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Sample records for jaea

  1. JAEA Takasaki annual report 2006

    Tanaka, Shigeru

    2008-03-01

    JAEA Takasaki annual report 2006 describes research and development activities performed from April 1, 2006 to March 31, 2007 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) space, nuclear and energy engineering, 2) environmental conservation and resource security, 3) biotechnology and medical application, and 4) advanced materials, analysis and novel technology. This annual report contains 186 reports consisting of 178 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, related press-releases, TV programs, patents, and the type of research collaborations as Appendices. (author)

  2. JAEA Takasaki annual report 2010

    Kojima, Takuji

    2012-01-01

    JAEA Takasaki annual report 2010 describes research and development activities performed from April 1, 2010 to March 31, 2011 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) Space, Nuclear and Energy Engineering, 2) Environmental Conservation and Resource Exploitation, 3) Medical and Biotechnological Application, and 4) Advanced Materials, Analysis and Novel Technology. This annual report contains 159 reports consisting of 151 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, patents, related press-releases, television broadcasting, and the type of research collaborations as Appendices. (author)

  3. JAEA Takasaki annual report 2012

    Kojima, Takuji

    2014-03-01

    JAEA Takasaki annual report 2012 describes research and development activities performed from April 1, 2012 to March 31, 2013 mainly with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) Space, Nuclear and Energy Engineering, 2) Environmental Conservation and Resource Exploitation, 3) Medical and Biotechnological Application, and 4) Advanced Materials, Analysis and Novel Technology. This annual report contains 164 reports consisting of 156 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, a list of publications, patents, related press-releases, television broadcasting, and the type of research collaborations as appendices. (author)

  4. JAEA Takasaki annual report 2011

    Kojima, Takuji

    2013-01-01

    JAEA Takasaki annual report 2011 describes research and development activities performed from April 1, 2011 to March 31, 2012 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) Space, Nuclear and Energy Engineering, 2) Environmental Conservation and Resource Exploitation, 3) Medical and Biotechnological Application, and 4) Advanced Materials, Analysis and Novel Technology for Facilities. This annual report contains 158 reports consisting of 150 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, patents, related press-releases, television broadcasting, and the type of research collaborations as appendices. (author)

  5. JAEA Takasaki annual report 2005

    Ohara, Yoshihiro

    2007-02-01

    JAEA Takasaki annual report 2005 describes research and development activities performed from April 1, 2005 to March 31, 2006 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and those in a recent few years with electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) nuclear and energy engineering, 2) environmental conservation and resource security, 3) biotechnology and medical application, 4) advanced materials, analysis and novel technology. This annual report contains 182 reports consisting of 174 research papers and 8 status reports on operation/maintenance of above irradiation facilities, and a list of publications, related press-releases, IV programs, patents, and the type of research collaborations as Appendices. (author)

  6. JAEA Takasaki annual report 2009

    Tanaka, Shigeru [Japan Atomic Energy Agency, Takasaki Advanced Radiation Research Inst., Takasaki, Gunma (Japan)

    2011-01-15

    JAEA Takasaki annual report 2009 describes research and development activities performed from April 1, 2009 to March 31, 2010 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three {sup 60}Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) space, nuclear and energy engineering, 2) environmental conservation and resource security, 3) biotechnology and medical application, and 4) advanced materials, analysis and novel technology. This annual report contains 165 reports consisting of 157 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, patents, related press-releases, TV programs, and the type of research collaborations as Appendices. (author)

  7. JAEA Takasaki annual report 2009

    Tanaka, Shigeru

    2011-01-01

    JAEA Takasaki annual report 2009 describes research and development activities performed from April 1, 2009 to March 31, 2010 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) space, nuclear and energy engineering, 2) environmental conservation and resource security, 3) biotechnology and medical application, and 4) advanced materials, analysis and novel technology. This annual report contains 165 reports consisting of 157 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, patents, related press-releases, TV programs, and the type of research collaborations as Appendices. (author)

  8. JAEA Takasaki annual report 2014

    Yokota, Wataru

    2016-02-01

    JAEA Takasaki annual report 2014 describes research and development activities performed from April 1, 2014 to March 31, 2015 mainly with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) Space, Nuclear and Energy Engineering, 2) Environmental Conservation and Resource Exploitation, 3) Medical and Biotechnological Application, and 4) Advanced Materials, Analysis and Novel Technology. This annual report contains 162 reports consisting of 154 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, a list of publications, patents, related press-releases, television broadcasting, and the type of research collaborations as appendices. (author)

  9. JAEA Takasaki annual report 2007

    Tanaka, Shigeru

    2008-11-01

    JAEA Takasaki annual report 2007 describes research and development activities performed from April 1, 2007 to March 31, 2008 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) space, nuclear and energy engineering, 2) environment conservation and resource security, 3) biotechnology and medical application, and 4) advanced materials, analysis and novel technology. This annual report contains 174 reports consisting of 166 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, related press-releases, TV programs, patents, and the type of research collaborations as Appendices. (author)

  10. JAEA Takasaki annual report 2011

    Kojima, Takuji [Japan Atomic Energy Agency, Takasaki Advanced Radiation Research Institute, Takasaki, Gunma (Japan)

