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-02-01

    Radioactive waste drums of dismantled equipment and contaminated soil waste generated from KAERI research reactor, Seoul in 1988 were transferred to KAERI in Taejeon and are stored at low and medium level storage building until now. As a result of relatively long term storage, a corrosion on the surface of the drums was progressed and a remedial action was conducted to take a measure for the enhancement of safety. Thus, we examined the corrosion status on the surface of waste drums and studied mostly applicable methods. Resultingly, the seriously corroded drums were repackaged and the slightly corroded drums were painted after removing a corroded part on the surface. 12 refs., 14 figs., 12 tabs. (Author)

  16. Development of the Decommissioning Project Management System, DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Park, J. H.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-03-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The management of the projects can be defined as 'the decision of the changes of the decommissioning methodologies for the more efficient achievement of the project at an adequate time and to an improved method'. The correct decision comes from the experiences on the decommissioning project and the systematic experiences can be obtained from the good management of the decommissioning information. For this, a project management tool, DECOMMIS, was developed in the D and D Technology Division, which has the charge of the decommissioning projects at the KAERI, and its purpose was extended to following fields; generation of reports on the dismantling waste for WACID, record keeping for the next decommissioning projects of nuclear facilities, provision of fundamental data for the R and D of the decommissioning technologies.

  17. Development of a preliminary PIRT (Phenomena Identification and Ranking Table) of thermal-hydraulic phenomena for 330MWt SMART integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, B. D.; Lee, W. J.; Sim, S. K.; Song, J. H.; Kim, H. C.

    1997-09-01

    The work reported in this document identifies the thermal-hydraulic phenomena that are expected to occur during a number of key transients in a 330 MWt SMART integral reactor which is under development at KAERI. The result of this efforts is based on the current design concept of SMART integral reactor. Although the design is still evolving, the preliminary Phenomena Identification and Ranking Table (PIRT) has been developed based on the experts` knowledge and experience. The preliminary PIRT has been developed by the consensus of KAERI expert panelists and AHP (Analytical Hierarchy Process). Preliminary PIRT developed in this report is intended for use to identify and integrate development areas of further experimental tests needed and thermal-hydraulic models and correlations and code improvements for the safety analysis of the SMART integral reactor. (author). 7 refs., 21 tabs., 22 figs.

  18. Development of a preliminary PIRT (Phenomena Identification and Ranking Table) of thermal-hydraulic phenomena for SMART

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Bub Dong; Lee, Won Jae; Kim, Hee Cheol; Song, Jin Ho; Sim, Suk Ku [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The work reported in this paper identifies the thermal-hydraulic phenomena that are expected to occur during a number of key transients in SMART (System-integrated Modular Advanced ReacTor) which is under development at KAERI. The result of this effort is based on the current design concept of SMART integral reactor. Although the design is still evolving, the preliminary Phenomena Identification and Ranking Table (PIRT) has been developed based on the experts` knowledge and experience. The preliminary PIRT has been developed by consensus of KAERI expert panelists and AHP (Analytical Hierarchy Process). Preliminary PIRT developed in this paper is intended to be used to identify and integrate development areas of further experimental tests needed, thermal hydraulic models and correlations and code improvements for the safety analysis of the SMART. 8 refs., 4 tabs (Author)

  19. Waste Information Management System-2012 - 12114

    Energy Technology Data Exchange (ETDEWEB)

    Upadhyay, H.; Quintero, W.; Shoffner, P.; Lagos, L.; Roelant, D. [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States)

    2012-07-01

    The Waste Information Management System (WIMS) -2012 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 40 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. WIMS continues to successfully accomplish the goals and objectives set forth by DOE for this project. It has

  20. Fluid dynamics evaluation of split vane grid spacer in a small modular reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nazififard, Mohammad [Kashan Univ (Iran, Islamic Republic of). Dept. of Energy System Engineering; Seoul National Univ. (Korea, Republic of). Dept. of Nuclear Engineering; Philosophia, Seoul (Korea, Republic of); Nematollahi, Mohammadreza [Shiraz Univ. (Iran, Islamic Republic of). Dept. of Nuclear Engineering; Suh, Kune Y. [Seoul National Univ. (Korea, Republic of). Dept. of Nuclear Engineering; Philosophia, Seoul (Korea, Republic of)

    2015-12-15

    This paper numerically evaluates the effect of a split vane grid spacer on thermohydrodynamics in a subchannel of a typical small modular pressurized water reactor. The turbulent convective heat transfer and pressure drop are numerically calculated. Thermohydrodynamics and neutronics coupling would indeed be interesting for more quantitative analyses of the fuel assembly design, heat transfer correlation and mixing coefficient for the System-Integrated Modular Advanced Reactor (SMART) being developed by the Korea Atomic Energy Research Institute (KAERI).

  1. Nuclear design manual for generation of cross section and heterogeneous formfunction for CASMO-3/MASTER

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Ho; Cho, Byung Oh; Song, Jae Seong; Lee, Chung Chan

    1996-12-01

    A three-dimensional reactor core simulation code, MASTER, has been developed as a part of the ADONIS project in KAERI. CASMO-3 prepares various two-group cross sections for the constituents of a reactor core such as fuel assembly, radial and axial reflectors, control rod and detector for MASTER. This report includes the standard design procedure for generation of two-group cross sections and heterogeneous formfunction by CASMO-3/FORM for MASTER. (author). 16 refs., 16 tabs., 12 figs.

  2. Verification of ONED90 code

    International Nuclear Information System (INIS)

    ONED90 developed by KAERI is a 1-dimensional 2-group diffusion theory code. For nuclear design and reactor simulation, the usage of ONED90 encompasses core follow calculation, load follow calculation, plant power control simulation, xenon oscillation simulation and control rod maneuvering, etc. In order to verify the validity of ONED90 code, two well-known benchmark problems are solved by ONED90 shows very similar result to reference solution. (Author) 11 refs., 5 figs., 13 tabs

  3. Participation in benchmark MATIS-H of NEA/OCDE: uses CFD codes applied to nuclear safety. Study of the spacer grids in the fuel elements

    International Nuclear Information System (INIS)

    This paper develops participation in benchmark MATIS-H, promoted by the NEA / OECD-KAERI, involving the study of turbulent flow in a rod beam with spacers in an experimental installation. Its aim is the analysis of hydraulic behavior of turbulent flow in the subchannels of the fuel elements, essential for the improvement of safety margins in normal and transient operations and to maximize the use of nuclear energy through an optimal design of grids.

  4. Development of real-time monitoring and control in COIL laser cutting for joint R and D between Korea and U.S

    International Nuclear Information System (INIS)

    The laser monitoring and control technique investigated to experiment for cutting kerf width and result of laser cutting for D and D of nuclear facility. The demands for this laser monitoring and control technique were applied to process control in laser cutting and to fabricate monitoring and control system, focusing lens assembly. This system can had a advantage to monitor and control the laser cutting on real time. KAERI investigated the COIL laser and monitored 2 kW laser power

  5. Development of fuel test loop in HANARO

    International Nuclear Information System (INIS)

    KAERI have developed a fuel test loop facility to conduct the fuel irradiation test at HANARO. Maximum 3 pins of fuel can be tested in the IR-1 irradiation hole of HANARO under commercial power plant operating conditions. The integral system performance test with mock-up fuels under a high temperature is being performed. The FTL will be used for an advanced fuel irradiation test and could maximize the usage of HANARO. (author)

  6. Experimental Report for Safety Relevant Design Basis Accident Tests by using the High Temperature/High Pressure Test Facility(VISTA)

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Ki Yong; Park, Hyun Sik; Cho, Seok; Lee, Sung Jae; Choi, Nam Hyun; Min, Kyong Ho; Song, Chul Hwa; Park, Chun Kyong; Chung, Moon Ki

    2005-07-15

    The VISTA (Experimental Verification by Integral Simulation of Transients and Accidents) is an experimental facility to verify the performance and safety issues of the SMART-P (Pilot plant of the System-integrated Modular Advanced Reactor). The basic design of the SMART-P has been completed by KAERI. The present report describes experimental test results for safety relevant design basis accidents by using the VISTA facility.

  7. Simulation of Shielding Effects on the Total Dose Observed in TDE of KISAT-1

    Science.gov (United States)

    Kim, Sung-Joon; Shin, Young Hoon; Min, Kyoung Wook

    2001-06-01

    The threshold voltage shift observed in TDE (Total Dose Experiment) on board the KITSAT-1 is converted into dose (rad(SiO2)) usinsg the result of laboratory calibration with Co-60 gamma ray source in KAERI (Korea Atomic Energy Research Institute). Simulation using the NASA radiation model of geomagnetosphere verifies that the dose difference between RADFET1 and RADFET3 observed on KITSAT-1 comes from the difference in shielding thickness at the position of these RADFETs.

  8. The small angle neutron spectrometer at the HANARO reactor, Korea

    Science.gov (United States)

    Seong, B.-S.; Han, Y.-S.; Lee, C.-H.; Lee, J.-S.; Hong, K.-P.; Park, K.-N.; Kim, H.-J.

    A new small angle neutron spectrometer (SANS) has been installed on the CN beam tube at the 30 MW HANARO Research Reactor in the Korea Atomic Energy Research Institute (KAERI). The SANS is to be used for the study of microstructural inhomogeneities in materials in the 1 nm to 100 nm size range. In this paper, the design characteristics of the spectrometer are presented in detail, and several SANS results for standard samples are presented which illustrate its performance.

  9. Present status of residual stress instrument at the HANARO

    Science.gov (United States)

    Moon, Myung-Kook; Em, Vyacheslav; Lee, Chang-Hee; Cheon, Jong-Kyu; Choi, Young-Hyun; Nam, Uk-Won; Kong, Kyung-Nam

    2006-11-01

    The new residual stress instrument was installed recently at beam port ST-1 at the HANARO reactor in KAERI. The instrument is equipped with 200 mm high position-sensitive detector. The shielding drum for monochromator allows take-off angle in the range of 2 θM=0-60°. A horizontally focusing bent perfect crystal Si monochromator with (2 2 0) reflecting plane was found to be the most appropriate for the instrument.

  10. Maintenance and fabrication of electronic equipment

    CERN Document Server

    Chung, C E; Kim, J B; Kim, Y K; Moon, B S

    2001-01-01

    Providing technical support to the maintenance and repair problems of electronic instruments, we have assisted the research and development work, and made it done effectively in KAERI. In addition, we have improved the performance of the alarming system of the unit211 in PIEF and the lamp control module(IND100) in RWTF using PLCs. And also, electronic circuit modules for MAFF system which is an instrument for airborne monitoring in radiation area have been designed and fabricated.

  11. The improvement of the education courses on radiation protection and radioisotope handling

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Han Suk; Kim, Woong Ki [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    About 48,000 nuclear personnel and 10,000 radioisotope personnel have participated in the KAERI-NTC's education and training programs. For the needs of personnel in radioisotope and radiation handling, KAERI-NTC has operated a class-room based full-time course for 4 weeks for applicants of a general license and 6 weeks for applicants of supervisor license. These courses educated almost 3,908 trainees for general radioisotope handling and 1,856 trainees for supervisors of radiation handling. Since the Korean Association for Radiation Application (KARA) was established in 1985 and the Korea Academy of Nuclear Safety (KANS) was established in 2002, KARA and KANS have operated with a non-classroom based correspondence course. According to this role separation in training radioisotope handling personnel, KAERI-NTC tried to improve the classroom based courses. The number of applicants of general radioisotope handling in recent years is increasing around 3,000 - 4,000 in a year. The real participants in an general license test are 2,105 to 2,841 in 2013 and 2014. The ratio of successful applicants in general isotope handling are just the 23% in 2013 and 4.2% in 2014. Addressing this low ratio of successful applicants, several proactive measures in KAERI-NTC were considered to enhance these courses for general users and supervisors. The purpose of this paper is to provide. For the further development of these courses, our measures were classified the measures in the Implementation stage of the ADDIE model. In addition to this Implementation stage, it is recommended that these actions should be applied to the other stages of ADDIE such as Analysis, Design, Development and Evaluation.

  12. The first technical report for the improvement of R and D evaluation : Focusing on the evaluation reaction of R and D project investigator

    Energy Technology Data Exchange (ETDEWEB)

    Yeo, Ji Won; Kim, I.C.; Won, B.C.; Kim, M.R. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1997-12-01

    The main objectives of this report are as follows. - Measuring the project manager's reaction on R and D evaluation and determining its influencing factors. - Testing the relationship between personal characteristics (tolence for ambiguity, risk-taking propensity, self-efficacy, Turn-over intention) and the outcome of Project Evaluation. - Presenting the useful information related to rebuilding a R and D Evaluation System of KAERI (Korea Atomic Energy Research Institute). 72 refs., 6 figs., 41 tabs. (Author)

  13. Development of a Remote Handling System in an Integrated Pyroprocessing Facility

    OpenAIRE

    Hyo Jik Lee; Jong Kwang Lee; Byung Suk Park; Kiho Kim; Won Il Ko; Il Je Cho

    2013-01-01

    Over the course of a decade-long research programme, the Korea Atomic Energy Research Institute (KAERI) has developed several remote handling systems for use in pyroprocessing research facilities. These systems are now used successfully for the operation and maintenance of processing equipment. The most recent remote handling system is the bridge-transported dual arm servo-manipulator system (BDSM), which is used for remote operation at the world’s largest pyroprocess integrated inactive demo...

  14. Nuclear design aspect of the Korean high intensity proton accelerator project

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Jonghwa; Song, Tae-Yung [Korea Atomic Energy Research Inst., Yusong, Taejon (Korea, Republic of)

    1998-11-01

    A plan to construct a high current proton accelerator has been proposed by KAERI. We are presenting the required nuclear design to support the project as well as a brief overview of the proposed proton accelerator. The target and core design is highlighted to show feasibility of incineration of minor actinides from the spent fuel of light water reactors. Radiation shielding and activation analyses are also important for the design and the license of the accelerator. (author)

  15. Establishment of Oversea HRD Network and Operation of International Nuclear Education/Training Program

    International Nuclear Information System (INIS)

    The project deals with establishment of international network for human resources and the development of international nuclear education and training programs. The primary result is the establishment of KAERI International Nuclear R and D Academy as a new activity on cooperation for human resource development and building network. For this purpose, KAERI concluded the MOU with Vietnamese Universities and selected 3 students to provide Master and Ph. D. Courses in 2008. KAERI also held the 3rd World Nuclear University Summer Institute, in which some 150 international nuclear professionals attended for 6 weeks. Also, as part of regional networking, the Asian Network for Education in Nuclear Technology (ANENT) was promoted through development of a cyber platform and accomplishment the first IAEA e-training course. There were 3 kind of development activities for the international cooperation of human resources development. Firstly, the project provided training courses on nuclear energy development for the Egyptian Nuclear personnel under the bilateral cooperation. Secondly, the project published the English textbook and its lecture materials on introduction to nuclear engineering and fundamentals on OPR 1000 system technology. Lastly, the project developed a new KOICA training course on research reactor and radioisotope application technology to expand the KOICA sponsorship from 2008. The international nuclear education/training program had offered 15 courses to 314 people from 52 countries. In parallel, the project developed 11 kinds of lecturer materials and also developed 29 kinds of cyber lecturer materials. The operation of the International Nuclear Training and Education Center (INTEC) has contributed remarkably not only to the effective implementation of education/training activities of this project, but also to the promotion of other domestic and international activities of KAERI and other organizations

  16. Verification of ONED90 code

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Jong Hwa; Lee, Ki Bog; Zee, Sung Kyun; Lee, Chang Ho [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-12-01

    ONED90 developed by KAERI is a 1-dimensional 2-group diffusion theory code. For nuclear design and reactor simulation, the usage of ONED90 encompasses core follow calculation, load follow calculation, plant power control simulation, xenon oscillation simulation and control rod maneuvering, etc. In order to verify the validity of ONED90 code, two well-known benchmark problems are solved by ONED90 shows very similar result to reference solution. (Author) 11 refs., 5 figs., 13 tabs.

  17. Development of a pilot size of electrochemical flushing equipment for radioactive soil and concrete

    International Nuclear Information System (INIS)

    A pilot size of electrochemical flushing equipment will be manufactured suitable to the contamination characteristics of radioactive soil and concrete stored in KAERI radioactive waste storage. An optimal reagent and an optimal decontamination conditions should be decided through many experiments. - Contamination characterises analysis of TRIGA radioactive soil and concrete - Manufacture of pilot-scale electrochemical flushing equipment - Manufacture and improvement of suitable electrochemical flushing equipment for contamination characteristics in pilot size - Decontamination experiments of electrochemical flushing equipment in a pilot scale

  18. NUCLEAR HYDROGEN DEVERLOPMENT AND DEMONSTRATION PROGRAM IN KOREA

    Institute of Scientific and Technical Information of China (English)

    林昌奎; 朴原奭; 张锺和

    2004-01-01

    The Korea Atomic Energy Research Institute (KAERI) launched a nuclear hydrogen program to develop and demonstrate a hydrogen mass production system by 2019. The key feature of the system is to produce the hydrogen from water using nuclear power. No fossil fuel (energy) will be used and no greenhouse gas will be emitted. The high temperature gas-cooled reactor (HTGR), which has high safety characteristics with competitive economy, is being developed to provide a high temperature heat (about 1000℃) requir...

  19. Development on the radiological emergency management guide

    Energy Technology Data Exchange (ETDEWEB)

    Khang, Byung Oui; Lee, Jong Tai; Lee, Goan Yup; Lee, Moon

    2000-01-01

    The comprehensive emergency management system in KAERI describes the requirements for emergency plan, preparedness, evaluations and readiness assurance, response and recovery activities to timely and effectively countermeasure according to the type and size of an event. The guidance of facility emergency plan and detailed response procedures for initial action, building/site evacuation, personnel accountability, search and fire fighting in the radioactive, fissionable, toxic and inflammable hazardous substances handling facilities are also developed. (author)

  20. MELCOR DB Construction for the Severe Accident Analysis DB

    Energy Technology Data Exchange (ETDEWEB)

    Song, Y. M.; Ahn, K. I. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-10-15

    The Korea Atomic Energy Research Institute (KAERI) has been constructing a severe accident analysis database (DB) under a National Nuclear R and D Program. In particular, an MAAP (commercial code being widely used in industries for integrated severe accident analysis) DB for many scenarios including a station blackout (SBO) has been completed. This paper shows the MELCOR DB construction process with examples of SBO scenarios, and the results will be used for a comparison with the MAAP DB

  1. Development on the radiological emergency management guide

    International Nuclear Information System (INIS)

    The comprehensive emergency management system in KAERI describes the requirements for emergency plan, preparedness, evaluations and readiness assurance, response and recovery activities to timely and effectively countermeasure according to the type and size of an event. The guidance of facility emergency plan and detailed response procedures for initial action, building/site evacuation, personnel accountability, search and fire fighting in the radioactive, fissionable, toxic and inflammable hazardous substances handling facilities are also developed. (author)

  2. Influence of dopants on the glow curve structure and energy dependence of LiF:Mg, Cu, Si detectors

    OpenAIRE

    Knežević, Željka; Ranogajec-Komor, Maria; Miljanić, Saveta; Lee, Jungil; Kim, Jang-Lyul; Musić, Svetozar

    2011-01-01

    LiF thermoluminescent material doped with Mg, Cu and Si recently developed by the Korea Atomic Energy Research Institute (KAERI) has shown very good dosimetric properties. Since the thermoluminescence in LiF was found to be dependent on the proper combination of dopants, the investigation of the concentration and type of dopants is very important in developing and characterisation of new TL materials. The aim of this work was to determine the influence of type and concentration of activators ...