    2013-01-15

    JAEA Takasaki annual report 2011 describes research and development activities performed from April 1, 2011 to March 31, 2012 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three {sup 60}Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) Space, Nuclear and Energy Engineering, 2) Environmental Conservation and Resource Exploitation, 3) Medical and Biotechnological Application, and 4) Advanced Materials, Analysis and Novel Technology for Facilities. This annual report contains 158 reports consisting of 150 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, patents, related press-releases, television broadcasting, and the type of research collaborations as appendices. (author)

  11. JAEA Takasaki annual report 2008

    Tanaka, Shigeru

    2009-12-01

    JAEA Takasaki annual report 2008 describes research and development activities performed from April 1, 2008 to March 31, 2009 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) space, nuclear and energy engineering, 2) environmental conservation and resource security, 3) biotechnology and medical application, and 4) advanced materials, analysis and novel technology. This annual report contains 161 reports consisting of 153 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, related press-releases, TV programs, patents, and the type of research collaborations as Appendices. (author)

  12. JAEA Takasaki annual report 2012

    Kojima, Takuji [Japan Atomic Energy Agency, Takasaki Advanced Radiation Research Institute, Takasaki, Gunma (Japan)

    2014-03-15

    JAEA Takasaki annual report 2012 describes research and development activities performed from April 1, 2012 to March 31, 2013 mainly with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three {sup 60}Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) Space, Nuclear and Energy Engineering, 2) Environmental Conservation and Resource Exploitation, 3) Medical and Biotechnological Application, and 4) Advanced Materials, Analysis and Novel Technology. This annual report contains 164 reports consisting of 156 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, a list of publications, patents, related press-releases, television broadcasting, and the type of research collaborations as appendices. (author)

  13. JAEA Takasaki annual report 2010

    Kojima, Takuji [Japan Atomic Energy Agency, Takasaki Advanced Radiation Research Inst., Takasaki, Gunma (Japan)

    2012-01-15

    JAEA Takasaki annual report 2010 describes research and development activities performed from April 1, 2010 to March 31, 2011 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three {sup 60}Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) Space, Nuclear and Energy Engineering, 2) Environmental Conservation and Resource Exploitation, 3) Medical and Biotechnological Application, and 4) Advanced Materials, Analysis and Novel Technology. This annual report contains 159 reports consisting of 151 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, patents, related press-releases, television broadcasting, and the type of research collaborations as Appendices. (author)

  14. JAEA Takasaki annual report 2013

    Kojima, Takuji

    2015-03-01

    JAEA Takasaki annual report 2013 describes research and development activities performed from April 1, 2013 to March 31, 2014 mainly with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/gamma-ray irradiation facilities (an electron accelerator and three 60 Co gamma-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: 1) Space, Nuclear and Energy Engineering, 2) Environmental Conservation and Resource Exploitation, 3) Medical and Biotechnological Application, and 4) Advanced Materials, Analysis and Novel Technology. This annual report contains 169 reports consisting of 160 research papers and 9 status reports on operation/maintenance of the irradiation facilities described above, a list of publications, patents, related press-releases, television broadcasting, and the type of research collaborations as appendices. (author)

  15. Report of Committee for JAEA Internationalization Initiative

    2013-03-01

    In global circumstances surrounding nuclear energy, the role expected to Japan Atomic Energy Agency (JAEA) is becoming increasingly important. JAEA has been promoted an initiative for the international hub in order to increase the scientific competitiveness of Japan and make international contributions, by gathering excellent researchers from the entire world with the latest facilities. Also, JAEA established 'Committee for JAEA Internationalization Initiative', which will discuss issues such as environmental improvement for accepted foreigners, direction of efforts for internationalization initiative and strategies to improve current situation. This report mentions the results of the committee's discussion including current issues for the initiative and recommendations for their solution, as well as the issues to be discussed in order to enhance international awareness of JAEA staff. The following is the summary of the recommendations for the initiative: Set up local teams that focus on the situation of each site in order to provide detailed support for foreigners from diversified backgrounds. Develop systems for emergency situations to provide information for safety swiftly for foreigners and confirm their safety, in addition to preparing emergency goods. Prepare bilingual documents and systems that foreigners need to use for their work based on importance and frequency of use of such systems and documents. (author)

  16. Status Report of JAEA Nuclear Data Center

    Fukahori, T.

    2011-01-01

    Nuclear Data Center of Japan Atomic Energy Agency (JAEA) is working on the nuclear data evaluation for Japanese Evaluated Nuclear Data Library JENDL. The evaluation and related works are performed in the cooperation with Universities, Research Organizations and Companies in Japan through Japanese Nuclear Data Committee. The number of Nuclear Data Center staff members is 7 including one technical assistant as of April 1, 2011. The manpower is not enough for the evaluation and related work. The budget is obtained from MEXT (Ministry of Education, Culture, Sports, Science and Technology), but is annually decreasing after establishment of JAEA. Especially the budget must be much shorter than usual in 2011FY, since many of it will be spent for recovering after the earthquake. We are seeking another fund to compensate the decreasing budget.

  17. Status Report of JAEA Nuclear Data Center

    Fukahori, T.

    2012-01-01

    Nuclear Data Center of Japan Atomic Energy Agency (JAEA) is working on the nuclear data evaluation for Japanese Evaluated Nuclear Data Library JENDL. The evaluation and related works are performed in the cooperation with Universities, Research Organizations and Companies in Japan through Japanese Nuclear Data Committee. The number of Nuclear Data Center staff members is 7 including one technical assistant as of April 1, 2012. The manpower is not enough for the evaluation and related work. The budget is obtained from Ministry of Education, Culture, Sports, Science and Technology (MEXT), but is annually decreasing after establishment of JAEA. Especially the budget must be much shorter than usual in 2012FY, since many of it will be spent for recovering after the earthquake and Fukushima accident. We are seeking another fund to compensate the decreasing budget.

  18. Proposed plan for a JAEA internationalization initiative (JII) (Contract research)

    Bolton, Paul R; Kawanishi, Shunichi [Japan Atomic Energy Agency, Photo-Medical Research Center, Kizugawa, Kyoto (Japan); Mizuki, Jun' ichiro [Japan Atomic Energy Agency, Quantum Beam Science Directorate, Sayo, Hyogo (Japan)

    2011-01-15

    Concepts for a JAEA Internationalization Initiative, JII are presented. Following a general discussion of issues and recommendations for JII, a 'fast startup JII' is proposed in the form of fast start action items (FSAI). The FSAI represent a clear set of action items that can be implemented at the KPSI/PMRC site which would serve as a seed site for test and evaluation. A JAEA Internationalization Initiative that is guided by evaluation and tailored for JAEA as a whole can be established with appropriate oversight and tracking at each JAEA site by local JII teams. In addition to recommendations for the KPSI/PMRC seed site, the roles of the Quantum Beam Science Directorate (QuBS) leadership and the International Affairs Department (IAD) of JAEA are also discussed. Current KPSI/PMRC activities that are consistent with a JII are briefly presented. (author)

  19. Proposed plan for a JAEA internationalization initiative (JII) (Contract research)

    Bolton, Paul R.; Kawanishi, Shunichi; Mizuki, Jun'ichiro

    2011-01-01

    Concepts for a JAEA Internationalization Initiative, JII are presented. Following a general discussion of issues and recommendations for JII, a 'fast startup JII' is proposed in the form of fast start action items (FSAI). The FSAI represent a clear set of action items that can be implemented at the KPSI/PMRC site which would serve as a seed site for test and evaluation. A JAEA Internationalization Initiative that is guided by evaluation and tailored for JAEA as a whole can be established with appropriate oversight and tracking at each JAEA site by local JII teams. In addition to recommendations for the KPSI/PMRC seed site, the roles of the Quantum Beam Science Directorate (QuBS) leadership and the International Affairs Department (IAD) of JAEA are also discussed. Current KPSI/PMRC activities that are consistent with a JII are briefly presented. (author)

  20. JAEA's activities relating the Fukushima Nuclear Plant accident

    Tagawa, Akihiro

    2012-01-01

    JAEA started the activities relating to the Fukushima nuclear plant accident immediately after the Great East Japan Earthquake. The Office of Fukushima Partnership Operations for Environmental Remediation was opened and the JAEA staff was stationed as the base of cooperation with other organizations. It is conducting environmental radiation monitoring, environmental radioactivity analyses, resident public consulting, and demonstration of decontamination technology. Experts of JAEA are providing technical advice and supports to the Nuclear Safety Commission of Japan and the Ministry of Education, Culture and Sports. Furthermore, the water radiolysis leading to hydrogen gas evolution by Cs 137 adsorbed zeolite and the technique for radioactive waste process and its disposal of fuel debris are being studied. JAEA's Nuclear Emergency Assistance and Training Center (NEAT) is acting as a center of these supporting activities of JAEA. (S. Ohno)

  1. Development of analytical techniques for safeguards environmental samples at JAEA

    Sakurai, Satoshi; Magara, Masaaki; Usuda, Shigekazu; Watanabe, Kazuo; Esaka, Fumitaka; Hirayama, Fumio; Lee, Chi-Gyu; Yasuda, Kenichiro; Inagawa, Jun; Suzuki, Daisuke; Iguchi, Kazunari; Kokubu, Yoko S.; Miyamoto, Yutaka; Ohzu, Akira

    2007-01-01

    JAEA has been developing, under the auspices of the Ministry of Education, Culture, Sports, Science and Technology of Japan, analytical techniques for ultra-trace amounts of nuclear materials in environmental samples in order to contribute to the strengthened safeguards system. Development of essential techniques for bulk and particle analysis, as well as screening, of the environmental swipe samples has been established as ultra-trace analytical methods of uranium and plutonium. In January 2003, JAEA was qualified, including its quality control system, as a member of the JAEA network analytical laboratories for environmental samples. Since 2004, JAEA has conducted the analysis of domestic and the IAEA samples, through which JAEA's analytical capability has been verified and improved. In parallel, advanced techniques have been developed in order to expand the applicability to the samples of various elemental composition and impurities and to improve analytical accuracy and efficiency. This paper summarizes the trace of the technical development in environmental sample analysis at JAEA, and refers to recent trends of research and development in this field. (author)