  3. Presence of inulin-type fructo-oligosaccharides and shift from raffinose family oligosaccharide to fructan metabolism in leaves of boxtree (Buxus sempervirens

    Directory of Open Access Journals (Sweden)

    Wim eVan den Ende

    2016-03-01

    Full Text Available from raffinose family oligosaccharide to fructan metabolism in leaves of boxtree (Buxus sempervirens Wim Van den Ende1,* Marlies Coopman1, Rudy Vergauwen1, André Van Laere11 KU Leuven, Laboratory of Molecular Plant Biology, Institute of Botany and Microbiology, Kasteelpark Arenberg 31, B-3001 Leuven, Belgium* Correspondence: Wim Van den Ende, Laboratory of Molecular Plant Biology,Institute of Botany and Microbiology, Kasteelpark Arenberg 31, B-3001 Leuven, Belgium tel +32 16321952; fax +32 16321967;Wim.vandenende@bio.kuleuven.beKeywords: inulin, oligosaccharides, stress, RFO, fructanAbstractFructans are known to occur in 15% of flowering plants and their accumulation is often associated with stress responses. Typically, particular fructan types occur within particular plant families. The family of the Buxaceae, harbouring Pachysandra terminalis, an accumulator of graminan- and levan-type fructans, also harbours boxtree (Buxus sempervirens, a cold and drought tolerant species. Surprisingly, boxtree leaves do not accumulate the expected graminan- and levan-type fructans but small inulin fructo-oligosaccharides (FOS: 1-kestotriose and nystose and raffinose family oligosaccharides (RFO: raffinose and stachyose instead. The seasonal variation in concentrations of glucose, fructose, sucrose, FOS and RFO were followed. Raffinose and stachyose peaked during the winter months, while FOS peaked at a very narrow time-interval in spring, immediately preceded by a prominent sucrose accumulation. Sucrose may function as a reserve carbohydrate in winter and early spring leaves. The switch from RFO to fructan metabolism in spring strongly suggests that fructan and RFO fulfil distinct roles in boxtree leaves. RFO may play a key role in the cold acclimation of winter leaves while temporal fructan biosynthesis in spring might increase sink strength to sustain the formation of new shoots.

  4. Waste Information Management System with 2012-13 Waste Streams - 13095

    Energy Technology Data Exchange (ETDEWEB)

    Upadhyay, H.; Quintero, W.; Lagos, L.; Shoffner, P.; Roelant, D. [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States)

    2013-07-01

    The Waste Information Management System (WIMS) 2012-13 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 40 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. (authors)

  5. Establish the Foundation of Environmental Assessment Technique in ROK via the International Environmental Modelling for Radiation Safety Managed by IAEA

    International Nuclear Information System (INIS)

    Tritiated water (HTO) released from the nuclear facilities can easily be absorbed by plants via their stomata and incorporated into organics by metabolic processes such as photosynthesis. Organically bound tritium (OBT) in plant cells is mostly inexchangeable and remains at harvest to contribute some to the ingestion radiation dose (Barry et al., 1999). In assessing the ingestion dose due to an accidental release of HTO, a dynamic model simulating its environmental behaviors is needed. Various types of dynamic HTO models have been developed in many different countries. Joint international researches have been conducted many times for model comparisons and validations (BIOMOVS II, 1996a, 1996b). In 2003, however, with the understanding of an insufficiency in the validation test, the IAEA started on a joint international research program for the validation of environmental models (EMRAS : Environmental Modelling for Radiation Safety) as a successor to the BIOMASS (2001). The KAERI submitted 'a scenario of an acute soybean exposure to HTO' to the Tritium Working Group (Theme 1) in the EMRAS program. It was accepted as Task 2 of the working group. This report is the result of a joint research for the KAERI scenario carried out by the EMRAS tritium working group with the KAERI playing a role of a coordinator

  6. The 24 CANFLEX-NU bundle demonstration irradiation at Wolsong-1 generating station-bundle manufacture and QA, fuel handling aspects, flasking and shipping and pie for the irradiated fuel, and follow-up documentation

    International Nuclear Information System (INIS)

    Korea Ministry of Science and Technology(MOST) has pushed and given a financial support to a KEPRI/KAERI Joint Industrialization Program of CANFLEX-NU Fuel as one of Korea's National Nuclear Mid- and Long Term R and D Program. The Industrialization Program will be conducted for 3 years from 2000 November to efficiently utilize the CANFLEX fuel technology developed by KAERI and AECL jointly, where the KAERI's works have been conducted under the Korea's national program of the mid- and long-term nuclear R and D programs since 1992. This document is a report to guideline the following activities on the safety assessment for the 24 CANFLEX-NU (CANDU Flexible fuelling-Natural Uranium) fuel bundle demonstration irradiation at Wolsong-1 Generating Station: 'bundle manufacture and QA', 'Fuel handling aspects such as loading fuel, de-fuelling and segregation, and visual in-bay examinations', 'Flasking and shipping', 'Post-irradiation examination', and 'Follow-up documentation to be produced'

  7. Workstation environment supports for startup of YGN 3 and 4 nuclear unit

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Won Jae; Kim, Won Bong; Lee, Byung Chae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Light water reactor fuel development division of Korea Atomic Energy Research Institute participated in the installation of the plant computer system and software, and the user support activities of Asea Brown Boveri/Combustion Engineering for the Plant Monitoring System during the startup phase of YGN-3 nuclear unit. The main purpose of the participation is to have the self-reliant plant- computer technology for the independent design and startup of next nuclear units. This report describes the activities performed by KAERI with ABB/CE at the plant site. In addition, it describes the direct transfer of data files between PMS and workstation which was independently carried out by KAERI. Since KAERI should support the site in setting-up the plant computer environment independent of ABB-CE from the next nuclear units, the review was performed for the technical details of activities provided to the site in order to provide the better computer environment in the next nuclear units. In conclusion, this report is expected to provide the technical background for the supporting of plant computing environment and the scope of support work at plant site during Yonggwang 3, 4 startup in the area of plant computer for the next nuclear units. 6 refs. (Author) .new.

  8. Korea-China Optical Technology Research Centre

    International Nuclear Information System (INIS)

    The main objectives of this project are to develop cooperative channel by personnel exchanges between industrial, educational and research partners of Korea and China on the fields of optical technologies which are the basis of optical industry and being spot-lighted as new industry of 21th century, and to raise the class of Korean optical technology up to world class by utilization of Chinese large facilities through the cooperative research between the optical technology institutions of both sides. To attain the goals mentioned above, we carried out the cooperative researches between the Korean and Chinese optical technology institutions in the following 7 fields; ? research cooperation between KAERI-SITP for the quantum structured far-IR sensor technology - research cooperation for the generation of femtosecond nuclear fusion induced neutrons - research cooperation between KAERI-AIOFM for laser environment analysis and remote sensing technology - research cooperation between KAERI-SIOM for advanced diode-pumped laser technology - cooperative research related on linear and nonlinear magneto-optical properties of advanced magnetic quantum structures - design of pico-second PW high power laser system and its simulation and - cooperative research related on the femto-second laser-plasma interaction physics

  9. Design modification of the in-pile test section for increase of sealing capability

    International Nuclear Information System (INIS)

    Since KAERI established the fuel test loop (FTL) at HANARO in 2009, KAERI has carried out several experiments to verify the performances of the equipment. Based on the experiments, the design modification of the In-Pile test Section (IPS) has been processed to improve some difficulties such as difficulty in ejecting the inner assembly of the IPS from the pressure vessel, difficulty of the sealing process of the cooling water, etc. At first, because the cooling water of HANARO in KAERI consists of an open-pool type, if a certain shock is generated during the disassembly process, the cooling water can be spattered out of the pool. Therefore, two jacking bolts will be added on the top flange part of the inner assembly to decrease the shock. Second, at the pressure boundary of the IPS where MI-cables go through, the brazing process has been used to seal out the cooling water. However, because the length of the IPS is up to 5.5 meters, it is too difficult and time consuming to carry out the brazing process at the end part of the IPS. Therefore, the brazing process will be replaced with the mechanical sealing structure to simplify the assembly process. (author)

  10. Korea-China Optical Technology Research Centre

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Cheol Jung; Cha, H. K.; Rhee, Y. J. (and others)

    2007-04-15

    The main objectives of this project are to develop cooperative channel by personnel exchanges between industrial, educational and research partners of Korea and China on the fields of optical technologies which are the basis of optical industry and being spot-lighted as new industry of 21th century, and to raise the class of Korean optical technology up to world class by utilization of Chinese large facilities through the cooperative research between the optical technology institutions of both sides. To attain the goals mentioned above, we carried out the cooperative researches between the Korean and Chinese optical technology institutions in the following 7 fields; ? research cooperation between KAERI-SITP for the quantum structured far-IR sensor technology - research cooperation for the generation of femtosecond nuclear fusion induced neutrons - research cooperation between KAERI-AIOFM for laser environment analysis and remote sensing technology - research cooperation between KAERI-SIOM for advanced diode-pumped laser technology - cooperative research related on linear and nonlinear magneto-optical properties of advanced magnetic quantum structures - design of pico-second PW high power laser system and its simulation and - cooperative research related on the femto-second laser-plasma interaction physics.

  11. Development of cold neutron depth profiling system at HANARO

    Science.gov (United States)

    Park, B. G.; Sun, G. M.; Choi, H. D.

    2014-07-01

    A neutron depth profiling (NDP) system has been designed and developed at HANARO, a 30 MW research reactor at the Korea Atomic Energy Research Institute (KAERI). The KAERI-NDP system utilizes cold neutrons that are transported along the CG1 neutron guide from the cold neutron source and it consists of a neutron beam collimator, a target chamber, a beam stopper, and charged particle detectors along with NIM-standard modules for charged particle pulse-height analysis. A 60 cm in diameter stainless steel target chamber was designed to control the positions of the sample and detector. The energy distribution of the cold neutron beam at the end of the neutron guide was calculated by using the Monte Carlo simulation code McStas, and a neutron flux of 1.8×108 n/cm2 s was determined by using the gold foil activation method at the sample position. The performance of the charged particle detection of the KAERI-NDP system was tested by using Standard Reference Materials. The energy loss spectra of alpha particles and Li ions emitted from 10B, which was irradiated by cold neutrons, were measured. The measured peak concentration and the areal density of 10B in the Standard Reference Material are consistent with the reference values within 1% and 3.4%, respectively.

  12. KEIMS utility manual (edition 1.0)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeun Seung; Eom, Young Sam; Choi, Jin Yeup; Nam, Ji Hwa [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-06-01

    Since 1987 when KAERI had started Yonggwang 3 and 4 NSSS system design project, KAERI has carried out so many NSSS system design projects such as Ulchin 3 and 4, Wolsong 2, 3 and 4 and Yonggwang 5 and 6 with fixed members that necessity of increasing productivity has been raised. To improve design work efficiency, it was considered that computerization of workflow which took so much man-power and business time. As result of investigation of design workflow to reduce man-power loss. It was suggested that DDA (Document Distribution for Agreement) workflow, design document stored in DDCD (Document Distribution and Control Center), IOC (Interoffice Correspondence) document, Letter, PM Memo should be preferentially computerized. On the basis of these computerization requirements, MEDIS (Modular Engineering Document Imaging System) was selected. Prototype had been implemented during 1995.9 -1995.12, and from 1996.1 KEIMS (KAERI Engineering Information Management System) has been operated. This MEDIS system utility manual was composed of several technical memos which has been described on customization of MEDIS fit to KEIMS, program development for system check, and information control of database. Further edition would be released as utility technical memo added. (Author) .new.

  13. Comparison of various methods to quantify a fault tree for Seismic PSA

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sang Hoon; Park, Jin Hee; Kim, Dong San; Lim, Ho-Gon; Jang, Seung Cheol [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    Typically, quantification (evaluation of frequency) of a sequence in a PSA is performed by generating minimal cut sets and quantifying it using REA (Rare event approximation) or MCUB (Minimal cut upper bound) method. MCUB gives more exact value than REA. But, it is known that REA and MCUB method may produce very conservative value when a probability of each event is larger than 0.1 such as in seismic PSA. The PSA software AIMS-PSA and FTREX developed in KAERI use REA and MCUB method to quantify a PSA model. Thus, it is necessary to verify the quantification result for seismic PSA. There are several method/software available for the verification. ACUBE developed by EPRI quantifies the pre-generated minimal cut sets using BDD (binary decision diagram) method. FTeMC developed by KAERI is based on Monte Carlo method. FtBdd developed by KAERI is based on BDD, but it can be applied for small fault trees. In section 2, a simple example is provided to characterize various methods. The results of those methods are compared for a seismic PSA model. REA and MCUB may produce very conservative value for a seismic PSA model which includes events whose probabilities are large. It is not easy to get the exact value for every case. We should recognize the limitation of each method/software when analyzing the quantification results for PSA. To verify the results, a supporting analysis can be used using other software such as Monte Carlo method.

  14. Internet services for nuclear data

    International Nuclear Information System (INIS)

    Modern internet technology make it possible to acquire the up to data and reliable nuclear data easily for the user. Main international and national centers distributing the nuclear data are as follows: · IAEA Nuclear Data Section (http://www-nds.iaea.or.at/) · NEA Databank (http://www.nea.fr/html/databank/) · BNL National Nuclear Data Center (http://www.nndc.bnl.gov/) · LANL T2 (http://t2.lanl.gov/) · JAERI Japanese Nuclear Data Center (http://www.nndc.tokai.jaeri.go.jp/) KAERI is also servicing a nuclear data web server since 1994(http://hpngp01.kaeri.re.kr/). The target customers for the KAERI web server are those who are not so familiar with the conventions of nuclear data production society. The server has a 'Table of Nuclides' with graphic interface which contains the mass of nuclides, the decay and half life, the decay scheme, the neutron capture cross section, the fission yields and the neutron cross section. An interactive cross section plotter is provided to compare the cross sections between each evaluated files. We have archived the MCNP library sets, which were processed upon the request from domestic users. An electron and X-ray attenuation factor calculator is also provided for medical scientists

  15. Study of nuclear computer code maintenance and management system

    International Nuclear Information System (INIS)

    Software maintenance is one of the most important problems since late 1970's.We wish to develop a nuclear computer code system to maintenance and manage KAERI's nuclear software. As a part of this system, we have developed three code management programs for use on CYBER and PC systems. They are used in systematic management of computer code in KAERI. The first program is embodied on the CYBER system to rapidly provide information on nuclear codes to the users. The second and the third programs were embodied on the PC system for the code manager and for the management of data in korean language, respectively. In the requirement analysis, we defined each code, magnetic tape, manual and abstract information data. In the conceptual design, we designed retrieval, update, and output functions. In the implementation design, we described the technical considerations of database programs, utilities, and directions for the use of databases. As a result of this research, we compiled the status of nuclear computer codes which belonged KAERI until September, 1988. Thus, by using these three database programs, we could provide the nuclear computer code information to the users more rapidly. (Author)

  16. Nuclear Manpower Development

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, I. A.; Lee, K. B.; Shin, B. C. [KAERI, Daejeon (Korea, Republic of)

    2010-12-15

    The industry-university-research collaborative education is aiming at developing national nuclear human resources to satisfy with the increasing needs from the industry. For this efforts are being made to develop curricula customized to respective industry needs by improving existing ones. As the demand for training programs for the university students and domestic nuclear personnel was increasing owing to revitalization of nuclear industry, Nuclear Training Center (NTC) improved previous education programs to meet the needs. NTC has operated 2 education programs on research reactor experiments for the university students, and 18 programs on nuclear technology related experiment courses in 2010. Furthermore, the NTC developed new education programs related to 'standardized research reactor system design'. Also the request from universities for internship programs was increased by about three times in 2010 compared to those of the previous year, and this required to develop relevant curricula. In 2005, NTC developed KAERI-ACE, as a unique competency-based staff education system of Korea Atomic Energy Research Institute (KAERI). Based on the system, the NTC has performed 'systematic education'. In 2008, NTC was awarded Best HRD(Human Resource Development) in Public sector for the first time as a government-supported research institute. In 2009, the system was improved to become KAERI-ACE 2.0, based on which, in 2010, NTC improved and diversified education programs including various cyber training programs

  17. Nuclear Manpower Development

    International Nuclear Information System (INIS)

    The industry-university-research collaborative education is aiming at developing national nuclear human resources to satisfy with the increasing needs from the industry. For this efforts are being made to develop curricula customized to respective industry needs by improving existing ones. As the demand for training programs for the university students and domestic nuclear personnel was increasing owing to revitalization of nuclear industry, Nuclear Training Center (NTC) improved previous education programs to meet the needs. NTC has operated 2 education programs on research reactor experiments for the university students, and 18 programs on nuclear technology related experiment courses in 2010. Furthermore, the NTC developed new education programs related to 'standardized research reactor system design'. Also the request from universities for internship programs was increased by about three times in 2010 compared to those of the previous year, and this required to develop relevant curricula. In 2005, NTC developed KAERI-ACE, as a unique competency-based staff education system of Korea Atomic Energy Research Institute (KAERI). Based on the system, the NTC has performed 'systematic education'. In 2008, NTC was awarded Best HRD(Human Resource Development) in Public sector for the first time as a government-supported research institute. In 2009, the system was improved to become KAERI-ACE 2.0, based on which, in 2010, NTC improved and diversified education programs including various cyber training programs

  18. Development of fission Mo production technology

    International Nuclear Information System (INIS)

    The feasibility study is accomplished in this project for the development of fission moly production. The KAERI process proposed for development in KAERI is discussed together with those of the American Cintichem and Russian IPPE, each of which would be plausible for introduction whenever the indigenous development is not much feasible. For the conceptual design of the KAERI irradiation target, analysis method is set up and some preliminary analysis is performed accordingly for the candidate design. To establish chemical process concepts for the afore-mentioned three processes, characteristics, operation conditions, and the management of the generated wastes are investigated. Basic requirements of hotcell facilities for chemical processing and a possible way of utilizing the existing hotcells are discussed in parallel with the counter-measures for the construction of new hotcell facilities. Various conditions of target irradiation for fission moly production in Hanaro are analyzed. Plan for introduction of the relevant technology introduction and for procurement of highly enriched uranium are considered. On the basis of assuming some conditions, the economic feasibility study for fission moly production is also overviewed. (author). 22 refs., 28 tabs., 24 figs

  19. Current state of the construction of an integrated test facility for hydrogen risk

    Energy Technology Data Exchange (ETDEWEB)

    Na, Young Su; Hong, Seong-Ho; Hong, Seong-Wan [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    Experimental research on hydrogen as a combustible gas is important for an assessment of the integrity of a containment building under a severe accident. The Korea Atomic Energy Research Institute (KAERI) is preparing a large-scaled test facility, called SPARC (SPray-Aerosol-Recombiner-Combustion), to estimate the hydrogen behavior such as the distribution, combustion and mitigation. This paper introduces the experimental research activity on hydrogen risk, which was presented at International Congress on Advances in Nuclear Power Plants (ICAPP) this year. The KAERI is preparing a test facility, called SPARC (SPray-Aerosol-Recombiner-Combustion test facility), for an assessment of the hydrogen risk. In the SPARC, hydrogen behavior such as mixing with steam and air, distribution, and combustion in the containment atmosphere will be observed. The SPARC consists of a pressure vessel with a 9.5 m height and 3.4 m in diameter and the operating system to control the thermal hydraulic conditions up to 1.5 MPa at 453 K in a vessel. The temperature, pressure, and gas concentration at various locations will be measured to estimate the atmospheric behavior in a vessel. To install the SPARC, an experimental building, called LIFE (Laboratory for Innovative mitigation of threats from Fission products and Explosion), was constructed at the KAERI site. LIFE has an area of 480 m''2 and height of 18.6 m, and it was designed by considering the experimental safety and specification of a large-sized test facility.

  20. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    For the KAERI site, various environmental samples were collected three times a month, and the natural environmental radiation levels were also measured at each sampling point. Measurements for gross alpha and beta radioactivities of the samples were routinely measured for all samples. Strontium-90 concentrations were also analysed for the fallout and air samples collected daily basis on the roof of the main building. Accumulated exposure including the possibility of determination of low level environmental radiation field by employing thermoluminescent dosimeter, CaSO4: Dsub(y)-0.4 teflon disc type, at 6 posts in on-site of the KAERI. As for Kori site, at 19 points of ON, OFF-site, and at the same time the environmental radiation exposure rate at each sampling point were measured. Several environmental samples such as surface soil, pine needles, water samples, milk sample and pasture samples were collected and analysed on a quarterly basis. As a result of the survey it can be said that no significant release of radiation to the environment due to the operations of nuclear facilities including research reactor at the KAERI and power reactor at the Kori has been found during the period of the survey and monitoring. (author)

  1. Cooperation of nuclear manpower development between Viet Nam and Korea in order to enhance establishment of infrastructure in exporting nuclear technology to Viet Nam

    Energy Technology Data Exchange (ETDEWEB)

    Lee, E. J.; Han, K. W.; Park, J. K.; Kim, Y. T.; Nam, Y. M.; Jang, Y. H.; Yang, M. H

    2003-08-15

    Through this project, KAERI provided OJT Programme to 3 nuclear experts of Viet Nam at the KAERI for 3 months as a cooperation of human resource development in the field of nuclear policy, nuclear safety analysis and thermo hydraulic. We could have publicity activities of S/W and H/W then achieve an advantage position of economical and technical in exporting nuclear technology to Viet Nam. Also we have provided a training course and seminar for a high-level delegation of nuclear policy decision makers, which is consisted of 5 deputy ministers and general directors of Viet Nam in Korea. Thus we could have Vietnamese who are favoring Korea. The KAERI will also prepare a data base of trained Vietnamese in Korea for the maximum utilization of them in cooperating with Viet Nam. We accomplished the cooperation of human resource development and providing program and curriculum of the nuclear education and training in Viet Nam. Furthermore, it is expected that the enhancement of nuclear technical cooperation between Viet Nam and Korea and the nuclear human resource development.

  2. Workstation environment supports for startup of YGN 3 and 4 nuclear unit

    International Nuclear Information System (INIS)

    Light water reactor fuel development division of Korea Atomic Energy Research Institute participated in the installation of the plant computer system and software, and the user support activities of Asea Brown Boveri/Combustion Engineering for the Plant Monitoring System during the startup phase of YGN-3 nuclear unit. The main purpose of the participation is to have the self-reliant plant- computer technology for the independent design and startup of next nuclear units. This report describes the activities performed by KAERI with ABB/CE at the plant site. In addition, it describes the direct transfer of data files between PMS and workstation which was independently carried out by KAERI. Since KAERI should support the site in setting-up the plant computer environment independent of ABB-CE from the next nuclear units, the review was performed for the technical details of activities provided to the site in order to provide the better computer environment in the next nuclear units. In conclusion, this report is expected to provide the technical background for the supporting of plant computing environment and the scope of support work at plant site during Yonggwang 3, 4 startup in the area of plant computer for the next nuclear units. 6 refs. (Author) .new

  3. Cooperation of nuclear manpower development between Viet Nam and Korea in order to enhance establishment of infrastructure in exporting nuclear technology to Viet Nam

    International Nuclear Information System (INIS)

    Through this project, KAERI provided OJT Programme to 3 nuclear experts of Viet Nam at the KAERI for 3 months as a cooperation of human resource development in the field of nuclear policy, nuclear safety analysis and thermo hydraulic. We could have publicity activities of S/W and H/W then achieve an advantage position of economical and technical in exporting nuclear technology to Viet Nam. Also we have provided a training course and seminar for a high-level delegation of nuclear policy decision makers, which is consisted of 5 deputy ministers and general directors of Viet Nam in Korea. Thus we could have Vietnamese who are favoring Korea. The KAERI will also prepare a data base of trained Vietnamese in Korea for the maximum utilization of them in cooperating with Viet Nam. We accomplished the cooperation of human resource development and providing program and curriculum of the nuclear education and training in Viet Nam. Furthermore, it is expected that the enhancement of nuclear technical cooperation between Viet Nam and Korea and the nuclear human resource development

  4. Analysis of Pending Problems for a Technology Demand of Domestic Operational Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Dae Seo; Park, Won Seok; Wi, Myung Hwan; Ha, Jae Joo

    2008-01-15

    Eleven technology fields were chosen, which have a relation with the solution of the pending problems of domestic operational nuclear power plants to manage an efficient operation and safe regulation for domestic nuclear power plants. The progressive background, requirements, and performance on the pending problems, 34, of an operation and regulation for domestic nuclear power plants were analyzed with regard to a risk information application, severe accident, PSR of structural materials, underwater monitoring, operation inspection and a fire protection, an instrument aging, metal integrity and steam generator, human technology and a digital I and C, quality assurance, secondary system and a user reliance and mass communications. KAERI's role is to provide a solution to these pending problems of domestic nuclear power plants. KAERI's technology is to be applicable to the pending problems for domestic nuclear power plants to raise an operational efficiency and an application frequency of nuclear power plants. In the future, a technology treaty between KAERI and KHNP is to be established to solve the pending problems for domestic nuclear power plants. Operation rate of nuclear power plants will also be raised and contribute to the supply of national energy due to this technology treaty.

  5. Control rod reactivity worth determination of a typical MTR research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Rizwan, M.; Raza, S.S.; Khan, R. [Pakistan Institute of Engineering and Applied Sciences (PIEAS), Islamabad (Pakistan). Dept. of Nuclear Engineering

    2015-10-15

    The safe and reliable utilization of research reactor demands the possible accurate information of control rod (CR) worths. The criticality positions of the control rods changes with time due to build up fission products. It is therefore important to determine the reactivity worth of control rods. The aim of this article is to estimate the reactivity worth of controls rods in the equilibrium core of a Materials Testing Reactor (MTR). A deterministic model of the reactor core was developed and confirmed against the reference results of excess reactivity, shutdown margin and combined control rod reactivity worth using the combination of WIMS/D4 and CITATION computer codes.

  6. Revised delayed neutron data for Pickering NGS B

    International Nuclear Information System (INIS)

    Revised delayed neutron fractions and constants were calculated specifically for Pickering NGS B using the latest available delayed neutron data for fissionable isotopes, the currently recommended CANDU delayed photoneutron data, and the formulae provided by Laughton. Burnup-dependent number densities of the fissionable isotopes were computed with WIMS-AECL-IST. Validation and assessment of the new fractions and constants was performed by comparison of historical operating data with point kinetics simulation using the new values. Recommendations are made regarding possible improvements to the delayed neutron data. (author)

  7. Liste des auteurs

    OpenAIRE

    2015-01-01

    Yves Tanguy, Université de Nantes, France Jacques Verger, Université Paris Sorbonne, Paris, France Jéremy duQuesnay Adams, Dept of History, SMU, USA Étienne Wolff, Université de Paris X­Nanterre, France Claire Nouvet, Emory University, USA François Lejeune, Université de Nantes, France Wim Verbaal, Université de Gand, Belgique Thomas N. Bisson, Harvard University, USA Jean Jolivet, École Pratique des Hautes Études, Paris, France Guy Lobrichon, Collège de France, France Constant J. Mews, Sc...

  8. WiMAX ja LTE neljännen sukupolven mobiililaajakaistateknologioina

    OpenAIRE

    Väätäinen, Tommi

    2012-01-01

    Insinöörityössä tutkittiin ja vertailtiin kahta neljännen sukupolven (4G) langatonta laajakaista- ja matkapuhelinteknologiaa WiMAX:ia ja LTE:tä tavoitteena selvittää niiden tulevaisuuden näkymiä 4G-mobiililaajakaistamarkkinoilla. Työn alkuvaiheessa selvitettiin kummankin teknologian ominaisuudet ja standardien kehityshistoria tähän päivään asti. Työn loppuvaiheessa tutkittiin WiMAX:in ja LTE:n välistä kilpailuasetelmaa teknisten ominaisuuksien, markkina- ja kilpailutilanteen kannalta. WiM...

  9. Analysis of the impact of coolant density variations in the high efficiency channel of a pressure tube super critical water reactor

    International Nuclear Information System (INIS)

    The Pressure Tube (PT) Supercritical Water Reactor (SCWR) is based on a light water coolant operating at pressures above the thermodynamic critical pressure; a separate low temperature and low pressure moderator. The coolant density changes by an order of magnitude depending on its local enthalpy in the porous ceramic insulator tube. This causes significant changes in the neutron transport characteristics, axially and radially, in the fuel channel. This work performs lattice physics calculations for a 78-element Pu-Th fuel at zero burnup and examines the effect of assumptions related to coolant density in the radial direction of a HEC, using the neutron transport code WIMS-AECL. (author)

  10. Investigation of accelerator's characteristics used for an energy amplifier

    International Nuclear Information System (INIS)

    The sub-critical reactor of the energy amplifier is a kind of swimming pool reactors, operates by fast neutron and uses ThO2 + 0.1U233 as fuel. The long cylindrical fuel bars are arranged in constant steps according to a hexagonal configuration. The two fuel assemblies are with the 12.43 mm and 11.38 mm fuel bar steps. The cell group parameters and effective neutron multiplication coefficient of the energy amplifier including two neutron energy groups are defined by the WIMS-D homogenization code. Their calculating results are presented. (NHA)

  11. Interface Screenings

    DEFF Research Database (Denmark)

    Thomsen, Bodil Marie Stavning

    2015-01-01

    In Wim Wenders' film Until the End of the World (1991), three different diagrams for the visual integration of bodies are presented: 1) GPS tracking and mapping in a landscape, 2) video recordings layered with the memory perception of these recordings, and 3) data-created images from dreams...... and memories. From a transvisual perspective, the question is whether or not these (by now realized) diagrammatic modes involving the body in ubiquitous global media can be analysed in terms of the affects and events created in concrete interfaces. The examples used are filmic as felt sensations...

  12. Neutronic parameters calculations of a CANDU reactor

    International Nuclear Information System (INIS)

    Neutronic calculations that reproduce in a simplified way some aspects of a CANDU reactor design were performed. Starting from some prefixed reactor parameters, cylindrical and uniform iron adjuster rods were designed. An appropriate refueling scheme was established, defininig in a 2 zones model their dimensions and exit burnups. The calculations have been done using the codes WIMS-D4 (cell), SNOD (reactivity device simulations) and PUMA (reactor). Comparing with similar calculations done with codes and models usually employed for CANDU design, it is concluded that the models and methods used are appropriate. (Author)

  13. Error Reduction for Weigh-In-Motion

    Energy Technology Data Exchange (ETDEWEB)

    Hively, Lee M [ORNL; Abercrombie, Robert K [ORNL; Scudiere, Matthew B [ORNL; Sheldon, Frederick T [ORNL

    2009-01-01

    Federal and State agencies need certifiable vehicle weights for various applications, such as highway inspections, border security, check points, and port entries. ORNL weigh-in-motion (WIM) technology was previously unable to provide certifiable weights, due to natural oscillations, such as vehicle bouncing and rocking. Recent ORNL work demonstrated a novel filter to remove these oscillations. This work shows further filtering improvements to enable certifiable weight measurements (error < 0.1%) for a higher traffic volume with less effort (elimination of redundant weighing).

  14. Time Evolution of Selected Actinides in TRIGA MARK-II Fuel

    International Nuclear Information System (INIS)

    Study is made on the evolution of several actinides capable of undergoing fission or breeding available on the Malaysian Nuclear Agency (MNA) TRIGA MARK-II fuel. Population distribution of burned fuel in the MNA reactor is determined with a model developed using WIMS. This model simulates fuel conditions in the hottest position in the reactor, thus the location where most of the burn up occurs. Theoretical basis of these nuclide time evolution are explored and compared with the population obtained from our models. Good agreements are found for the theoretical time evolution and the population of Uranium-235, Uranium-236, Uranium-238 and Plutonium-239. (author)

  15. A WEIGHTED ITERATIVE METHOD FOR ROBUST SELF-CALIBRATION

    Institute of Scientific and Technical Information of China (English)

    Liu Shigang; Wu Chengke; Tang Li; Jia Jing

    2006-01-01

    A robust self-calibration method is presented, which can efficiently discard the outliers based on a Weighted Iteration Method (WIM). The method is an iterative process in which the projective reconstruction is obtained based on the weights of all the points, whereas the weights are defined in inverse proportion to the reciprocal of the re-projective errors. The weights of outliers trend to zero after several iterations, and the accurate projective reconstruction is determined. The location of the absolute conic and the camera intrinsic parameters are obtained after the projective reconstruction. The theory and experiments with both simulate and real data demonstrate that the proposed method is very efficient and robust.

  16. Calculation of fundamental parameters for the dynamical study of TRIGA-3-Salazar reactor (Mixed reactor core)

    International Nuclear Information System (INIS)

    Kinetic parameters for dynamic study of two different configurations, 8 and 9, both with standard fuel, 20% enrichment and Flip (Fuel Life Improvement Program with 70% enrichment) fuel, for TRIGA Mark-III reactor from Mexico Nuclear Center, are obtained. A calculation method using both WIMS-D4 and DTF-IV and DAC1 was established, to decide which of those two configurations has the best safety and operational conditions. Validation of this methodology is done by calculate those parameters for a reactor core with new standard fuel. Configuration 9 is recommended to be use. (Author)

  17. Static Scale Conversion Weigh-In-Motion System; FINAL

    International Nuclear Information System (INIS)

    In support of the Air Mobility Battle Lab (AMBL), the Defense Advanced Research Projects Agency (DARPA) Advanced Logistics Program and the U. S. Transportation Command (USTRANSCOM), the ultimate objective of this project is to develop and demonstrate a full-scale prototype static scale conversion weigh-in-motion/Profilometry (SSC-WIM/P) system to measure and record dimensional and weight information for the Department of Defense (DoD) equipment and cargo. The Oak Ridge National Laboratory (ORNL), along with the AMBL, and Intercomp, Inc. have developed a long-range plan for developing a dual-use system which can be used as a standard static scale or an accurate weigh-in-motion system. AMBL will work to define requirements for additional activities with U.S. Transportation Command, Air Mobility Command, and the Joint Warfighting Battle Lab for both the SSC-WIM/P and a portable Weigh-in-Motion System for individual units. The funding goal is to fully fund the development of two prototype test articles (a SSC-WIM kit, and a laser profilometer) and have at least one fully operational system by the early 2002 timeframe. The objective of this portion of the project will be to develop a SSC-WIM system, which at a later date can be fully integrated with a profilometry system; to fully characterize DOD wheeled vehicles and cargo (individual axle weights, total vehicle weight, center of balance, height, width and length measurements). The program will be completed in phases with the initial AMBL/DARPA funding being used to initiate the efforts while AMBL/USTC obtains funding to complete the first generation system effort. At the completion of an initial effort, the interface hardware and the data acquisition/analysis hardware will be developed, fabricated, and system principles and basic functionality evaluated, tested, and demonstrated. Additional funding, when made available, will allow the successful completion of a first generation prototype system. This effort will be

  18. Performance Evaluation of Downlink WiMAX System in Vicinity of UWB System

    OpenAIRE

    Maan A. S. Al-Adwany

    2011-01-01

    In this paper, we evaluate the performance of WiMAX downlink system in vicinity of UWB system. The study is achieved via simulating a scenario of an office building which utilizes from both WiMAX and UWB appliances. From the simulation results, we found that WiMAX system is largely affected by the UWB interference. However, in order to overcome the interference problem and achieve reasonable BER (Bit Error Rate) of 10-4, we found that it is very necessary to raise the WiM...

  19. Hanford inventory program user's manual

    International Nuclear Information System (INIS)

    Provides users with instructions and information about accessing and operating the Hanford Inventory Program (HIP) system. The Hanford Inventory Program is an integrated control system that provides a single source for the management and control of equipment, parts, and material warehoused by Westinghouse Hanford Company in various site-wide locations. The inventory is comprised of spare parts and equipment, shop stock, special tools, essential materials, and convenience storage items. The HIP replaced the following systems; ACA, ASP, PICS, FSP, WSR, STP, and RBO. In addition, HIP manages the catalog maintenance function for the General Supplies inventory stocked in the 1164 building and managed by WIMS

  20. Pressure tube creep impact on the physics parameters for CANDU-6 reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kim, W. Y.; Min, B. J. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Kam, S. C.; Kim, M. E. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2004-07-01

    The lattice cell calculations are performed to assess the sensitivity of the reactor physics parameters to pressure tube creep resulting from radiation aging. The physics parameters of the lattice cell are calculated by using WIMSD-5B code, WIMS- AECL code, and MCNP code. The reference model(normal state) and two perturbed models accounting for the pressure tube creep are developed on the basis of CANDU-6 lattice cell. The 2.5% and 5% values of pressure tube diameter creep are considered. Also, The effects of the analyzed lattice parameters which are the coolant void reactivity, the fuel fission density and the atom density of Pu isotopes on the lattice.