  2. Report of Committee for JAEA Internationalization Initiative (Translated document)

    NONE

    2013-07-15

    In global circumstances surrounding nuclear energy, the role expected by the Japan Atomic Energy Agency (JAEA) is becoming increasingly important. JAEA has promoted an initiative for an international hub in order to increase the scientific competitiveness of Japan and make international contributions, by gathering excellent researchers from the entire world with the latest facilities. Also, JAEA has established the 'Committee for JAEA Internationalization Initiative', which will discuss issues such as environmental improvement for accepted foreigners, direction of efforts for internationalization initiative and strategies to improve the current situation. This report mentions the results of the committee's discussion including current issues for the initiative and recommendations for their solution, as well as issues to be discussed in order to enhance international awareness of JAEA staff. The following is the summary of the recommendations for the initiative: Set up local teams that focus on the situation of each site in order to provide detailed support for foreigners from diversified backgrounds. Develop systems for emergency situations to provide information for safety swiftly for foreigners and confirm their safety, in addition to preparing emergency goods. Prepare bilingual documents and systems that foreigners need to use for their work based on importance and frequency of use of such systems and documents. (author)

  3. Report of Committee for JAEA Internationalization Initiative (Translated document)

    2013-07-01

    In global circumstances surrounding nuclear energy, the role expected by the Japan Atomic Energy Agency (JAEA) is becoming increasingly important. JAEA has promoted an initiative for an international hub in order to increase the scientific competitiveness of Japan and make international contributions, by gathering excellent researchers from the entire world with the latest facilities. Also, JAEA has established the 'Committee for JAEA Internationalization Initiative', which will discuss issues such as environmental improvement for accepted foreigners, direction of efforts for internationalization initiative and strategies to improve the current situation. This report mentions the results of the committee's discussion including current issues for the initiative and recommendations for their solution, as well as issues to be discussed in order to enhance international awareness of JAEA staff. The following is the summary of the recommendations for the initiative: Set up local teams that focus on the situation of each site in order to provide detailed support for foreigners from diversified backgrounds. Develop systems for emergency situations to provide information for safety swiftly for foreigners and confirm their safety, in addition to preparing emergency goods. Prepare bilingual documents and systems that foreigners need to use for their work based on importance and frequency of use of such systems and documents. (author)

  4. JAEA's activities for cleaning at contaminated area in Fukushima

    Nakayama, Shinichi; Tokizawa, Takayuki; Iijima, Kazuki; Kurikami, Hiroshi; Funaki, Hironori

    2011-01-01

    JAEA is taking part in development of decontamination measures for public facilities such as schools and parks. This report concerns as a model case to several schools and their swimming pool. For school yard contaminated, topsoil of 5 cm was removed and covered with clean soil, while the removed soil was berried into a 1.5m- deep trench. Water decontamination of swimming pools was also tried based on a series of tests. JAEA is also studying to make specific polymer grafted with cesium-absorbing material. It was found that the most important is a trustful relationship with school officials, municipality and local people through dialogue and decontamination works. (S. Ohno)

  5. Traceability on radon measurements at the JAEA Ningyo-toge

    Ishimori, Yuu

    2007-01-01

    The study on the establishment and maintenance of the traceability on radon measurements at the Ningyo-toge Environmental Engineering Center of the Japan Atomic Energy Agency (JAEA Ningyo-toge) is illustrated in this paper. The primary standard is a radium solution provided by the National Bureau of Standard (present the National Institute of Standards and Technology) in the USA, and the secondary standard is the method with gas-filled ionization chambers calibrated with the solution. The radon reference chamber is utilized to provide reference atmospheres in calibration experiments for other monitors. Through the intercomparison experiments among the international reference institutes, it was confirmed that the reliability and consistency of the secondary standard of the JAEA Ningyo-toge have been retained since 1984. It shows that the calibration and measurement techniques associated with the traceability system constructed have been maintained well at the JAEA Ningyo-toge. Science there is no reference field as a national standard and no method regulated by the Japanese Industrial standard, this paper provides not only reliability and accuracy of the radon measurements at the JAEA Ningyo-toge, but also useful information for the standardization of radon measurements in Japan. (author)

  6. Development of JAEA sorption database (JAEA-SDB). Update of data evaluation functions and sorption/QA data

    Tachi, Yukio; Suyama, Tadahiro; Ochs, Michael; Ganter, Charlotte

    2011-03-01

    Sorption and diffusion of radionuclides in buffer materials (bentonite) and rocks are the key processes in the safe geological disposal of radioactive waste, because migration of radionuclides in this barrier is expected to be diffusion-controlled and retarded by sorption processes. It is therefore necessary to understand the sorption and diffusion processes and develop database compiling reliable data and mechanistic/predictive models, so that reliable parameters can be set under a variety of geochemical conditions relevant to performance assessment (PA). For this purpose, Japan Atomic Energy Agency (JAEA) has developed databases of sorption and diffusion parameters in buffer materials (bentonite) and rocks. These sorption and diffusion databases (SDB/DDB) were firstly developed as an important basis for the H12 PA of high-level radioactive waste disposal, and have been provided through the Web. JAEA has been continuing to improve and update the SDB/DDB in view of potential future data needs, focusing on assuring the desired quality level and testing the usefulness of the databases for possible applications to PA-related parameter setting. The present report focuses on developing and updating of the sorption database (JAEA-SDB) as basis of integrated approach for PA-related K d setting. This includes an overview of database structure, contents and functions including additional data evaluation function focusing on multi-parameter dependence, operating method, PA-related applications of the web-based JAEA-SDB. K d data and their QA results are updated by focusing our recent activities on the K d setting and mechanistic model development. As a result, 4,250 K d data from 32 references are added, total K d values in the JAEA-SDB are about 28,540. The QA/classified K d data are about 39% for all K d data in JAEA-SDB. The updated JAEA-SDB is expected to make it possible to obtain quick overview of the available data, and to have suitable access to the respective data