  1. Validation of finite element code DELFIN by means of the zero power experiences at the nuclear power plant of Atucha I

    International Nuclear Information System (INIS)

    Code DELFIN, developed in CNEA, treats the spatial discretization using heterogeneous finite elements, allowing a correct treatment of the continuity of fluxes and currents among elements and a more realistic representation of the hexagonal lattice of the reactor. It can be used for fuel management calculation, Xenon oscillation and spatial kinetics. Using the HUEMUL code for cell calculation (which uses a generalized two dimensional collision probability theory and has the WIMS library incorporated in a data base), the zero power experiences performed in 1974 were calculated. (author). 8 refs., 9 figs., 3 tabs

  2. An Analysis of the Nuclear Data Libraries' Impact on the Criticality Computations Performed using Monte Carlo Codes

    International Nuclear Information System (INIS)

    The major aim of this work is a sensitivity analysis related to the influence of the different nuclear data libraries on the k-infinity values and on the void coefficient estimations performed for various CANDU fuel projects, and on the simulations related to the replacement of the original stainless steel adjuster rods by cobalt assemblies in the CANDU reactor core. The computations are performed using the Monte Carlo transport codes MCNP5 and MONTEBURNS 1.0 for the actual, detailed geometry and material composition of the fuel bundles and reactivity devices. Some comparisons with deterministic and probabilistic codes involving the WIMS library are also presented

  3. The first acceleration to 300 GeV

    CERN Multimedia

    1976-01-01

    After the acceleration to 80 GeV in May the 200 GeV energy was attained on June 4, followed by a successful attempt to reach 300 GeV and then 400 GeV by the Council session on June 17. Here at the desk (centre) Boris Milman and Bas de Raad, (right) Pat Mills and a machine operator. Then standing on the back Jacques Althaber, Simon Van der Meer, Hans-Peter Kindermann, Raymond Rausch, John Adams, Klaus Batzner, and still back Antonio Millich, Jim Allaby, Wim Middelkoop, Bo Angerth, Hans Horisberger.

  4. L’immaginario della crisi nello sguardo dell’angelo. Attraversando Il cielo sopra Berlino

    Directory of Open Access Journals (Sweden)

    Maria Felicia Schepis

    2015-12-01

    Full Text Available Periodical crises may affect both the existential and collective sphere every time something new disrupt habitual certainties, announcing a change. If crisis indicates a fracture, the raising of a “wall” may represent its consequence, as an attempt to stem the rift and to stop the ongoing changes. This is what we are going to deepen in this work by walking the cinematographic imaginary of Wim Wenders, Der Himmel über Berlin (1987. By crossing some themes of Benjamin, the angel’s look will assume the amazement of a child to indicate the passage beyond the Wall: beyond the crisis.

  5. MDA开发过程——《解析MDA》精彩选读

    Institute of Scientific and Technical Information of China (English)

    鲍志云

    2003-01-01

    MDA是一种新的开发方法。来自MDA标准委员会(属于OMG)的三位成员Jos Warmer、Anneke K1eppe和Wim Bast撰写了《解析MDA))一书。该书深入剖析了MDA的优越性和实现方法。开发人员也将通过《解析MDA))掌握定义MDA工具的必备知识。

  6. A Study of the Warm Ionized Medium Throughout the Sagittarius-Carina Arm

    CERN Document Server

    Krishnarao, Dhanesh; Benjamin, Robert A

    2016-01-01

    We present velocity-channel maps and analysis of the warm ionized medium (WIM) throughout the Sagittarius- Carina arm at Galactic longitudes 20 1000 pc along the far Carina arm. Physical conditions of the ionized gas are analyzed using the [S II]/H-alpha line ratio, which more closely traces H-alpha intensity than height above the plane, z, suggesting a stronger relationship with the in-situ electron density. We interpret this result as further evidence for the majority of the observed diffuse emission originating from in-situ ionized gas as opposed to scattered light from classical H II regions in the plane.

  7. Methods and Model Development for Coupled RELAP5/PARCS Analysis of the Atucha-II Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Andrew M. Ward

    2011-01-01

    Full Text Available In order to analyze the steady state and transient behavior of CNA-II, several tasks were required. Methods and models were developed in several areas. HELIOS lattice models were developed and benchmarked against WIMS/MCNP5 results generated by NA-SA. Cross-sections for the coupled RELAP5/PARCS calculation were extracted from HELIOS within the GenPMAXS framework. The validation of both HELIOS and PARCS was performed primarily by comparisons to WIMS/PUMA and MCNP for idealized models. Special methods were developed to model the control rods and boron injection systems of CNA-II. The insertion of the rods is oblique, and a special routine was added to PARCS to treat this effect. CFD results combined with specialized mapping routines were used to model the boron injection system. In all cases there was good agreement in the results which provided confidence in the neutronics methods and modeling. A coupled code benchmark between U of M and U of Pisa is ongoing and results are still preliminary. Under a LOCA transient, the best estimate behavior of the core appears to be acceptable.

  8. TRIGA spent-fuel storage criticality analysis

    International Nuclear Information System (INIS)

    A criticality safety analysis of a pool-type storage for spent TRIGA Mark II reactor fuel is presented. Two independent computer codes are applied: the MCNP Monte Carlo code and the WIMS lattice cell code. Two types of fuel elements are considered: standard fuel elements with 12 wt% uranium concentration and FLIP fuel elements. A parametric study of spent-fuel storage lattice pitch, fuel element burnup, and water density is presented. Normal conditions and postulated accident conditions are analyzed. A strong dependence of the multiplication factor on the distance between the fuel elements and on the effective water density is observed. A multiplication factor 6.5 cm, regardless of the fuel element type and burnup. At shorter distances, the subcriticality can be ensured only by adding absorbers to the array of fuel rods even if the fuel rods were burned to ∼20% burnup. The results of both codes agree well for normal conditions. The results show that WIMS may be used as a complement to the Monte Carlo code in some parts of the criticality analysis

  9. Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis

    Directory of Open Access Journals (Sweden)

    Seung Yeol Yoo

    2015-01-01

    Full Text Available The current neutronics design methodology of CANDU-PHWRs based on the two-step calculations requires determining not only homogenized two-group constants for ordinary fuel bundle lattice cells by the WIMS-AECL lattice cell code but also incremental two-group constants arising from the penetration of control devices into the fuel bundle cells by a supercell analysis code like MULTICELL or DRAGON. As an alternative way to generate the two-group constants necessary for the CANDU-PHWR core analysis, this paper proposes utilizing a B1 theory augmented Monte Carlo (MC few-group constant generation method (B1 MC method which has been devised for the PWR fuel assembly analysis method. To examine the applicability of the B1 MC method for the CANDU 6 core analysis, the fuel bundle cell and supercell calculations are performed using it to obtain the two-group constants. By showing that the two-group constants from the B1 MC method agree well with those from WIMS-AECL and that core neutronics calculations for hypothetical CANDU 6 cores by a deterministic diffusion theory code SCAN with B1 MC method generated two-group constants also agree well with whole core MC analyses, it is concluded that the B1 MC method is well qualified for both fuel bundle cell and supercell analyses.

  10. Analysis of axle and vehicle load properties through Bayesian Networks based on Weigh-in-Motion data

    International Nuclear Information System (INIS)

    Weigh-in-Motion (WIM) systems are used, among other applications, in pavement and bridge reliability. The system measures quantities such as individual axle load, vehicular loads, vehicle speed, vehicle length and number of axles. Because of the nature of traffic configuration, the quantities measured are evidently regarded as random variables. The dependence structure of the data of such complex systems as the traffic systems is also very complex. It is desirable to be able to represent the complex multidimensional-distribution with models where the dependence may be explained in a clear way and different locations where the system operates may be treated simultaneously. Bayesian Networks (BNs) are models that comply with the characteristics listed above. In this paper we discuss BN models and results concerning their ability to adequately represent the data. The paper places attention on the construction and use of the models. We discuss applications of the proposed BNs in reliability analysis. In particular we show how the proposed BNs may be used for computing design values for individual axles, vehicle weight and maximum bending moments of bridges in certain time intervals. These estimates have been used to advise authorities with respect to bridge reliability. Directions as to how the model may be extended to include locations where the WIM system does not operate are given whenever possible. These ideas benefit from structured expert judgment techniques previously used to quantify Hybrid Bayesian Networks (HBNs) with success

  11. Evaluation of ternary mobile phases for the analysis of carbonyl compound derivatives using high-performance liquid chromatography.

    Science.gov (United States)

    Ho, Duy Xuan; Kim, Ki-Hyun

    2011-01-01

    In this study, the feasibility of ternary mobile phases was examined in a high-performance liquid chromatography (HPLC)-based analysis of carbonyl compounds (CCs). To test the performance of different ternary phases, the liquid phase standards containing a 15 aldehyde/ketone-DNPH(o) mix were analyzed through a series of five-point calibration experiments. For this comparison, three types of ternary mobile phases were prepared initially by mixing water (W) with two of the following three organic solvents: isopropanol (I), methanol (M), and tetrahydrofuran (T). The resulting three types of ternary phases (named as WIM, WTM, and WIT) were tested and evaluated in relation to the water content or in terms of methanol-to-water ratio (M/W). The results derived by the three ternary phases revealed that the optimal resolution was attained near maximum water content, while those of WIT consistently suffered from poor resolution problems. The relative performances of WIM and WTM phases, if assessed by three key operating parameters (sensitivity, retention time, and resolution), were found to be reliable for most selected CCs with the decreasing M/W ratio. PMID:21218260

  12. Evaluation of Ternary Mobile Phases for the Analysis of Carbonyl Compound Derivatives Using High-Performance Liquid Chromatography

    Directory of Open Access Journals (Sweden)

    Duy Xuan Ho

    2011-01-01

    Full Text Available In this study, the feasibility of ternary mobile phases was examined in a high-performance liquid chromatography (HPLC-based analysis of carbonyl compounds (CCs. To test the performance of different ternary phases, the liquid phase standards containing a 15 aldehyde/ketone-DNPH(o mix were analyzed through a series of five-point calibration experiments. For this comparison, three types of ternary mobile phases were prepared initially by mixing water (W with two of the following three organic solvents: isopropanol (I, methanol (M, and tetrahydrofuran (T. The resulting three types of ternary phases (named as WIM, WTM, and WIT were tested and evaluated in relation to the water content or in terms of methanol-to-water ratio (M/W. The results derived by the three ternary phases revealed that the optimal resolution was attained near maximum water content, while those of WIT consistently suffered from poor resolution problems. The relative performances of WIM and WTM phases, if assessed by three key operating parameters (sensitivity, retention time, and resolution, were found to be reliable for most selected CCs with the decreasing M/W ratio.

  13. TRITON/NEWT calculation of the Corail assembly for plutonium recycling in PWR

    International Nuclear Information System (INIS)

    The TRITON/NEWT code sequence of SCALE 5.1 and associated cross section libraries are benchmarked in this work against WIMS8 and APOLLO2 for the plutonium-bearing CORAIL assembly. The CORAIL assembly is designed for the multi-recycling of plutonium in PWR, using an heterogeneous configuration of UO2 and MOX fuel pins. The heterogeneity makes the modeling of this assembly type particularly challenging. TRITON/NEWT shows a satisfactory agreement on the evolution of k∞ with burnup, on the assembly pin-wise power peaking and on the burnup dependent concentration of most of the minor actinides. An exception is found to be the burnup-dependent evolution of 242mAm, which shows discrepancies of up to 60%. The reason was traced to the branching ratio of the (n, γ) reaction Of 241Am. Upon modification of the probability of formation of 242Am from the default 16.2% to 10% (used by WIMS8) in the ORIGEN-S binary libraries, the large discrepancy in the concentration of 242mAm disappeared. It is also found that by slightly varying the group structure of the standard 44-UOX library of SCALE 5.1 it is possible to get closer agreement with the results obtained using the standard 238-group library. (authors)

  14. WIMCIT: An in-house development integrated code for neutron analysis in MTR reactors with mixed core

    International Nuclear Information System (INIS)

    So far, Peruvian nuclear research reactors RP-10 and RP-0 have been operating only with uranium oxide fuel elements (U3O8+Al). In the future RP-10 reactor will operate with mixed cores (U3Si2+Al, U3O8+Al). For this reason the calculus capacity has to be increased in order to be able to handle the new fuel management. Since preparation of nuclear libraries for diffusion calculation requires a significant amount of computational and human resources a new tool that processes libraries generation and diffusion calculations is necessary. For this reason the WIMCIT code was developed. The main feature of this code is to integrate WIMS and CITATION codes. The user can generate nuclear libraries in different groups (from 1 to 18) in the range of 0 - 10MeV automatically. They are generated from the WIMS output and then interpolated to create an input to CITATION according to the user specifications. Both the flux and power profiles can be calculated in different transverse sections. The output form the diffusion calculations is processed and different physical parameters of the reactor are displayed to the user. Others WIMCIT capabilities are, flux calculation, power profiles, burn-up average by element, control rod interaction in the core and fuel management in mixed core. The WIMCIT code has been validated on the experimental data from the RP-10 fresh core to the current core (Number 24). (author)

  15. Study of boron dilution phenomenon in the core and fuel assemblies of Bushehr VVERr-1000 reactor in normal operating conditions

    International Nuclear Information System (INIS)

    The spatial temperature distributions in fuel and coolant, results in appearing local changes in those elements densities in the reactor core, and also due to the complete solubility of boric acid in the coolant, there will be a direct correlation between the changes in the boron concentration and the coolant density. Because of the gradual reduction of boron concentration, first a local positive reactivity will be inserted into the core which will cause slight thermo-neutronic fluctuations in the reactor core. Of course, the trend of this process in the case of excessive reduction of the density of the coolant and evaporation of water (accident scenarios) will be reversed and subsequently the negative reactivity will be given to the system. With regard to the importance of this phenomenon, the spatial changes of boron concentration in the core and fuel assemblies of Bushehr VVER-1000 reactor have been examined. In line with this, by designing a complete thermo-neutronic cycle and by using CITATION, WIMS D-5 and COBRAN-EN codes, coolant temperature distribution and boron concentration will be calculated through this procedure, which first by using the output results of WIMS and CITATION codes, the thermal power of each fuel assembly will be calculated and finally, by linking these data to COBRA-EN code and using core and sub-channel analysis methods, the three-dimensional (3D) calculations of boron dilution will be obtained in the core as well as the fuel assemblies of the reactor. (authors)

  16. Effect of mesh grid size on the accuracy of deterministic VVER-1000 core calculations

    International Nuclear Information System (INIS)

    Research highlights: → Accuracy of changing mesh grid size in deterministic core calculations was investigated. → WIMS and CITATION codes were used in the investigation. → The best results belong to higher numbers of mesh points in radial and axial directions of the core. - Abstract: Numerical solutions based on finite-difference method require the domain in the problem to be divided into a number of nodes in the form of triangles, rectangular, and so on. To apply the finite-difference method in reactor physics for solving the diffusion equation with satisfactory accuracy, the distance between adjacent mesh-points should be small in comparison with a neutron mean free path. In this regard the effect of number of mesh points on the accuracy and computation time have been investigated using the VVER-1000 reactor of Bushehr NPP as an example, and utilizing WIMS and CITATION codes. The best results obtained in this study belong to meshing models with higher numbers of mesh-points in both radial and axial directions of the reactor core.

  17. Design of an implantable power supply for an intraocular sensor, using POWER (power optimization for wireless energy requirements)

    Energy Technology Data Exchange (ETDEWEB)

    Albano, F. [Department of Material Science Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Chung, M.D. [Department of Mechanical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Blaauw, D.; Sylvester, D.M. [Department of Electrical Engineering and Computer Science, University of Michigan, Ann Arbor, MI 48109 (United States); Wise, K.D. [Department of Biomedical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Electrical Engineering and Computer Science, University of Michigan, Ann Arbor, MI 48109 (United States); Sastry, A.M. [Department of Biomedical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Material Science Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Mechanical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States)

    2007-06-30

    The reduction in size and power usage of MEMS (microelectromechanical systems) devices has enabled development of fully implantable medical devices [K.D. Wise, IEEE Eng. Med. Biol. Magaz. 24(5) (2005) 22-29], though major obstacles remain in developing devices of very small scale (<1 mm) [T. Simunic, L. Benini, G. De Micheli, IEEE Trans. Very Large Scale Integr. (VLSI) Syst. 9 (2001) 15-28]. One of the most challenging applications; an intraocular sensor (IOS) developed by the Wireless Integrated Micro-Systems-Engineering Research Center (WIMS-ERC) at The University of Michigan; is the subject of the present study. Our specific objectives are fourfold: (1) to model the power usage of an intraocular sensor (IOS); (2) to develop a methodology for optimization of Hybrid Implantable Power Systems (HIPS); (3) to apply the selection tool to identify candidate power systems; and (4) to establish a methodology to fabricate and test the performance of an optimized power supply. In the present study we fabricated and tested three different cells. For one of these, 10 complete discharge and recharge cycles were successfully obtained. The experimental capacity was 7.70 mAh (15% of theoretical) for a discharge rate of C/5. As part of future work, a microbattery will be built for the WIMS-ERC IOS and tested in a fully integrated testbed. (author)

  18. A fully integrated microbattery for an implantable microelectromechanical system

    Energy Technology Data Exchange (ETDEWEB)

    Albano, F. [Department of Material Science Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Mechanical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Lin, Y.S.; Blaauw, D.; Sylvester, D.M. [Department of Electrical Engineering and Computer Science, University of Michigan, Ann Arbor, MI 48109 (United States); Wise, K.D. [Department of Electrical Engineering and Computer Science, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Biomedical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Sastry, A.M. [Department of Material Science Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Biomedical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States); Department of Mechanical Engineering, University of Michigan, Ann Arbor, MI 48109 (United States)

    2008-12-01

    The Wireless Integrated Microsystems Engineering Research Center's Intraocular Sensor (WIMS-ERC IOS) was studied as a model system for an integrated, autonomous implantable device. In the present study, we had four objectives: (1) select and designing an optimized power supply for the WIMS-IOS; (2) develop a fabrication technique allowing small scale, low-cost, and integrable fabrication for CMOS systems, and experimentally demonstrate a microscopic power source; (3) map capacity and lifetime of several fabricated microbatteries; (4) determine the effects of miniaturization on capacity, lifetime and device architecture. Physical vapor deposition (PVD) was used to deposit thin layers ({<=}1 {mu}m) of metal sequentially onto glass substrates (SiO{sub 2}, as used in the device). To map the influence of size over cell capacity and cycle life, we fabricated and tested five stand-alone cells using a Solartron {sup registered} 1470E battery tester and a Maccor {sup registered} 4000 series tester. A sixth battery was fabricated to investigate the effects of system integration, variable discharge rate and size reduction simultaneously. The highest experimental capacity among the larger cells O(cm{sup 2}) was 100 {mu}Ah, achieved by IOS-C-1 at 250 {mu}A (1.4 C) discharge. Among O(mm{sup 2}) cells, IOS-M-1 achieved the highest capacity (2.75 {mu}Ah, {proportional_to}76% of theoretical) at 2.5 {mu}A discharge (0.7 C rate). (author)

  19. Design of an implantable power supply for an intraocular sensor, using POWER (power optimization for wireless energy requirements)

    Science.gov (United States)

    Albano, F.; Chung, M. D.; Blaauw, D.; Sylvester, D. M.; Wise, K. D.; Sastry, A. M.

    The reduction in size and power usage of MEMS (microelectromechanical systems) devices has enabled development of fully implantable medical devices [K.D. Wise, IEEE Eng. Med. Biol. Magaz. 24(5) (2005) 22-29], though major obstacles remain in developing devices of very small scale (applications; an intraocular sensor (IOS) developed by the Wireless Integrated Micro-Systems-Engineering Research Center (WIMS-ERC) at The University of Michigan; is the subject of the present study. Our specific objectives are fourfold: (1) to model the power usage of an intraocular sensor (IOS); (2) to develop a methodology for optimization of Hybrid Implantable Power Systems (HIPS); (3) to apply the selection tool to identify candidate power systems; and (4) to establish a methodology to fabricate and test the performance of an optimized power supply. In the present study we fabricated and tested three different cells. For one of these, 10 complete discharge and recharge cycles were successfully obtained. The experimental capacity was 7.70 mAh (15% of theoretical) for a discharge rate of C/5. As part of future work, a microbattery will be built for the WIMS-ERC IOS and tested in a fully integrated testbed.

  20. Fragility Analysis Methodology for Degraded Structures and Passive Components in Nuclear Power Plants - Illustrated using a Condensate Storage Tank

    Energy Technology Data Exchange (ETDEWEB)

    Nie, J.; Braverman, J.; Hofmayer, C.; Choun, Y.; Kim, M.; Choi, I.

    2010-06-30

    The Korea Atomic Energy Research Institute (KAERI) is conducting a five-year research project to develop a realistic seismic risk evaluation system which includes the consideration of aging of structures and components in nuclear power plants (NPPs). The KAERI research project includes three specific areas that are essential to seismic probabilistic risk assessment (PRA): (1) probabilistic seismic hazard analysis, (2) seismic fragility analysis including the effects of aging, and (3) a plant seismic risk analysis. Since 2007, Brookhaven National Laboratory (BNL) has entered into a collaboration agreement with KAERI to support its development of seismic capability evaluation technology for degraded structures and components. The collaborative research effort is intended to continue over a five year period. The goal of this collaboration endeavor is to assist KAERI to develop seismic fragility analysis methods that consider the potential effects of age-related degradation of structures, systems, and components (SSCs). The research results of this multi-year collaboration will be utilized as input to seismic PRAs. In the Year 1 scope of work, BNL collected and reviewed degradation occurrences in US NPPs and identified important aging characteristics needed for the seismic capability evaluations. This information is presented in the Annual Report for the Year 1 Task, identified as BNL Report-81741-2008 and also designated as KAERI/RR-2931/2008. The report presents results of the statistical and trending analysis of this data and compares the results to prior aging studies. In addition, the report provides a description of U.S. current regulatory requirements, regulatory guidance documents, generic communications, industry standards and guidance, and past research related to aging degradation of SSCs. In the Year 2 scope of work, BNL carried out a research effort to identify and assess degradation models for the long-term behavior of dominant materials that are

  1. The Conflux Fuel bundle: An Economic and Pragmatic Route to the use of Advanced Fuel Cycles in CANDU Reactors

    International Nuclear Information System (INIS)

    The CANFLEX1 bundle is being developed jointly by AECL and KAERI as a vehicle for introducing the use of enrichment and advanced fuel cycles in CANDU2 reactors. The bundle design uses smaller diameter fuel elements in the outer ring of a 43-element bundle to reduce the maximum element ratings in a CANDU fuel bundle by 20% compared to the 37-element bundle currently in use. This facilitates burnups of greater than 21,000 MW d/TAU to optimize the economic benefit available from the use of enrichment and advanced fuel cycles. A combination of this lower fuel rating, plus development work underway at Aecl to enhance the thermalhydraulic characteristics of the bundle (including both CHF3 and bundle. This provides extra flexibility in the fuel management procedures required for fuel bundles with higher fissile contents. The different bundle geometry requires flow tests to demonstrate acceptable vibration and fretting behavior of the Conflux bundle. A program to undertake the necessary range of flow tests has started at KAERI, involving the fabrication of the required bundles, and setting up for the actual tests. A program to study the fuel management requirements for slightly enriched (0.9 wt % 235 in total U) Conflux fuel has been undertaken by both Aecl and KAERI staff, and further work has started for higher enrichments. Irradiation testing of the Conflux bundle started in the NUR reactor in 1989, and a second irradiation test is due to start shortly. This paper describes the program, and reviews the status of key parts of the program

  2. The development of advanced robotics for the nuclear industry -The development of advanced robotic technology-

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Lee, Yong Bum; Park, Soon Yong; Cho, Jae Wan; Lee, Nam Hoh; Kim, Woong Kee; Moon, Byung Soo; Kim, Seung Hoh; Kim, Chang Heui; Kim, Byung Soo; Hwang, Suk Yong; Lee, Yung Kwang; Moon, Je Sun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    Main activity in this year is to develop both remote handling system and telepresence techniques, which can be used for people involved in extremely hazardous working area to alleviate their burden. In the robot vision technology part, KAERI-PSM system, stereo imaging camera module, stereo BOOM/MOLLY unit, and stereo HMD unit are developed. Also, autostereo TV system which falls under the category of next generation stereo imaging technology has been studied. The performance of KAERI-PSM system for remote handling task is evaluated and compared with other stereo imaging systems as well as general TV imaging system. The result shows that KAERI-PSM system is superior to the other stereo imaging systems about remote operation speedup and accuracy. The automatic recognition algorithm of instrument panel is studied and passive visual target tracking system is developed. The 5 DOF camera serving unit has been designed and fabricated. It is designed to function like human`s eye. In the sensing and intelligent control research part, thermal image database system for thermal image analysis is developed and remote temperature monitoring technique using fiber optics is investigated. And also, two dimensional radioactivity sensor head for radiation profile monitoring system is designed. In the part of intelligent robotics, mobile robot is fabricated and its autonomous navigation using fuzzy control logic is studied. These remote handling and telepresence techniques developed in this project can be applied to nozzle-dam installation/removal robot system, reactor inspection unit, underwater nuclear pellet inspection and pipe abnormality inspection. And these developed remote handling and telepresence techniques will be applied in general industry, medical science, and military as well as nuclear facilities. 203 figs, 12 tabs, 72 refs. (Author).

  3. Enhancement of weld failure and tube ejection model in PENTAP program

    International Nuclear Information System (INIS)

    The reactor vessel pressure, the debris mass, the debris temperature, and the component of material can have an effect on the penetration tube failure modes. Furthermore, these parameters are interrelated. There are some representative severe accident codes such as MELCOR, MAAP, and PENTAP program. MELCOR decides on a penetration tube failure by its failure temperature such as 1273K simply. MAAP considers all penetration failure modes and has the most advanced model for a penetration tube failure model. However, the validation work against the experimental data is very limited. PENTAP program which evaluates the possible penetration tube failure modes such as creep failure, weld failure, tube ejection, and a long term tube failure under given accident condition was developed by KAERI. The experiment for the tube ejection is being performed by KAERI. The temperature distribution and the ablation rate of both weld and lower vessel wall can be obtained through the experiment. This paper includes the updated calculation steps for the weld failure and the tube ejection modes of the PENTAP program to apply the experimental results. PENTAP program can evaluate the possible penetration tube failure modes. It still requires a large amount of efforts to increase the prediction of failure modes. Some calculation steps are necessary for applying the experimental and the numerical data in the PENTAP program. In this study, new calculation steps are added to PENTAP program to enhance the weld failure and tube ejection models using KAERI's experimental data which are the ablation rate and temperature distribution of weld and lower vessel wall

  4. Preliminary calibration of the ACP safeguards neutron counter

    Science.gov (United States)

    Lee, T. H.; Kim, H. D.; Yoon, J. S.; Lee, S. Y.; Swinhoe, M.; Menlove, H. O.

    2007-10-01

    The Advanced Spent Fuel Conditioning Process (ACP), a kind of pyroprocess, has been developed at the Korea Atomic Energy Research Institute (KAERI). Since there is no IAEA safeguards criteria for this process, KAERI has developed a neutron coincidence counter to make it possible to perform a material control and accounting (MC&A) for its ACP materials for the purpose of a transparency in the peaceful uses of nuclear materials at KAERI. The test results of the ACP Safeguards Neutron Counter (ASNC) show a satisfactory performance for the Doubles count measurement with a low measurement error for its cylindrical sample cavity. The neutron detection efficiency is about 21% with an error of ±1.32% along the axial direction of the cavity. Using two 252Cf neutron sources, we obtained various parameters for the Singles and Doubles rates for the ASNC. The Singles, Doubles, and Triples rates for a 252Cf point source were obtained by using the MCNPX code and the results for the ft8 cap multiplicity tally option with the values of ɛ, fd, and ft measured with a strong source most closely match the measurement results to within a 1% error. A preliminary calibration curve for the ASNC was generated by using the point model equation relationship between 244Cm and 252Cf and the calibration coefficient for the non-multiplying sample is 2.78×10 5 (Doubles counts/s/g 244Cm). The preliminary calibration curves for the ACP samples were also obtained by using an MCNPX simulation. A neutron multiplication influence on an increase of the Doubles rate for a metal ingot and UO2 powder is clearly observed. These calibration curves will be modified and complemented, when hot calibration samples become available. To verify the validity of this calibration curve, a measurement of spent fuel standards for a known 244Cm mass will be performed in the near future.

  5. Thoughts on Documentation of Atomic Power Technology

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Jeong Hoon; Lee, Hee Won; Song, Ki Chan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Korean Atomic Energy Research Institute (KAERI) has accumulated a number of technology development and research outcomes, including its representative achievements such as atomic energy technology independence and the first export of atomic energy system, since it was established in 1959. With its long history of over 50 years, KAERI has produced a large amount of information and explicit knowledge such as experiment data, database, design data, report, instructions, and operation data at each stage of its research and development process as it has performed various researches since its establishment. Also, a lot of tacit knowledge has been produced both knowingly and not unknowingly based on the experience of researchers who have participated in many projects. However, in the research environment in Korea where they focus overly on the output, tacit knowledge has not been managed properly compared to explicit knowledge. This tacit knowledge is as an important asset as explicit knowledge for an effective research and development. Moreover, as the first generation of atomic energy independence and research manpower retire, their accumulated experience and knowledge are in danger of disappearing. Therefore, in this study, we sought how to take a whole view and to document atomic energy technology researched and developed by KAERI, from the background to achievement of each field of the technology. Comprehensive and systematic documentation of atomic energy technology will establish a comprehensive management system of national atomic energy technology record to make a foundation of technical advancement and development of atomic energy technology. Also, it is expected to be used as an important knowledge and information resource of atomic energy knowledge management system

  6. The development of advanced robotics for the nuclear industry -The development of advanced robotic technology-

    International Nuclear Information System (INIS)

    Main activity in this year is to develop both remote handling system and telepresence techniques, which can be used for people involved in extremely hazardous working area to alleviate their burden. In the robot vision technology part, KAERI-PSM system, stereo imaging camera module, stereo BOOM/MOLLY unit, and stereo HMD unit are developed. Also, autostereo TV system which falls under the category of next generation stereo imaging technology has been studied. The performance of KAERI-PSM system for remote handling task is evaluated and compared with other stereo imaging systems as well as general TV imaging system. The result shows that KAERI-PSM system is superior to the other stereo imaging systems about remote operation speedup and accuracy. The automatic recognition algorithm of instrument panel is studied and passive visual target tracking system is developed. The 5 DOF camera serving unit has been designed and fabricated. It is designed to function like human's eye. In the sensing and intelligent control research part, thermal image database system for thermal image analysis is developed and remote temperature monitoring technique using fiber optics is investigated. And also, two dimensional radioactivity sensor head for radiation profile monitoring system is designed. In the part of intelligent robotics, mobile robot is fabricated and its autonomous navigation using fuzzy control logic is studied. These remote handling and telepresence techniques developed in this project can be applied to nozzle-dam installation/removal robot system, reactor inspection unit, underwater nuclear pellet inspection and pipe abnormality inspection. And these developed remote handling and telepresence techniques will be applied in general industry, medical science, and military as well as nuclear facilities. It has been looking for these techniques to expand the working area of human, raise the working efficiencies of remote task to the highest degree, and enhance the industrial

  7. Report of the IAEA regional workshop on the development of a web-portal for ANENT. Working material

    International Nuclear Information System (INIS)

    The Asian Network for Education in Nuclear Technology is a new partnership for cooperation in human resource development and research in nuclear technology as a key strategy for capacity building, nuclear infrastructure development and better use of available information resources. Following the first coordinating committee meeting organized by the IAEA in Kuala Lumpur, Malaysia, the Asian Network for Education in Nuclear Technology (ANENT) was established in February 2004, to promote, manage and preserve nuclear knowledge; to ensure the continued availability of talented and qualified manpower in the nuclear field in the Asian region; and to enhance the quality of the human resources for the sustainability of nuclear technology. Universities, research centers, government agencies and other institutions involved in nuclear education and training in the region, are accepted as participating members of ANENT and international or regional networks as collaborating members. Currently there are 28 participating institutions from 12 countries (Australia, China, India, Indonesia, Malaysia, Mongolia, Pakistan, Republic of Korea, Sri Lanka, Thailand, Philippines and Vietnam) and 6 networks as collaborating members. The present document includes the material presented at the Regional Workshop on 'Development of a Web-Portal for the ANENT', which was organized in cooperation with the Korea Atomic Energy Research Institute (KAERI) and held in the KAERI Nuclear Training Center, Daejeon, Korea, from 21 to 25 March 2005. The workshop participants have concluded that, in general, the ANENT web-portal developed by KAERI is considered as appropriate and user friendly as the infrastructure for promoting, managing and preserving nuclear knowledge and facilitating the ANENT Group Activities

  8. Studies on decommissioning of TRIGA reactors and site restoration technologies in the Republic of Korea

    International Nuclear Information System (INIS)

    Research and development on research reactor decommissioning and environmental restoration has been carried out at KAERI since 1997 to prepare for the decommissioning of KAERI's two TRIGA-type research reactors, which had been shut down since 1995. A 3-D graphic model of the TRIGA research reactor was built using IGRIP. The dismantling process was simulated in the graphic environment to verify the feasibility of individual operations before the execution of the remote dismantling process. An under-water wall-climbing robot, moving by propeller injection, and identifying its coordinates by using a laser sensor, was developed and tested in the TRIGA reactor pool by measuring a radioactive contamination map of the reactor surface. Using MODFLOW and TRIGA site geological data, a computer simulation of the underground migration of residual radionuclides, after the TRIGA reactor decommissioning, was carried out. It was found that the underground migration rate was very slow such that, when radionuclide decay and dilution are considered, the residual radionuclides will not have a significant environmental impact. The soil decontamination R and D, using soil washing, solvent flushing and electro-decontamination technologies, was carried out to determine the best method for decontaminating the soil waste accumulated in KAERI. The decontamination results indicated that, using the soil washing method, more than 80% of the soil wastes could be decontaminated well enough to discharge them to the environment. It was also determined that the control of solution pH and temperature in the soil washing process is important for the reduction of decontamination waste. Further decontamination, using an electro-kinetic decontamination method, was considered necessary for the residual soil waste, which consisted mainly of fine soil particles. (author)

  9. Status and strategy for technical nuclear cooperation between R.O.K. and U.S.A

    International Nuclear Information System (INIS)

    The seven Joint Coordinating Committees between R.O.K. and other countries, including the U.S. are currently in operation. Among these, the most amicable and fruitful one is the R.O.K.-U.S.A. Joint Standing Committee on Nuclear Energy Cooperation(JSCNEC). It is a prerequisite to assess the current status of international joint research which is under way for the effective implementation of international cooperation. It is anticipated that this can be realized by devising continuous follow-up measures based on its assessment and smooth feedback. Various matters encompassing 8 policy matters, 14 technological cooperation matters, 13 nuclear safety cooperation matters and 6 safeguards matters were discussed at the 19th R.O.K.-U.S.A. JSCNEC held June 22-26 in Seoul and Taejon. Among these, matters related to KAERI are the 13 technical cooperation and 2 nuclear safety cooperation concerns. The background and current status of matters in the technical cooperation and nuclear safety cooperation areas as well as our position and discussion direction for each item, with a review of the summary record of the 18th R.O.K.-U.S.A. JSCNEC are presented in this report. At the same time, its publication is meaningful in that after this committee meeting, a status of nuclear technological and safety cooperation between R.O.K. and U.S., which are related to KAERI, has been complied and is clear at a glance. This will be a review of the discussion results from the 19th R.O.K.-U.S.A. JSCNEC. After its publication, we intend to implement a bilateral cooperation with the U.S. more effectively by devising follow-up measures for each issue. This will be achieved through a thorough management of its progress and systematic cooperation in work affairs between personnel of the government and KAERI responsible for bilateral cooperation with the U.S. (author)

  10. Incorporating Level-2 PSA Feature of CONPAS into AIMS-PSA Software

    International Nuclear Information System (INIS)

    CONPAS (CONtainment Performance Analysis System) utilizes a methodology to treat containment phenomena in detail like APET but in simple way. In mid 2000's, KAERI has developed very fast cut set generator FTREX and PC's OS (Operating system) has changed into Windows 95. Thus, KAERI has developed new Level-1 PSA software, called AIMS-PSA (Advanced Information Management System for PSA) to replace KIRAP. Recently, KAERI has been developing an integrated PSA platform, called OCEANS (On-line Consolidator and Evaluator of All mode risk for Nuclear System), for the risk assessment of all power modes and all hazards. CONPAS for Level-2 PSA was developed in 1990's using the Visual Basic 6.0 compiler which is not supported any more. It needs to be updated for the integrated PSA software framework. This paper describes a study to incorporate the features of CONPAS into AIMS-PSA. The basic idea is to follow the approach of CONPAS, but in the integrated way. Various approaches for Level-2 PSA have been used since WASH-1400. APET approach of NUREG-1150 study would be most comprehensive and complex methodology for containment event tree analysis. CONPAS is the Level-2 PSA software to utilize an approach to treat containment phenomena in detail like APET but in simple way. But, new Level-2 PSA software is required to develop more integrated PSA framework. A modified approach of CONPAS is developed and incorporated in AIMS-PSA software that can handle Level-1 and Level-2 PSA in the integrated way (from the viewpoint of event tree and fault tree). AIMS-PSA combines whole Level-2 PSA model to produce a One Top fault tree and to generate cut sets in the same way as Level-1 PSA. Quantification results of Level-2 PSA such as frequency for each STC can be calculated from the minimal cut sets

  11. Incorporating Level-2 PSA Feature of CONPAS into AIMS-PSA Software

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sang Hoon; Lim, Hogon; Ahn, Kwang Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    CONPAS (CONtainment Performance Analysis System) utilizes a methodology to treat containment phenomena in detail like APET but in simple way. In mid 2000's, KAERI has developed very fast cut set generator FTREX and PC's OS (Operating system) has changed into Windows 95. Thus, KAERI has developed new Level-1 PSA software, called AIMS-PSA (Advanced Information Management System for PSA) to replace KIRAP. Recently, KAERI has been developing an integrated PSA platform, called OCEANS (On-line Consolidator and Evaluator of All mode risk for Nuclear System), for the risk assessment of all power modes and all hazards. CONPAS for Level-2 PSA was developed in 1990's using the Visual Basic 6.0 compiler which is not supported any more. It needs to be updated for the integrated PSA software framework. This paper describes a study to incorporate the features of CONPAS into AIMS-PSA. The basic idea is to follow the approach of CONPAS, but in the integrated way. Various approaches for Level-2 PSA have been used since WASH-1400. APET approach of NUREG-1150 study would be most comprehensive and complex methodology for containment event tree analysis. CONPAS is the Level-2 PSA software to utilize an approach to treat containment phenomena in detail like APET but in simple way. But, new Level-2 PSA software is required to develop more integrated PSA framework. A modified approach of CONPAS is developed and incorporated in AIMS-PSA software that can handle Level-1 and Level-2 PSA in the integrated way (from the viewpoint of event tree and fault tree). AIMS-PSA combines whole Level-2 PSA model to produce a One Top fault tree and to generate cut sets in the same way as Level-1 PSA. Quantification results of Level-2 PSA such as frequency for each STC can be calculated from the minimal cut sets.