  7. Development of JAEA sorption database (JAEA-SDB). Update of sorption/QA data in FY2015

    Tachi, Yukio; Suyama, Tadahiro

    2016-03-01

    Sorption and diffusion of radionuclides in buffer materials (bentonite) and rocks are the key processes in the safe geological disposal of radioactive waste, because migration of radionuclides in these barrier materials is expected to be diffusion-controlled and retarded by sorption processes. It is therefore necessary to understand the sorption and diffusion processes and develop databases compiling reliable data and mechanistic/predictive models, so that reliable parameters can be set under a variety of geochemical conditions relevant to performance assessment (PA). For this purpose, Japan Atomic Energy Agency (JAEA) has developed databases of sorption and diffusion parameters in bentonites and rocks. These sorption and diffusion databases (SDB/DDB) were firstly developed as an important basis for the H12 PA of high-level radioactive waste disposal, and have been provided through the Web. JAEA has been continuing to improve and update the SDB/DDB in view of potential future data needs, focusing on assuring the desired quality level and testing the usefulness of the databases for possible applications to PA-related parameter setting. The present report focuses on improving and updating of the sorption database (JAEA-SDB) as basis of integrated approach for PA-related K d setting and mechanistic sorption model development. This includes an overview of database structure, contents and functions including additional data evaluation function focusing on statistical data evaluation and grouping of data related to potential perturbations. K d data and their QA results are updated by focusing our recent activities on the K d setting and mechanistic model development. As a result, 11,206 K d data from 83 references were added, total number of K d values in the JAEA-SDB reached about 58,000. The QA/classified K d data reached about 60% for all K d data in JAEA-SDB. The updated JAEA-SDB is expected to make it possible to obtain quick overview of the available data, and to

  8. Introduction of commercialization success cases with JAEA's result development business

    Takenaka, Shingo; Yoshii, Fumio; Nakajima, Junsaku

    2009-01-01

    JAEA's result development business has conducted joint researches on 69 subjects for ten years and brought about 26 commercialization success cases. This article presented six cases to contribute the activation of local industry to some extend. Demineralization technology for circulating water of air-conditioning and heating was developed using graft polymers. Biological effects of irradiated chitosan led to product of plant energizer oligo-glucosamine-L'. High performance gas analyzer developed for fusion research was used for componential analysis of yeast starter of old sake for taste check. Titanium-clad materials for knife were produced with hot rolling machine. Application of biodegradable polymer (polylactic acid) to demonstration lenses was developed. Surface condition and salt concentration sensors for snowy and icy roads were developed based on JAEA's patents. (T. Tanaka)

  9. Development of a comprehensive nuclear materials accountancy system at JAEA

    Takeda, Hideyuki; Usami, Masayuki; Hirosawa, Naonori; Fujita, Yoshihisa; Kodani, Yoshiki; Komata, Kazuhiro

    2007-01-01

    The Japan Atomic Energy Agency (JAEA) is submitting various types of accounting reports of international controlled materials to the Ministry of Education, Culture, Sports, Science, and Technology (MEXT) based on domestic laws and regulations. JAEA developed a comprehensive Nuclear Material Accountancy System to achieve uniform management of the data of each facility by using a company-wide database. Personal computers in each facility are connected throughout the company using an in-house network to create the comprehensive Nuclear Material Accountancy System. This System uses personal computers to facilitate timely communication and for easy maintenance and operation. Efficient data processing and quality control functions for accountancy reporting are also realized by this System. In addition, the System has the ability to extract and summarize data about Plutonium Management in the company for public announcement. This report introduces and describes the details and functions of this System. (author)

  10. Status of recent utilization of JAEA AMS MUTSU

    Amano, Hikaru; Kabuto, Shoji; Kinoshita, Naoki

    2008-01-01

    Tandetron AMS was set up at the JAEA Mutsu in 1997. This AMS has been used for the determination of 14 C/ 12 C and 129 I/ 127 I. So far, 7075 samples have been measured for the 14 C-AMS, and 1317 samples have been measured for the 129 I-AMS until the end of September 2007. This AMS has adopted the open door policy which is periodic filing of applications and judgment for use twice a year, expecting broad usage including environmental issue and estimation of radioactive wastes for the general users from the spring of 2006. Eight external assignments have adopted in the first half of 2007, eleven external assignments have adopted in the latter half of 2007 at the JAEA AMS MUTSU. (author)

  11. Introduction of the WAN accelerator in JAEA network

    Hirayama, Takashi; Kannari, Masaaki; Sato, Tomohiko

    2012-06-01

    In pursuance of 'The Optimization Plan on the network of JAEA', which aims to ensure network reliability and information security and to improve convenience in using the network, we are engaged in the optimization of inter-institute/center network bandwidth. This is a record of an introduction of WAN Accelerator into the network to Ningyo-toge Environmental Engineering Center which bandwidth is limited due to a geographically constraint. (author)

  12. Present status of the Tandetron Accelerator at Mutsu Establishment, JAEA

    Amano, Hikaru; Kabuto, Shoji; Kinoshita, Naoki; Suzuki, Takashi; Otosaka, Shigeyoshi; Kuwabara, Jun; Kitamura, Toshikatsu; Tanaka, Takayuki; Kitada, Yoshinobu; Watanabe, Yukiya

    2007-01-01

    The accelerator mass analyzer system at Mutsu Establishment, JAEA consists of a 3 MV tandem electrostatic accelerator and two beamlines for measuring isotope ratios of carbon and iodine. The present paper reports on (1) the operation and maintenance works in fiscal 2005, (2) the measurements of 14 C and 129 I and the related technology development, and (3) the public utilization of the system, which was started from 2006. (K.Y.)