  12. Enhancement of weld failure and tube ejection model in PENTAP program

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Jaehoon; An, Sang Mo; Ha, Kwang Soon; Kim, Hwan Yeol [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The reactor vessel pressure, the debris mass, the debris temperature, and the component of material can have an effect on the penetration tube failure modes. Furthermore, these parameters are interrelated. There are some representative severe accident codes such as MELCOR, MAAP, and PENTAP program. MELCOR decides on a penetration tube failure by its failure temperature such as 1273K simply. MAAP considers all penetration failure modes and has the most advanced model for a penetration tube failure model. However, the validation work against the experimental data is very limited. PENTAP program which evaluates the possible penetration tube failure modes such as creep failure, weld failure, tube ejection, and a long term tube failure under given accident condition was developed by KAERI. The experiment for the tube ejection is being performed by KAERI. The temperature distribution and the ablation rate of both weld and lower vessel wall can be obtained through the experiment. This paper includes the updated calculation steps for the weld failure and the tube ejection modes of the PENTAP program to apply the experimental results. PENTAP program can evaluate the possible penetration tube failure modes. It still requires a large amount of efforts to increase the prediction of failure modes. Some calculation steps are necessary for applying the experimental and the numerical data in the PENTAP program. In this study, new calculation steps are added to PENTAP program to enhance the weld failure and tube ejection models using KAERI's experimental data which are the ablation rate and temperature distribution of weld and lower vessel wall.

  13. Establishment of team work system for advanced spent fuel management process

    International Nuclear Information System (INIS)

    The advanced spent fuel management process (ASFMP), which is being developed by KAERI, is now in the 2nd research phase. This phase has a goal to design the total system of active demonstration of ASFMP. It is composed of the core process, remote handling technologies, examination technologies and experimental facilities. For the collaboration of these research fields, a team work system has been established by proper hardware and software selections for use of about 50 project members. This system has been tested by adaptation to the ASFMP project and will be used during the remained project period

  14. Design of teleoperated robot system for nozzle dam maintenance in steam generator

    International Nuclear Information System (INIS)

    The recent development of teleoperated manipulator system in KAERI is presented. The manipulator system is composed of master-slave arm and control system with VME based hierarchical structure. Supervisory control part with graphic workstation provides affluent visual information to human operator. This robot can be operated either in the teleoperation mode with master-slave or in the program mode running by computer system itself to enable installation or removal of nozzle dam appropriately within a water chamber of steam generator. Evaluation and analysis have been carried out to get optimal parameters of the robot. (author)

  15. Management of technical information department

    International Nuclear Information System (INIS)

    This report introduces technical information activities in 1996. They are composed of basic tasks and applied tasks. 1. Basic activities - acquisition, cataloging, and Information services 2. Management of KAERI-TIPS (Technical Information Processing System) 3. Construction of the database for nuclear-related Information 4. Role of Specialized Nuclear Information Center in the field of nuclear energy and cooperation with INIS section of IAEA 5. Beside above activities, in 1996 TID homepage was opened and online document delivery service was provided. (author). 25 tabs., 17 figs

  16. Monte carlo depletion analysis of SMART core by MCNAP code

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Jong Sung; Sim, Hyung Jin; Kim, Chang Hyo [Seoul National Univ., Seoul (Korea, Republic of); Lee, Jung Chan; Ji, Sung Kyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2001-05-01

    Depletion an analysis of SMART, a small-sized advanced integral PWR under development by KAERI, is conducted using the Monte Carlo (MC) depletion analysis program, MCNAP. The results are compared with those of the CASMO-3/ MASTER nuclear analysis. The difference between MASTER and MCNAP on k{sub eff} prediction is observed about 600pcm at BOC, and becomes smaller as the core burnup increases. The maximum difference bet ween two predict ions on fuel assembly (FA) normalized power distribution is about 6.6% radially , and 14.5% axially but the differences are observed to lie within standard deviation of MC estimations.

  17. Analysis of ISO/IEC 17025 for establishment of KOLAS (Korea Laboratory Accreditation Scheme) quality assurance system

    International Nuclear Information System (INIS)

    Besides one existent accredited lab, radioactive material chemical analysis lab, five test laboratories and two calibration labs are under plan to acquire the accreditation from KOLAS. But the current Quality Manual was developed according to ISO Guide 25 that was superceded by ISO/IEC 17025. Since it is tailored to the radioactive material chemical analysis lab, a number of requirements of the Manual are not applicable to the labs other than radioactive material chemical analysis lab. Through the analysis of ISO/IEC 17025, a model of quality system was established which is not only consistent with ISO/IEC 17025 but reflective of the KAERI's situation

  18. User's manual ACE/ONED (Version 1.0)

    International Nuclear Information System (INIS)

    This report explains installation of ACE/ONED code, structure of input and output, how to prepare input and introduces some sample inputs. ACE/ONED developed by KAERI is a two-group one-dimensional diffusion theory code for nuclear design and reactor simulations. The usage of ACE/ONED encompasses core follow calculation, load-following calculation, plant power control simulation, xenon oscillation simulation, control rod maneuvering, and so on. ACE/ONED programmed of FORTRAN 77 in most part can be run on almost all kinds of computer including personal computer. 4 tabs., 4 figs., 8 refs. (Author) .new

  19. Total System Performance Assessment

    International Nuclear Information System (INIS)

    Based on the KAERI FEP list developed through the previous studies, the KAERI FEP Encyclopedia has been developed. Current version is 1.0 which includes all relevant FEPs to compose of two references and all alternative scenarios. Many interaction FEPs between scenario defining FEP(SDF) are created throughout the study. FEPs are classified into many Integrated FEP(IFEP) which eventually become the elements of the RES matrix. The FEAS program one of the component of the KAERI's CYPRUS information system is added to develop the FEP, RES, AC, AMF and finally scenarios. It assists to create transparent way to deal with assessment from the stage of the planning of the R and D to the final stage of the external audit and regulatory body review. Even though MASCOT-K and compartment analysis codes such as AMBER, GoldSim and Ecolego are excellent for TSPA they by in heritage possess a certain limitation especially to identify a proper migration cross sectional area when a relatively big component intersects with a tiny one such as a fracture. It is truly 3D phenomena in nature. MDPSA code is developed which is expected to overcome limitations in compartment models while successfully deals with natural disruptive events. The R and D target for the TSPA is to develop the sufficient scenarios and their variation cases to understand the safety of KRS in every possible aspect. For this, reference scenarios, alternative scenarios covering engineered barrier failure and natural events are developed and assessed respectively for around 100 cases. The stylized template to assess the Korean reference biosphere is developed using the AMBER. Three critical groups, agricultural, freshwater and marine water fishing groups are identified to assess the DCF following the guidelines of ICRP. Based on the QA principles of T2R3, the web based QA system is developed using the procedures in the USNRC 10CFR50 Appendix B. The QA system is combined with the PAID and FEAS to create the comprehensive

  20. Improvement of remote control system of automatic ultrasonic equipment for inspection of reactor pressure vessel

    International Nuclear Information System (INIS)

    One of the important issues related to the nuclear safety is in-service inspection of reactor pressure vessel (RPV). A remote controlled automatic ultrasonic method is applied to the inspection. At present the automatic ultrasonic inspection system owned by KAERI is interrupted due to degradation of parts. In order to resume field inspection new remote control system for the equipment was designed and installed to the existing equipment. New ultrasonic sensors and their modules for RPV inspection were designed and fabricated in accordance with the new requirements of the inspection codes. Ultrasonic sensors were verified for the use in the RPV inspection. (author)

  1. Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Nie,J.; Braverman, J.; Hofmayer, C.; Kim, M. K.; Choi, I-K.

    2009-04-27

    When performing seismic safety assessments of nuclear power plants (NPPs), the potential effects of age-related degradation on structures, systems, and components (SSCs) should be considered. To address the issue of aging degradation, the Korea Atomic Energy Research Institute (KAERI) has embarked on a five-year research project to develop a realistic seismic risk evaluation system which will include the consideration of aging of structures and components in NPPs. Three specific areas that are included in the KAERI research project, related to seismic probabilistic risk assessment (PRA), are probabilistic seismic hazard analysis, seismic fragility analysis including the effects of aging, and a plant seismic risk analysis. To support the development of seismic capability evaluation technology for degraded structures and components, KAERI entered into a collaboration agreement with Brookhaven National Laboratory (BNL) in 2007. The collaborative research effort is intended to continue over a five year period with the goal of developing seismic fragility analysis methods that consider the potential effects of age-related degradation of SSCs, and using these results as input to seismic PRAs. In the Year 1 scope of work BNL collected and reviewed degradation occurrences in US NPPs and identified important aging characteristics needed for the seismic capability evaluations that will be performed in the subsequent evaluations in the years that follow. This information is presented in the Annual Report for the Year 1 Task, identified as BNL Report-81741-2008 and also designated as KAERI/RR-2931/2008. The report presents results of the statistical and trending analysis of this data and compares the results to prior aging studies. In addition, the report provides a description of U.S. current regulatory requirements, regulatory guidance documents, generic communications, industry standards and guidance, and past research related to aging degradation of SSCs. This report

  2. Design of NBI-1 Local I and C

    International Nuclear Information System (INIS)

    To complete the KSTAR neutral beam facility, the I and C (Instrumentation and Control) of KSTAR NBI(Neutral Beam Injector) will be also implemented. The goal of this research is to design EPICS (Experiment Physics and Industrial Control System) based I and C for KSTAR NBI, During about 10 years, KAERI has already installed and operated the neutral beam facility in the test stand, and has many operation experience and material for a new neutral beam facility. Using this experience and material, the new I and C for KSTAR NBI will be improved and implemented, and complied with KSTAR discharge scenario and operation sequence

  3. Management of the radioactive waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kil Jeong; An, Sum Jin; Lee, Kang Mu; Jeong, Kyeong Hwan; Lee, Young Hee; Sohn, Jong Sik; Bae, Sang Min; Kang, Kwon Ho; Yim, Kil Sung; Ui, Keum San; Kim, Tae Kuk; Sohn, Young Jun; You, Young Keol; Park, Young Yoong; Yoon, Bong Keun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-12-01

    The radioactive wastes generated in Korea Atomic Energy Research Institute (KAERI) in 1993 are about 107 m{sup 3} of liquid waste and 169 drums of solid waste. Liquid waste is treated by the evaporation process, the bituminization process, and the solar evaporation process. The solid waste is treated by the compaction process and the cementation process. The radioactive wastes treated in 1993 are about 194 m{sup 3} of liquid waste and 31 drums of solid waste, respectively. 28 tabs., 12 figs. (Author) .new.

  4. Analysis of ISO/IEC 17025 for establishment of KOLAS (Korea Laboratory Accreditation Scheme) quality assurance system

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Ji Hee

    2000-12-01

    Besides one existent accredited lab, radioactive material chemical analysis lab, five test laboratories and two calibration labs are under plan to acquire the accreditation from KOLAS. But the current Quality Manual was developed according to ISO Guide 25 that was superceded by ISO/IEC 17025. Since it is tailored to the radioactive material chemical analysis lab, a number of requirements of the Manual are not applicable to the labs other than radioactive material chemical analysis lab. Through the analysis of ISO/IEC 17025, a model of quality system was established which is not only consistent with ISO/IEC 17025 but reflective of the KAERI's situation.

  5. History for fifty years of Korea Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    This introduces establishment, foundation, technical independent, puberty and preview of KAERI. It is divided six chapters, which deals with research and development on nuclear fission and nuclear fusion, cycle of nuclear fuel and research of nuclear safety, nuclear business and technical development, activity on nuclear safe regulation like establishment and role module for nuclear safety center and check of the safety of nuclear power plant, study of radio therapeutics and cancer treatment, development of human resources for nuclear power and training, general management about regulations, organization, person, contract, facility and building, welfare and establishment and activity of labor union.

  6. Prediction and suppression of beam breakup instability in multicell superconducting cavities

    Science.gov (United States)

    Volkov, V.

    2009-01-01

    Beam breakup instability in superconducting cavities is a serious problem. In this work, a four-cell LEP cavity installed in the KAERI linear accelerator is considered as an example. Dependence of the breakup instability threshold currents on the characteristics of a dipole mode was determined both analytically and numerically. An efficient technique to suppress breakup instability using rf beam focusing within a cavity is suggested. The technique involves applying TE-type monopole higher-order modes and is useful for multicell superconducting cavities with many trapped high-Q dipole modes.

  7. Cold test results of a side-coupled standing-wave electron-accelerating structure

    Science.gov (United States)

    Song, Ki Baek; Li, Yonggui; Lee, Sanghyun; Lee, Byeong-No; Park, Hyung Dal; Cha, Sung-Su; Lee, Byung Cheol

    2013-07-01

    The radio-frequency (RF) cavity for the dual-energy S-band electron linear accelerator (LINAC) is designed for a cargo inspection system (CIS) at the Korea Atomic Energy Research Institute (KAERI). The cold test results of the electron accelerator structure, which has a side-coupled standing-wave interlaced-pulse dual-energy mode, are described. The design concept, basic structure, microwave-tuning method, and cold-test procedure are described as well. The measured dispersion curve, spectrum characteristics, ρ-f relation of the power coupler, and axial field distribution of the accelerating gradient are provided.

  8. Coulomb explosions of deuterium clusters studied by compact design of Nomarski interferometer

    Science.gov (United States)

    Martinkova, Michaela; Kalal, Milan; Rhee, Yong Joo

    2010-08-01

    Interactions of high-intensity femtosecond lasers with deuterium clusters leading to Coulombic explosions and subsequent production of fusion neutrons attracted in recent years considerable attention. In order to maximize the neutron yield finding a dependence of clusters size and their spatial distribution on experimental conditions became very important. In this paper a possibility to measure the deuterium clusters spatial distributions experimentally was analyzed. In combination with experiments recently performed in the Laboratory of Quantum Optics at the Korea Atomic Energy Research Institute (KAERI) interferometry was identified as the diagnostics suitable for such measurements.

  9. Application study of nuclear technologies for integration chemical, biological and radiological technology

    International Nuclear Information System (INIS)

    The projects are suggested the method to maximize the technology and research results which are being carried out by KAERI on the nuclear field. The study presents 1)the technology to rapidly and accurately determine and the nature of contamination, 2) the technology to predict the spread of contaminant and the magnitude of damage, and 3) the expert-aided decision making technology to identify the optimum counter-measures. And the solutions are also suggested the application to military technology in Chemical, Biological and Radiation field. In addition, I hope this kind of cooperation model come to be the good case of military civilian research harmony to improve the national competition capability

  10. User`s manual ACE/ONED (Version 1.0)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ki Bok; Lee, Jeong Chan; Song, Jae Seung; Lee, Chang Kyu; Ji, Sung Kyun; Song, Jae Woong; Kim, Yong Rae; Chang, Jong Hwa [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of)

    1996-03-01

    This report explains installation of ACE/ONED code, structure of input and output, how to prepare input and introduces some sample inputs. ACE/ONED developed by KAERI is a two-group one-dimensional diffusion theory code for nuclear design and reactor simulations. The usage of ACE/ONED encompasses core follow calculation, load-following calculation, plant power control simulation, xenon oscillation simulation, control rod maneuvering, and so on. ACE/ONED programmed of FORTRAN 77 in most part can be run on almost all kinds of computer including personal computer. 4 tabs., 4 figs., 8 refs. (Author) .new.

  11. Total System Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Yong Soo; Kang, Chul Hyung; Lee, Youn Myoung; Han, Ji Woong; Choi, Jong Won; Hahn, Pil Soo; Park, Jeong Hwa; Jeong, Mi Seon

    2007-06-15

    Based on the KAERI FEP list developed through the previous studies, the KAERI FEP Encyclopedia has been developed. Current version is 1.0 which includes all relevant FEPs to compose of two references and all alternative scenarios. Many interaction FEPs between scenario defining FEP(SDF) are created throughout the study. FEPs are classified into many Integrated FEP(IFEP) which eventually become the elements of the RES matrix. The FEAS program one of the component of the KAERI's CYPRUS information system is added to develop the FEP, RES, AC, AMF and finally scenarios. It assists to create transparent way to deal with assessment from the stage of the planning of the R and D to the final stage of the external audit and regulatory body review. Even though MASCOT-K and compartment analysis codes such as AMBER, GoldSim and Ecolego are excellent for TSPA they by in heritage possess a certain limitation especially to identify a proper migration cross sectional area when a relatively big component intersects with a tiny one such as a fracture. It is truly 3D phenomena in nature. MDPSA code is developed which is expected to overcome limitations in compartment models while successfully deals with natural disruptive events. The R and D target for the TSPA is to develop the sufficient scenarios and their variation cases to understand the safety of KRS in every possible aspect. For this, reference scenarios, alternative scenarios covering engineered barrier failure and natural events are developed and assessed respectively for around 100 cases. The stylized template to assess the Korean reference biosphere is developed using the AMBER. Three critical groups, agricultural, freshwater and marine water fishing groups are identified to assess the DCF following the guidelines of ICRP. Based on the QA principles of T2R3, the web based QA system is developed using the procedures in the USNRC 10CFR50 Appendix B. The QA system is combined with the PAID and FEAS to create the

  12. KJRR-FAI Hydraulic Flow Testing Input Package

    Energy Technology Data Exchange (ETDEWEB)

    N.E. Woolstenhulme; R.B. Nielson; D.B. Chapman

    2013-12-01

    The INL, in cooperation with the KAERI via Cooperative Research And Development Agreement (CRADA), undertook an effort in the latter half of calendar year 2013 to produce a conceptual design for the KJRR-FAI campaign. The outcomes of this effort are documented in further detail elsewhere [5]. The KJRR-FAI was designed to be cooled by the ATR’s Primary Coolant System (PCS) with no provision for in-pile measurement or control of the hydraulic conditions in the irradiation assembly. The irradiation assembly was designed to achieve the target hydraulic conditions via engineered hydraulic losses in a throttling orifice at the outlet of the irradiation vehicle.