  13. Quality policy on radiocarbon measurement at the JAEA-Mutsu AMS

    Otosaka, Shigeyoshi; Amano, Hikaru; Kabuto, Shoji; Kinoshita, Naoki; Tanaka, Takayuki

    2008-01-01

    Since April 2006, a common use of the JAEA-Mutsu AMS has been available for researchers inside/outside JAEA. Before the receiving 14 C data to the researchers, we calculate pMC (per cent modern carbon) value and accuracy/precision of the measurement is confirmed according to the JAEA-Mutsu's quality policy. In this paper, an outline of the quality policy is described. (author)

  14. Proceedings of JAEA-KPSI 8th symposium on advanced photon research

    2008-08-01

    JAEA-KPSI-APRC 8th Symposium on Advanced Photon Research was held at Kansai Photon Research Institute, Japan Atomic Energy Agency (JAEA-KPSI) in Kizu, Kyoto on June 4th - 5th, 2007. This report consists of contributed papers for the speeches and poster presentations in JAEA-KPSI-APRC 8th Symposium. The 33 of the presented papers are indexed individually. (J.P.N.)

  15. Conceptual design for the next JAEA's enterprise resource planning system

    Kimura, Hideo; Aoyagi, Tetsuo; Sakai, Manabu; Sato, Taiichi; Tsuji, Minoru

    2008-11-01

    JAEA developed the ERP (Enterprise Resource Planning) system at the establishment in 2005, aiming to support and enhance its business-critical task such as financial accounting and contract management. We considered the conceptual design of the next ERP system, and we implemented the prototype system to validate its effectiveness. Moreover, we implemented the simple add-on tool for rapid and easy development. At the result, we gauged the future prospects that the XML-centric system which we designed will offer high modularity, flexibility, connectivity between other systems, independence among subsystems. The simple add-on tool also demonstrated its effectiveness. (author)

  16. Research on radiation effect and radiation protection at JAEA

    Saito, Kimiaki

    2007-01-01

    Researches on radiation effect and radiation protection at JAEA have been carried out in different sections. In recent years, the organizations were rearranged to attain better research circumstances, and new research programs started. At present, radiation effect studies focus on radiation effect mechanisms at atomic, molecular and cellular levels including simulation studies, and protection studies focus on dosimetry for conditions difficult to cover with currently used methods and data as well as the related basic studies. The outlines of the whole studies and also some descriptions on selected subjects will be given in this paper. (author)

  17. Atomic and Molecular Data Activities for Fusion Research in JAEA

    Nakano, T.

    2011-01-01

    The Japan Atomic Energy Agency (JAEA) has been producing, collecting and compiling cross-section data for atomic and molecular collisions and spectral data relevant to fusion research. In this talk, an overview of our activities since the last meeting in September 2009 will be presented. The state selective charge transfer cross-section data of Be 4+ , C 4+ and C 6+ by collision with H(n=2) in the collision energy range between 62 eV/amu and 6.2 keV/amu have been calculated with a molecular-bases close-coupling method. The calculated charge transfer data of C 4+ was implemented in a collisional-radiative model code for C 3+ , and it is shown that in some cases the charge transfer from C 4+ to H(n=2) populates predominantly C 3+ (n = 6, 7). The cross-section data of dissociative recombination and excitation of HD + , D 2+ , DT + , T 2+ 3 HeH + and 4 HeH + were produced by theoretical calculation. The principal quantum number of dissociated H atom isotopes was also given. The analytical expressions for the cross-section data for 26 processes of He-collision systems were produced in order to facilitate practical use of the data. The compiled data are in preparation for the web site at the URL of http://www-jt60.naka.jaea.go.jp/engish/JEAMDL/. The chemical sputtering yield data of CFC materials with hydrogen isotope collisions have been compiled. The ionization rate of W 44+ and the radiative and the dielectronic recombination rates of W 45+ were calculated with FAC. The ratio of these rates was compared with experimentally measured ratio of W 45+ density to W 44+ density in JT-60U, showing that the calculated ratio of the recombination ratio of W 45+ to the ionization rate of W 44+ is accurate within the experimental uncertainty (∼ 30%). The atomic and molecular data activities in JAEA are pursued in collaboration with Japanese universities, and other department of JAEA. (author)

  18. Present status of the JAEA-AMS-TONO. 2012

    Saito-Kokubu, Yoko; Matsubara, Akihiro; Ishimaru, Tsuneari; Hanaki, Tatsumi; Nishizawa, A.; Miyake, M.; Ohwaki, Y.; Nishio, T.; Tanaka, Takayuki

    2013-01-01

    The Tono Geoscience Center (TGC) of JAEA has been conducting research into deep underground environments for R and D program related to the geological disposal of High-Level Radioactive Waste. The AMS system of the TGC has routinely been used for 14 C-AMS since it started to be operated in 1998. In recent years, we have promoted the development of system technology for routine 10 Be-AMS. An inter-laboratory comparison of the 14 C-AMS was performed with the JAEA-AMS-MUTSU. The data of isotope ratios obtained with both AMS systems showed that there is no significant difference between them. In the development for the 10 Be-AMS, several test measurements have been performed by using standard samples. The results indicated fairly robust stability of data quality, which contributed to complete the development for routine 10 Be measurement. We are now in the stage of the development for routine 26 Al-AMS. (author)

  19. JAEA involvement in Education and Training for Decommissioning

    Nakayama, Shinichi

    2017-01-01

    Education and Training for Decommissioning in Japan: E&T for decommissioning in Japan is: prioritized to decommissioning of TEPCO’s Fukushima Daiichi NPS; mostly government-funded: - Ministry Of Education, Culture, Sports, Science And Technology; -Ministry Of Economy, Trade And Industry; performed through collaborative R&D activities between research institutes, university/college, and academic societies. JAEA is involved in the E&T through: - University summer schools on robotics, decommissioning robot competition; - Participation in and/or invitation to JAEA’s international Fukushima Research Conferences, and to cooperative courses with scientific institutions; - Lectures at universities/colleges; - Hot facility construction/operation for engineers, characterization of radioactive wastes and fuel debris for radiochemists and technicians

  20. Regional cooperation planning. Project planning for JAEA/SNL regional cooperation on remote monitoring

    Olsen, John

    2006-01-01

    Developing cooperation between the JAEA's NPSTC and the NNCA may take advantage of bilateral activities between those parties and SNL. The merger of JNC and JAERI has affected the schedule for JAEA/SNL cooperation. Also, the evolution of the NNCA as an independent agency has slowed the projected schedule for cooperation between the JAEA and the NNCA. A potential schedule for establishment of a quadrilateral remote monitoring system may include interim activities, securing an agreement of some type, and actual establishment of VPN links. A parallel schedule might exist for informing other regional parties and gaining their interest. (author)

  1. Institutional overviews. Overview of the JAEA and the Nuclear Nonproliferation Science and Technology Center

    Senzaki, Masao

    2006-01-01

    The Nuclear Nonproliferation Science and Technology Center (NPSTC) was formed within the new Japan Atomic Energy Agency (JAEA) to carry out safeguards and material control duties for the JAEA. Development of technologies and procedures for safeguards is an important duty. In addition, the new NPSTC will assume a 'think tank' role in support of the nonproliferation regime, help train nonproliferation experts, and cooperate with academic, government and non-governmental organizations on nonproliferation issues. This report briefly summarizes the formation of the JAEA and describes the duties and structure of the NPSTC in detail. (author)

  2. Annual report of Fusion Research and Development Directorate of JAEA

    Kubo, Hirotaka; Hoshino, Katsumichi; Isei, Nobuaki; Nakamura, Hiroo; Sato, Satoshi; Shimada, Katsuhiro; Sugie, Tatsuo

    2009-01-01

    This annual report provides an overview of major results and progress on research and development (R and D) activities at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from April 1, 2007 to March 31, 2008, including those performed in collaboration with other directorates of JAEA, research institutes, and universities. The JT-60U operation regime was extended toward the long sustainment of high normalized beta (β N ) with good confinement (β N =2.6 x 28 s). Effectiveness of real-time control of current profile was demonstrated in high β plasmas. Toroidal momentum diffusivity and the convection velocity were systematically clarified for the first time, and intrinsic rotation due to pressure gradient was discovered. Effects of toroidal rotation and magnetic field ripple on type 1 ELM size and pedestal performance were clarified, and type I ELM control was demonstrated by toroidal rotation control. Variety of inter-machine experiments, such as JT-60U and JET, and domestic collaborations were performed. In theoretical and analytical researches, for the NEXT (Numerical Experiment of Tokamak) project, numerical simulations of a tokamak plasma turbulence progressed and a zonal field generation was investigated. Also, nonlinear MHD simulations found the Alfven resonance effects on the evolution of magnetic islands driven by externally applied perturbations. Integrations of several kinds of element codes progressed in the integrated transport/MHD model, the integrated edge/pedestal model and the integrated SOL/divertor model. In fusion reactor technologies, R and Ds for ITER and fusion DEMO plants have been carried out. For ITER, a steady state operation of the 170GHz gyrotron up to 800 s with 1 MW was demonstrated. Also extracted beam current of the neutral beam injector has been extended to 320 mA at 796 keV. In the ITER Test Blanket Module (TBM), designs and R and Ds on Water and Helium Cooled Solid Breeder TBMs were progressed. For

  3. Development of computational science in JAEA. R and D of simulation

    Nakajima, Norihiro; Araya, Fumimasa; Hirayama, Toshio

    2006-01-01

    R and D of computational science in JAEA (Japan Atomic Energy Agency) is described. Environment of computer, R and D system in CCSE (Center for Computational Science and e-Systems), joint computational science researches in Japan and world, development of computer technologies, the some examples of simulation researches, 3-dimensional image vibrational platform system, simulation researches of FBR cycle techniques, simulation of large scale thermal stress for development of steam generator, simulation research of fusion energy techniques, development of grid computing technology, simulation research of quantum beam techniques and biological molecule simulation researches are explained. Organization of JAEA, development of computational science in JAEA, network of JAEA, international collaboration of computational science, and environment of ITBL (Information-Technology Based Laboratory) project are illustrated. (S.Y.)