  13. Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants

    International Nuclear Information System (INIS)

    When performing seismic safety assessments of nuclear power plants (NPPs), the potential effects of age-related degradation on structures, systems, and components (SSCs) should be considered. To address the issue of aging degradation, the Korea Atomic Energy Research Institute (KAERI) has embarked on a five-year research project to develop a realistic seismic risk evaluation system which will include the consideration of aging of structures and components in NPPs. Three specific areas that are included in the KAERI research project, related to seismic probabilistic risk assessment (PRA), are probabilistic seismic hazard analysis, seismic fragility analysis including the effects of aging, and a plant seismic risk analysis. To support the development of seismic capability evaluation technology for degraded structures and components, KAERI entered into a collaboration agreement with Brookhaven National Laboratory (BNL) in 2007. The collaborative research effort is intended to continue over a five year period with the goal of developing seismic fragility analysis methods that consider the potential effects of age-related degradation of SSCs, and using these results as input to seismic PRAs. In the Year 1 scope of work BNL collected and reviewed degradation occurrences in US NPPs and identified important aging characteristics needed for the seismic capability evaluations that will be performed in the subsequent evaluations in the years that follow. This information is presented in the Annual Report for the Year 1 Task, identified as BNL Report-81741-2008 and also designated as KAERI/RR-2931/2008. The report presents results of the statistical and trending analysis of this data and compares the results to prior aging studies. In addition, the report provides a description of U.S. current regulatory requirements, regulatory guidance documents, generic communications, industry standards and guidance, and past research related to aging degradation of SSCs. This report

  14. Compilation of the computing methods in radiation shielding

    International Nuclear Information System (INIS)

    In order to update the KAERI radiation shielding technology, the calculational shielding methods were surveyed throughly. Computer codes and data libraries for radiation shielding calculation were collected and some model calculations were carried out with them. So far the following materials were ensured for our future use: 23 shielding codes, 7 data libraries, 7 data processing codes and 11 peripheral shielding codes. All of these were compiled again for the CYBER-73 computer system, and will be widely used in shielding analysis of accelerators, shipping casks as well as nuclear power plant. (author)

  15. Thermal test of noncombustible urethane for applying to type B packages for radioisotope

    International Nuclear Information System (INIS)

    The package to safely transport the radioisotope, which is produced from HANARO, has to be developed to establish the distribution system of the radioisotope from production to consumption. KAERI is developing the type B package for Ir-192 600 ci. The type B package must be able to endure from thermal condition of 800 .deg. C. However, it is very difficult that the polyurethane, which is used as shock absorber, is maintained less than 327 .deg. C that is melting point of lead used as shielding material. Therefore, the specimens, which are applied noncombustible urethane and fireproof materials, are made. The experimental estimation for thermal condition of 800 .deg. C was conducted

  16. Development of quality assurance procedures for research and development

    International Nuclear Information System (INIS)

    The complexity and the diversity of R and D project are increasing and the life cycle in science and technology is getting shorter. It is required that the results of research and development are subject to prove their objectivity. KAERI is performing complex and various R and D projects. It is necessary that the principle of R and D QA should be applicated to projects for the efficient conduct of R and D and the objective and fair evaluation of the results. So, such requirements as are commonly applicable and necessary, regardless of the type of project and the degree of risk, are selected and QA procedures are established therewith

  17. Analysis of the Status of Foreign Underground Research Laboratories and In-situ Research Topics

    International Nuclear Information System (INIS)

    The status of 11 foreign underground research laboratories (URLs) for the study on high-level waste disposal in the 8 countries including USA has been investigated. The research topics of in-situ study which have been conducted and are planed to do in the URLs have been investigated and analyzed based on the Korean situation. Using the results, the essential in-situ research topics that should be carried out in KURT(KAERI Underground Research Tunnel) are suggested. These topics are classified into two groups, namely the field on engineered barriers and the field on natural barriers

  18. High Temperature Materials Characterization and Advanced Materials Development

    International Nuclear Information System (INIS)

    The project has been carried out for 2 years in stage III in order to achieve the final goals of performance verification of the developed materials, after successful development of the advanced high temperature material technologies for 3 years in Stage II. The mechanical and thermal properties of the advanced materials, which were developed during Stage II, were evaluated at high temperatures, and the modification of the advanced materials were performed. Moreover, a database management system was established using user-friendly knowledge-base scheme to complete the integrated-information material database in KAERI material division

  19. Studies on DANESS Code Modeling

    International Nuclear Information System (INIS)

    The DANESS code modeling study has been performed. DANESS code is widely used in a dynamic fuel cycle analysis. Korea Atomic Energy Research Institute (KAERI) has used the DANESS code for the Korean national nuclear fuel cycle scenario analysis. In this report, the important models such as Energy-demand scenario model, New Reactor Capacity Decision Model, Reactor and Fuel Cycle Facility History Model, and Fuel Cycle Model are investigated. And, some models in the interface module are refined and inserted for Korean nuclear fuel cycle model. Some application studies have also been performed for GNEP cases and for US fast reactor scenarios with various conversion ratios

  20. Preliminary design concepts of an advanced integral reactor

    International Nuclear Information System (INIS)

    An integral reactor on the basis of PWR technology is being conceptually developed at KAERI. Advanced technologies such as intrinsic and passive safety features are implemented in establishing the design concepts of the reactor to enhance the safety and performance. Research and development including laboratory-scale tests are concurrently underway for confirming the technical adoption of those concepts to the rector design. The power output of the reactor will be in the range of 100MWe to 600MWe which is relatively small compared to the existing loop type reactors. The detailed analysis to assure the design concepts is in progress. (author). 3 figs, 1 tab

  1. Preliminary design concept of an advanced integral reactor

    International Nuclear Information System (INIS)

    An integral reactor on the basis of PWR technology is being conceptually developed at KAERI. Advanced technologies such as intrinsic and passive safety features are implemented in establishing the design concepts of the reactor to enhance the safety and performance. Research and development including laboratory-scale tests are concurrently underway for confirming the technical adoption of those concepts to the reactor design. The power output of the reactor will be in the range of 100MWe to 600MWe which is relatively small compared to the existing loop type reactors. The detailed analysis to assure the design concepts is in progress. (author)

  2. Development of applied optical techniques

    International Nuclear Information System (INIS)

    This report resents the status of researches on the applications of lasers at KAERI. A compact portable laser fluorometer detecting uranium desolved in aqueous solution was built. The laser-induced fluorescence of uranium was detected with a photomultiplier tube. A delayed gate circuit and an integrating circuit were used to process the electrical signal. A small nitrogen laser was used to excite uranium. The detecting limit is about 0.1 ppb. The effect of various acidic solutions was investigated. Standard addition technique was incorporated to improve the measuring accuracy. This instrument can be used for safety inspection of workers in the nuclear fuel cycle facilities. (Author)

  3. Current Status of Non-Electric Applications of Nuclear Energy

    International Nuclear Information System (INIS)

    IAEA Technical Meeting(I3-TM-37394) on 'Non-Electric Applications of Nuclear Energy' has been successfully held from March 3 to 6 in 2009 at KAERI/INTEC. The 24 experts from 12 countries participated in this meeting and provided 17 presentations and their opinions and comments in desalination, hydrogen production, and heat application sessions. All of the participants from 12 countries agreed that nuclear power should be the potential carbon-free energy source to replace crude oil and reduce greenhouse gas emissions in the fields of non-electric applications such as desalination, hydrogen production, district heating, and industrial processes applications

  4. An analysis of heating, ventilation and air conditioning system for nuclear facilities

    International Nuclear Information System (INIS)

    An analysis of HVAC system was made on various nuclear facilities such as the existing nuclear power plants in Korea, Post Irradiation Examination Facility at KAERI and Midwest Fuel Recovery Plant in USA, to get basic data and information for the design of the spent fuel interim storage facility to be implemented as one of the radwaste management projects. With the results of this study, the HVAC system to be applied to the spent fuel interim storage facility was selected and the major design considerations of the facility were suggested. (Author)

  5. Management of technical information department

    Energy Technology Data Exchange (ETDEWEB)

    Kim, T. H.; Han, D. H.; Moon, H. W. [and others

    1997-03-01

    This report introduces technical information activities in 1996. They are composed of basic tasks and applied tasks. 1. Basic activities - acquisition, cataloging, and Information services 2. Management of KAERI-TIPS (Technical Information Processing System) 3. Construction of the database for nuclear-related Information 4. Role of Specialized Nuclear Information Center in the field of nuclear energy and cooperation with INIS section of IAEA 5. Beside above activities, in 1996 TID homepage was opened and online document delivery service was provided. (author). 25 tabs., 17 figs.

  6. Establishment of a Learning Management System

    International Nuclear Information System (INIS)

    A web-based learning management system (LMS) has been established to address the need of customized education and training of Nuclear Training Center (NTC) of KAERI. The LMS is designed to deal with various learning types (e.g. on-line, off-line and blended) and a practically comprehensive learning activity cycle (e.g. course preparation, registration, learning, and postlearning) as well as to be user-friendly. A test with an example course scenario on the established system has shown its satisfactory performance. This paper discusses details of the established webbased learning management system in terms of development approach and functions of the LMS

  7. Sensitivity of Input Parameters in the PSHA for NPP Sites

    International Nuclear Information System (INIS)

    In this study, the most uncertain input parameter in the PSHA was identified for Korean NPP sites through sensitivity analysis. Shinuljin Nuclear Units 1 and 2 site was selected in this study. Expert panels developed input parameters for PSHA. Input data were analyzed, and used for sensitivity analysis to see the effects of each parameter on seismic hazard. Through sensitivity analysis, we identified the degree of uncertainty of each parameter. The CONPAS, EQHAZAS, and EQHAZAS Manager codes, which were developed by KAERI, were utilized to compute the seismic hazard. The Gutenberg-Richter parameter was identified as the most uncertain one in this study

  8. Proceedings of DUPIC fuel workshop 97

    International Nuclear Information System (INIS)

    The researchers discuss the technical aspects of DUPIC fuel fabrication in the workshop as follows; 1) The DUPIC fuel development program in KAERI 2) AECL's progress in developing the DUPIC fuel fabrication process 3) Mechanical decladding 4) Nonproliferation and safeguards aspects of the DUPIC fuel cycle concept 5) Assessment of DUPIC fuel compatibility with CANDU-6 6) The development of combination software for spent PWR fuel to fabricate the homogeneous DUPIC fuel 7) Thermodynamic properties of the DUPIC fuel and its performance 8) Captural properties of cesium and ruthenium 9) A secondary fuel removal process : Plasma processing 10) Technology development for DUPIC process safeguards

  9. The Korean Strategy for Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Since 1997, the Korea Atomic Energy Research Institute (KAERI) has been developing core pyroprocessing technology for effective SFM. Research goals are to increase equipment throughput and to minimize the volume of high level radio-active waste. The pyroprocess includes electroreduction, electrorefining, electrowinning, and a waste salt treatment system. This paper briefly addresses unit processes and related innovative technologies. Experiments on the unit processes were tested successfully, and based on the results, engineering-scale equipment has been designed for the PRIDE (PyRoprocess Integrated inactive DEmonstration facility). (author)

  10. The status and prospects of radiation application technology in Korea

    International Nuclear Information System (INIS)

    Full text : This article describes the Nuclear age in Korea which began in 1959 when Korea Atomic Energy Research Institute (KAERI) was first established. Since then, Korea became one of the leading countries in the world nuclear technology and industry. In Korea, 20 nuclear power plants are currently in operation, which produced 34.1% of total electricity in 2009. Furthermore, 8 nuclear power plants are under construction. Eventually, Korea succeeded in exporting nuclear power plant to United Arab Emirates and research reactor to Jordan in 2009. The nuclear application can be divided into two fields. The first one is nuclear power production, and the other is radiation application. Due to the governmental promotion policy, the research activity on radiation and RI application is greatly rising in Korea. Korea Atomic Energy Research Institute (KAERI) and Korea Institute of Radiological and Medical Sciences (KIRAMS) are two leading research institutes in this field. KAERI is conducting RI production and neutron research by using research reactor, and radiation application research such as radiation processing, biotechnological and agricultural application, and cyclotron application. KIRAMS is dedicated to the research on the medical application of radiation. Advanced Radiation Technology Institute (ARTI), constructed in 2006 as a sub organization of KAERI, is a major research institute for radiation application to material engineering, agriculture, biotechnology, environmental technology, and cyclotron beam application. ARTI is equipped with various radiation facilities such as Co-60 irradiation facility (490 kCi and 3 kCi), gamma phytotron, gamma cell, electron beam irradiator, ion implanter, and 30 MeV cyclotron. In material engineering field, new industrial and biomedical materials (carbon fiber filament, composite electrolyte, fuel cell membrane, hydrogels) are developed by radiation processing of polymer materials. In agricultural area, new plant varieties

  11. Development of regulatory policy for SMART-P

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S. H.; Moon, S. H.; Lee, Y. H.; Son, M. K.; Han, K. H.; Kim, D. H. [Korea Association for Nuclear Technology, Taejon (Korea, Republic of)

    2003-06-15

    KAERI promoted the construction of a research reactor, SMART-P, the reduced scale of SMART, with intent to demonstrate the safety and performance of SMART. According to this progress, the development of regulatory process for SMART-P became necessary. The establishment of regulatory policy, based on the current regulatory guidelines as well as technical aspect, became essential matters. Considering the on-going small and medium size reactors m near future, the selection of the appropriate measure in the existing regulatory process to SMART-P is very important. Thus the schematic study for the applicable licensing procedure and regulatory requirements suitable for SMART-P is required.

  12. Development of regulatory policy for SMART-P

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S. H.; Lee, Y. H.; Moo, Philip; Koh, B. J.; Son, M. K.; Han, G. H.; Kim, D. H. [Korea Association for Nuclear Technology, Daejeon (Korea, Republic of)

    2004-06-15

    KAERI promoted the construction of a research reactor, SMART-P, the reduced scale of SMART, with intent to demonstrate the safety and performance of SMART. According to this progress, the development of regulatory process for SMART-P became necessary. The establishment of regulatory policy, based on the current regulatory guidelines as well as technical aspect, became essential matters. Considering the on-going small and medium size reactors in near future, the selection of the appropriate measure in the existing regulatory process to SMART-P is very important. Thus the schematic study for the applicable licensing procedure and regulatory requirements suitable for SMART-P is required.

  13. Application bar-code system for solid radioactive waste management

    International Nuclear Information System (INIS)

    Solid radioactive wastes are generated from the post-irradiated fuel examination facility, the irradiated material examination facility, the research reactor, and the laboratories at KAERI. A bar-code system for a solid radioactive waste management of a research organization became necessary while developing the RAWMIS(Radioactive Waste Management Integration System) which it can generate personal history management for efficient management of a waste, documents, all kinds of statistics. This paper introduces an input and output application program design to do to database with data in the results and a stream process of a treatment that analyzed the waste occurrence present situation and data by bar-code system

  14. Evaluation for the status of the IAEA inspection at Hanaro and TRIGA Mark II and III reactor

    International Nuclear Information System (INIS)

    Safeguards implementation of nuclear material was carried out at facility level in an effect to support the peaceful nuclear activities in KAERI. Safeguards implementation is to fulfill the obligations associated with international agreements such as IAEA comprehensive safeguards agreement and additional protocol. IAEA inspection is the most important and basic factor of the safeguards implementation for the purpose of verifying whether all source or special fissionable material is diverted to nuclear weapons or other nuclear explosive devices. The status of the IAEA inspection at Hanaro and TRIGA Mark II and III reactor during 2001-2006 is evaluated in this report

  15. Improvement of remote control system of automatic ultrasonic equipment for inspection of reactor pressure vessel

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, Yong Moo; Jung, H. K.; Joo, Y. S.; Koo, K. M.; Hyung, H.; Sim, C. M.; Gong, U. S.; Kim, S. H.; Lee, J. P.; Rhoo, H. C.; Kim, M. S.; Ryoo, S. K.; Choi, C. H.; Oh, K. I

    1999-12-01

    One of the important issues related to the nuclear safety is in-service inspection of reactor pressure vessel (RPV). A remote controlled automatic ultrasonic method is applied to the inspection. At present the automatic ultrasonic inspection system owned by KAERI is interrupted due to degradation of parts. In order to resume field inspection new remote control system for the equipment was designed and installed to the existing equipment. New ultrasonic sensors and their modules for RPV inspection were designed and fabricated in accordance with the new requirements of the inspection codes. Ultrasonic sensors were verified for the use in the RPV inspection. (autho0008.

  16. Post irradiation examination of HANARO nucler fuel (KFH-067). Metallographic and density test

    International Nuclear Information System (INIS)

    The 2nd phase post irradiation examination (PIE) of nuclear fuel for HANARO which is a multi purpose research reactor. Built at KAERI has been performed in order to meet the licensing requirement of it. Changes of microstructure and density between fules with 50 and 80 at% burnup have been examined and compared with each other. The detailed PIE items are as follows; microstructure of diameter relate the swelling of fuel, measurement reaction larger particles and aluminum matrix, measurement of oxide layer thickness of fuel cladding, distribute of U3Si, examination of welding part of end plug examination of end plug part feature, and density measurement of fuel with burnup

  17. Post irradiation examination of HANARO nucler fuel (KFH-067). Metallographic and density test

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Byung Ok; Hong, K. P.; Park, D. G.; Choo, Y. S.; Baik, S. J.; Kim, K. H.; Kim, H. C.; Jung, Y. H.; Oho, W. U.; Kim, B. K

    2001-01-01

    The 2nd phase post irradiation examination (PIE) of nuclear fuel for HANARO which is a multi purpose research reactor. Built at KAERI has been performed in order to meet the licensing requirement of it. Changes of microstructure and density between fules with 50 and 80 at% burnup have been examined and compared with each other. The detailed PIE items are as follows; microstructure of diameter relate the swelling of fuel, measurement reaction larger particles and aluminum matrix, measurement of oxide layer thickness of fuel cladding, distribute of U3Si, examination of welding part of end plug examination of end plug part feature, and density measurement of fuel with burnup.

  18. Maintenance and fabrication of electronic equipment

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chong Soo; Moon, Byung Soo; Hong, Suk Boong; Kim, Yong Keun; Kim, Jung Bok

    2000-12-01

    Providing technical support to the maintenance and repair problems of electronic instruments, we have assisted the research and development work, and reduced operation cost of the pilot plants in KAERI. In addition, we have improved the performance of the data processing system of RMS, and modified the cyclic box and IND100 using PLCs which are a facility for airborne monitoring in radiation area and lamp control modules of radiation monitoring control panel respectively. And also, a gamma-ray densitometer for KNGR has been designed and fabricated.

  19. Hydraulic characteristics of HANARO fuel bundles

    Energy Technology Data Exchange (ETDEWEB)

    Cho, S.; Chung, H. J.; Chun, S. Y.; Yang, S. K.; Chung, M. K. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    This paper presents the hydraulic characteristics measured by using LDV (Laser Doppler Velocimetry) in subchannels of HANARO, KAERI research reactor, fuel bundle. The fuel bundle consists of 18 axially finned rods with 3 spacer grids, which are arranged in cylindrical configuration. The effects of the spacer grids on the turbulent flow were investigated by the experimental results. Pressure drops for each component of the fuel bundle were measured, and the friction factors of fuel bundle and loss coefficients for the spacer grids were estimated from the measured pressure drops. Implications regarding the turbulent thermal mixing were discussed. Vibration test results measured by using laser vibrometer were presented. 9 refs., 12 figs. (Author)

  20. Development of the unified version of COBRA/RELAP5

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, J. J.; Ha, K. S.; Chung, B. D.; Lee, W. J.; Sim, S. K. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    The COBRA/RELAP5 code, an integrated version of the COBRA-TF and RELAP5/MOD3 codes, has been developed for the realistic simulations of complicated, multi-dimensional, two-phase, thermal-hydraulic system transients in light water reactors. Recently, KAERI developed an unified version of the COBRA/RELAP5 code, which can run in serial mode on both workstations and personal computers. This paper provides the brief overview of the code integration scheme, the recent code modifications, the developmental assessments, and the future development plan. 13 refs., 5 figs., 2 tabs. (Author)

  1. Classical and Quantum Polynomial Reconstruction via Legendre Symbol Evaluation

    CERN Document Server

    Russell, A; Russell, Alexander; Shparlinksi, Igor

    2002-01-01

    We consider the problem of recovering a hidden monic polynomial f(X) of degree d > 0 over the finite field F of p elements given a black box which, for any x in F, evaluates the quadratic character of f(x). We design a classical algorithm of complexity O(d^2 p^{d + c}), for any c > 0, and also show that the quantum query complexity of this problem is O(d). Some of our results extend those of Wim van Dam, Sean Hallgren and Lawrence Ip obtained in the case of a linear polynomial f(X) = X + s (with unknown s); some are new even in this case.

  2. Association of aphid life stages using DNA sequences:A case study of tribe Eriosomatini(Hemiptera:Aphididae:Pemphiginae)

    Institute of Scientific and Technical Information of China (English)

    He-Cai Zhang; Dong Zhang; Ge-Xia Qiao

    2008-01-01

    Association of aphid 1ife stages based on a portion of COI,sequcnce was applied in Eriosomatini.Tllree aphid specimens,nos.17496,19265a,and 19265b collected on Gramineae roots all clustered with tetraneura chinensis Mordvilko with strong support.The average pairwise p-distance among the four taxa was 0.001(range,0.000-0.002),and that among all the ingroup taxa was 0.065(range.0.000-0.141).This indicated that nos.17496 and 1 9265 b were the secondary.host morohs of T. chinensis.In this paper the secondary host morph of T.chinensis iS described for the first time.Wim the identification of more species'secondary-host morphs,aphids identification based on this morph will be made easily.

  3. Analysis of ANS LWR physics benchmark problems.

    Energy Technology Data Exchange (ETDEWEB)

    Taiwo, T. A.

    1998-07-29

    Various Monte Carlo and deterministic solutions to the three PWR Lattice Benchmark Problems recently defined by the ANS Ad Hoc Committee on Reactor Physics Benchmarks are presented. These solutions were obtained using the VIM continuous-energy Monte Carlo code and the DIF3D/WIMS-D4M code package implemented at the Argonne National Laboratory. The code results for the K{sub eff} and relative pin power distribution are compared to measured values. Additionally, code results for the three benchmark-prescribed infinite lattice configurations are also intercompared. The results demonstrate that the codes produce very good estimates of both the K{sub eff} and power distribution for the critical core and the lattice parameters of the infinite lattice configuration.

  4. Computer codes used during upgrading activities at MINT TRIGA reactor

    Energy Technology Data Exchange (ETDEWEB)

    Mohammad Suhaimi Kassim; Adnan Bokhari; Mohd. Idris Taib [Malaysian Institute for Nuclear Technology Research, Kajang (Malaysia)

    1999-10-01

    MINT TRIGA Reactor is a 1-MW swimming pool nuclear research reactor commissioned in 1982. In 1993, a project was initiated to upgrade the thermal power to 2 MW. The IAEA assistance was sought to assist the various activities relevant to an upgrading exercise. For neutronics calculations, the IAEA has provided expert assistance to introduce the WIMS code, TRIGAP, and EXTERMINATOR2. For thermal-hydraulics calculations, PARET and RELAP5 were introduced. Shielding codes include ANISN and MERCURE. However, in the middle of 1997, MINT has decided to change the scope of the project to safety upgrading of the MINT Reactor. This paper describes some of the activities carried out during the upgrading process. (author)

  5. News from the Library: E-book or printed book? You can have the best of both worlds!

    CERN Multimedia

    CERN Library

    2011-01-01

    Over the last couple of years, the Library has been expanding its collection of electronic books. The most popular titles are, of course, also bought as paper copies and are available for loan.   More than 15,000 titles, across all CERN-relevant disciplines, are now available for download from the Library. Recently, Springer physics and astronomy books, as well as all volumes from Lecture Notes in Physics, were added. So, from now on, readers will not have to queue up for popular books such as "Particle Accelerator Physics" (Wiedemann) or "Particle Detection with Drift Chambers" (Blum, Rolandi and Riegler), which are often in high demand. From left to right: Tullio Basaglia (CERN Library), Christian Caron (Springer) and Wim van der Stelt (Springer). In addition to providing electronic access, the publisher offers people at CERN the possibility to purchase paperback copies, distributed under the label “My Copy”, for the tempting price of &a...

  6. Digital Photography and Cinema

    Directory of Open Access Journals (Sweden)

    Alberto Sdegno

    2013-10-01

    Full Text Available In some significant film productions of the last thirty years photography play an innovative role, not only from a technical point of view, but also regarding the plot of the movie. The examples described in the text - from Blade Runner to the recent Inception - may allow a better understanding of the way in which the technology of image processing has altered the perception of film sequences, also helping to transform the opinions on this new way of work by artists usually adopting traditional practices, such as Wim Wenders. His film, Until the end of the world, in fact, appears as an episode particularly eloquent in the filmography of the artist, which testifies a change in the definition of the working method.

  7. Academic Management and Administration System Reform in Higher Education Institutions

    Institute of Scientific and Technical Information of China (English)

    Xiang Xianming

    2006-01-01

    Reforms in colleges and universities should promote the humanistic character of higher education-rather than simply serve for pure economic production--but also observe the sacred mission of transmiting and creating culture and knowledge.wim these two possessing momentous differences.These then demand rationality in academic management to guard against declination toward dehumanization or bureaucracy.Thus.the relationship between academic power and administrative power must be harmonized,and a reasonable equilibrium must be guaranteed.An academic management idea of power in learning is particularly emphasized to overcome the false polarity of managerism,straightforwardly reducing complicated academic operations to a kind of economic prosecution,hence truly promoting the function of a higher education system.

  8. Parametric evaluation of mixed (low and high enriched) fuel core for a swimming pool type research reactor

    International Nuclear Information System (INIS)

    A study has been carried out to evaluate the performance of a swimming pool type research reactor core comprised of mixed (low and high enriched) uranium fuel. The study includes the calculations of core reactivity, worth of control rods and core criticality at the Beginning Of Life (BOL) of the core and for two operating conditions Cold Zero Power (CZP) and Hot Full Power (HFP). Further, to ensure safe and stable operation of the core from nuclear design point of view, average power densities in the fuel region, power peaking factors, axial power distribution in the hot channel and reactivity feed back coefficients have also been calculated. Two group fluxes have also been determined at different irradiation locations. All these calculations have been carried out employing reactor lattice code WIMS-D14 and reactor analysis code CITATION The calculated results show reasonably good agreement with the quoted operational data of the previous LEU cores. (Author)

  9. Reactor physics calculations and their experimental validation for conversion and upgrading of a typical swimming pool type research reactor

    International Nuclear Information System (INIS)

    Detailed neutronic analysis of a typical swimming pool type research reactor, Pakistan Research Reactor-1 (PARR-1), was carried out for conversion of its core from 93% highly enriched uranium to 20% low enriched uranium fuel with power upgrading from 5 to 10 MW. Standard computer codes WIMS-D/4 and CITATION were employed to calculate core excess reactivity, power defect, reactivity effect of xenon and samarium, reactivity worth of fuel element, worth of control rods, shutdown margin, reactivity feedback coefficients, neutron flux and power peaking factors. A series of low and high power tests were performed on the newly converted core to determine its performance. A comparison between the calculated and measured results is presented in this article. The agreement is generally good

  10. Determination of neutron energy spectrum at a pneumatic rabbit station of a typical swimming pool type material test research reactor

    International Nuclear Information System (INIS)

    The method of multiple foil activation was used to measure the neutron energy spectrum, experimentally, at a rabbit station of Pakistan Research Reactor-1 (PARR-1), which is a typical swimming pool type material test research reactor. The computer codes MSITER and SANDBP were used to adjust the spectrum. The pre-information required by the adjustment codes was obtained by modelling the core and its surroundings in three-dimensions by using the one dimensional transport theory code WIMS-D/4 and the multidimensional finite difference diffusion theory code CITATION. The input spectrum covariance information required by MSITER code was also calculated from the CITATION output. A comparison between calculated and adjusted spectra shows a good agreement

  11. Clock-turning gait synthesis for humanoid robots

    Institute of Scientific and Technical Information of China (English)

    Zhe TANG; Zengqi SUN; Hongbo LIU; Meng Joo ER

    2007-01-01

    Turning gait is a basic motion for humanoid robots.This paper presents a method for humanoid turning.i.e.clock-turning.The objective of clock-turning is to change robot direction at a stationary spot.The clock-turning planning consists of four steps:ankle trajectory generation,hip trajectory generation,knee trajectory generation,and inverse kinematics calculation.Our proposed method is based on a typical humanoid structure with 12 DOFs(degrees of freedom).The final output of clock-turning planning is 12 reference trajectories.which are used to control a humanoid robot wim 12 DOFs.ZMP(zero moment point)is used as stability criterion for the planning.Simulation experiments are conducted to verify the effectiveness of our proposed clock-turning method.

  12. Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes

    Directory of Open Access Journals (Sweden)

    Lindley Benjamin A.

    2016-01-01

    Full Text Available The majority of nuclear reactors operating in the world today and similarly the majority of near-term new build reactors will be LWRs. These currently accommodate traditional Zr clad UO2/PuO2 fuel designs which have an excellent performance record for normal operation. However, the events at Fukushima culminated in significant hydrogen production and hydrogen explosions, resulting from high temperature Zr/steam interaction following core uncovering for an extended period. These events have resulted in increased emphasis towards developing more accident tolerant fuels (ATFs-clad systems, particularly for current and near-term build LWRs. R&D programmes are underway in the US and elsewhere to develop ATFs and the UK is engaging in these international programmes. Candidate advanced fuel materials include uranium nitride (UN and uranium silicide (U3Si2. Candidate cladding materials include advanced stainless steel (FeCrAl and silicon carbide. The UK has a long history in industrial fuel manufacture and fabrication for a wide range of reactor systems including LWRs. This is supported by a national infrastructure to perform experimental and theoretical R&D in fuel performance, fuel transient behaviour and reactor physics. In this paper, an analysis of the Integral Inherently Safe LWR design (I2S-LWR, a reactor concept developed by an international collaboration led by the Georgia Institute of Technology, within a US DOE Nuclear Energy University Program (NEUP Integrated Research Project (IRP is considered. The analysis is performed using the ANSWERS reactor physics code WIMS and the EDF Energy core simulator PANTHER by researchers at the University of Cambridge. The I2S-LWR is an advanced 2850 MWt integral PWR with inherent safety features. In order to enhance the safety features, the baseline fuel and cladding materials that were chosen for the I2S-LWR design are U3Si2 and advanced stainless steel respectively. In addition, the I2S-LWR design

  13. Theoretical estimation of sodium-24 activity concentration in primary coolant system of research reactor, Dhruva

    International Nuclear Information System (INIS)

    24Na is formed by the fast neutron reaction 27AI (n,a)24Na in the aluminium clad and flow tube of Dhruva fuel element. Heavy water, the primary coolant, contains activity escaping from clad and flow tube by recoil and from corrosion. For the purpose of estimating the 24Na activity in the Dhruva reactor, fast neutron reaction is considered as a dominant source. The method will then depend on the surface area of the aluminium exposed to the heavy water. In this paper, we estimate 24Na activity in the heavy water from recoil process only. The neutron flux above 4 MeV has been computed by the lattice computer code WIMS-D/4 (WIMSD 4, 1984) and also by using the Monte Carlo computer code. The Range of 24Na in the aluminium is computed using the SRIM computer code). (author)

  14. The calculation of resonance captures in a few-group approximation

    International Nuclear Information System (INIS)

    The theory of few-group treatment of resonance captures is expounded, and appropriate methods for the spatial and energy averaging of cross-sections are derived in a form suitable for machine computation - i.e. as material cross-sections which can be used directly in a neutronics code. The method treats both self and mutual shielding of resonances (the latter, interaction with other nuclides, by an approximate method), in geometries ranging from homogeneous mixtures, through regular rod arrays to clustered fuel assemblies, and includes the effect of spatial source distribution, for example between moderator and coolant in pressure tube configurations. A particular application of the method has been to the lattice calculation code WIMS, and a sample 10-group library of data for U-238 and U-235 as used in this code is included. (author)

  15. Fuel bundle geometry and composition influence on coolant void reactivity reduction in ACR and CANDU reactors

    International Nuclear Information System (INIS)

    It is very well known that the CANDU reactor has positive Coolant Void Reactivity (CVR), which is most important criticisms about CANDU. The most recent innovations based on using a thin absorbent Hafnium shell in the central bundle element were successfully been applied to the Advanced CANDU Reactor (ACR) project. The paper's objective is to analyze elementary lattice cell effects in applying such methods to reduce the CVR. Three basic fuel designs in their corresponding geometries were chosen to be compared: the ACR-1000TM, the RU-43 (developed in INR Pitesti) and the standard CANDU fuel. The bundle geometry influence on void effect was also evaluated. The WIMS calculations proved the Hafnium absorber suitability (in the latest 'shell design') to achieve the negative CVR target with great accuracy for the ACR-1000 fuel bundle design than for the other two projects. (authors)

  16. WLUP burnable absorber isotopic influence on coolant void reactivity in an ACR lattice

    International Nuclear Information System (INIS)

    ACRTM-1000 is the topmost nuclear power reactor promoted by AECL during the next years as a response to increasing competitiveness in the nuclear energy market. Recent AECL innovations allowed overriding for the first time the main CANDU drawback - the positive Coolant Void Reactivity (CVR). The solution was using of burnable absorbers in the central element (CE) whose radius was significantly increased. The paper's goal is to evaluate the isotopic influence on CVR and, as result, on nuclear safety when the central element is filled one by one with the most common oxide of burnable isotopes from the IAEA updated WIMS library (WLUP). The isotopes taken into account are: Dysprosium, Hafnium, Gadolinium, Erbium and Holmium. A comparison between CVRs given at the using of above lanthanides and their suitability to be used in the central element design is illustrated in the paper. (authors)

  17. Analysis of calculated neutron flux response at detectors of G.A. Siwabessy multipurpose reactor (RSG-GAS Reactor)

    International Nuclear Information System (INIS)

    Multi Purpose Reactor G.A. Siwabessy (RSG-GAS) reactor core possesses 4 fission-chamber detectors to measure intermediate power level of RSG-GAS reactor. Another detector, also fission-chamber detector, is intended to measure power level of RSG-GAS reactor. To investigate influence of space to the neutron flux values for each detector measuring intermediate and power levels has been carried out. The calculation was carried out using combination of WIMS/D4 and CITATION-3D code and focused on calculation of neutron flux at different detector location of RSG-GAS typical working core various scenarios. For different scenarios, all calculation results showed that each detector, located at different location in the RSG-GAS reactor core, causes different neutron flux occurred in the reactor core due to spatial time effect

  18. Development of a computer code for neutronic calculations of a hexagonal lattice of nuclear reactor using the flux expansion nodal method

    Directory of Open Access Journals (Sweden)

    Mohammadnia Meysam

    2013-01-01

    Full Text Available The flux expansion nodal method is a suitable method for considering nodalization effects in node corners. In this paper we used this method to solve the intra-nodal flux analytically. Then, a computer code, named MA.CODE, was developed using the C# programming language. The code is capable of reactor core calculations for hexagonal geometries in two energy groups and three dimensions. The MA.CODE imports two group constants from the WIMS code and calculates the effective multiplication factor, thermal and fast neutron flux in three dimensions, power density, reactivity, and the power peaking factor of each fuel assembly. Some of the code's merits are low calculation time and a user friendly interface. MA.CODE results showed good agreement with IAEA benchmarks, i. e. AER-FCM-101 and AER-FCM-001.

  19. Face-à-face avec l’ange : du regard frontal de l’art byzantin au « regard à la caméra »

    OpenAIRE

    Sandra Gorgievski

    2012-01-01

    Le regard hiératique et frontal de l’ange dans l’art chrétien byzantin, puis dans l’art roman, s’estompe à mesure que l’humanisme triomphe à la Renaissance : le regard de l’ange se détourne du spectateur, à l’image de l’évolution des pratiques religieuses et idéologiques et la réception des images cultuelles. Dans Les Ailes du désir de Wim Wenders, l’identification d’un ange passe par d’autres détails (iconique, pictural ou particolare). Le « regard à la caméra » adressé au spectateur et les ...

  20. Snow evolution in a semi-arid mountainous area combining snow modelling and Landsat spectral mixture analysis

    Science.gov (United States)

    Pimentel, R.; Herrero, J.; Polo, M. J.

    2015-05-01

    This study proposes the use of both physically-distributed hydrological modelling in combination with satellite remote sensing images, to study the evolution of the snowpack in the Sierra Nevada mountains, in southern Spain. The snowmelt-accumulation module inside WiMMed (Watershed Integrated Management in Mediterranean Environment) hydrological model was employed, which includes the use of depletion curves to expand the energy and water balance equations over a grid representation. Snow maps obtained from spectral mixture analysis of Landsat images were used to evaluate this model at the study site. The results show a significant agreement between observed and simulated snow pixels in the area, which allows production of sequences of snow maps with greater resolution than the remote sensing images employed. However, some mismatches do appear at the boundaries of the snow area, mainly related to: (a) the great number of mixed pixels; and (b) the influence of the snow transport by wind.