  4. General principles for future JAEA-NNCA cooperation in remote monitoring

    Olsen, John

    2006-01-01

    Precedents from existing bilateral documents might be useful in envisioning structure of a future NNCA/JAEA arrangement. This discussion included a listing of potential cooperative topics that NNCA and NPSTC had noted in previous informal meetings at O'arai and Daejeon over the preceding 18 months. A broad range of activities might be considered that reflect similar responsibilities in the JAEA's NPSTC and in the NNCA. (author)

  5. Overview of oceanographic research in JAEA-RGES

    Otosaka, Shigeyoshi

    2010-01-01

    Oceanographic research activities conducted by JAEA-RGES were described. The activities consist of two parts: a multi-year research project in the Japan Sea and the most recent research in the region Off-Rokkasho, Aomori, Japan. A series of expeditions in the Japan Sea has revealed horizontal and vertical distributions of artificial radionuclides. In addition, radiocarbon measurements of seawater have enabled us to understand general seawater circulation as well as transport processes of dissolved radionuclides in the sea. In the region Off-Rokkasho, where a reprocessing plant of spent nuclear fuel is located, site specific values for radionuclide migration model have been obtained. Special attention was paid to characteristics of particles in water, some of which contribute to the vertical transport of radionuclides via sinking process. It was suggested that concentrations of particulate materials are controlled not only by primary production but also by supplies of terrestrial materials. From this result, we concluded that the land-sea interaction would play an important role in the radionuclide behavior in coastal areas. (author)

  6. Summaries of research and development activities by using JAEA computer system in FY2007. April 1, 2007 - March 31, 2008

    2008-11-01

    Center for Computational Science and e-Systems (CCSE) of Japan Atomic Energy Agency (JAEA) installed large computer systems including super-computers in order to support research and development activities in JAEA. This report presents usage records of the JAEA computer system and the big users' research and development activities by using the computer system in FY2007 (April 1, 2007 - March 31, 2008). (author)

  7. Summaries of research and development activities by using JAEA computer system in FY2006. April 1, 2006 - March 31, 2007

    2008-02-01

    Center for Promotion of Computational Science and Engineering (CCSE) of Japan Atomic Energy Agency (JAEA) installed large computer systems including super-computers in order to support research and development activities in JAEA. CCSE operates and manages the computer system and network system. This report presents usage records of the JAEA computer system and the big users' research and development activities by using the computer system in FY2006 (April 1, 2006 - March 31, 2007). (author)

  8. Summaries of research and development activities by using JAEA computer system in FY2009. April 1, 2009 - March 31, 2010

    2010-11-01

    Center for Computational Science and e-Systems (CCSE) of Japan Atomic Energy Agency (JAEA) installed large computer systems including super-computers in order to support research and development activities in JAEA. This report presents usage records of the JAEA computer system and the big users' research and development activities by using the computer system in FY2009 (April 1, 2009 - March 31, 2010). (author)

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

    Ishihara, Masahiro; Ishitsuka, Etsuo; Suzuki, Masahide

    2012-12-01

    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. 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)

  10. Information exchange on HTGR and nuclear hydrogen technology between JAEA and INET in 2008

    Fujimoto, Nozomu; Tachibana, Yukio; Sun Yuliang

    2009-07-01

    The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been growing because the high temperature heat produced by the reactor can be utilized not only for efficient power generation but also for broad process heat applications, especially for thermo-chemical hydrogen production to fuel a prospective hydrogen economy in future. Presently only two HTGR reactors are operational in the world, including the HTTR (High Temperature Engineering Test Reactor) in Japan Atomic Energy Agency (JAEA) and the HTR-10 in the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. JAEA and INET have cooperated since 1986 in the field of HTGR development, particularly on the HTTR and HTR-10 projects. This report describes the cooperation activities on HTGR and nuclear hydrogen technology between JAEA and INET in 2008. (author)

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

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

    2008-11-01

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

  12. Information exchange on HTGR and nuclear hydrogen technology between JAEA and INET in 2009

    Fujimoto, Nozomu; Wang Hong

    2010-07-01

    The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been growing because the high temperature heat produced by the reactor can be utilized not only for efficient power generation but also for broad process heat applications, especially for thermo-chemical hydrogen production to fuel a prospective hydrogen economy in future. Presently only two HTGR reactors are operational in the world, including the HTTR (High Temperature Engineering Test Reactor) in Japan Atomic Energy Agency (JAEA) and the HTR-10 in the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. JAEA and INET have cooperated since 1986 in the field of HTGR development, particularly on the HTTR and HTR-10 projects. This report describes the cooperation activities on HTGR and nuclear hydrogen technology between JAEA and INET in 2009. (author)

  13. Information exchange mainly on HTGR operation and maintenance technique between JAEA and INET in 2005

    Tachibana, Yukio; Hino, Ryutaro; Yu Suyuan

    2006-06-01

    The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been growing because the high temperature heat produced by the reactor can be utilized not only for efficient power generation but also for broad process heat applications, especially for thermo-chemical hydrogen production to fuel a prospective hydrogen economy in future. Presently only two HTGR reactors are operational in the world, including the HTTR (High Temperature Engineering Test Reactor) in Japan Atomic Energy Agency (JAEA) and the HTR-10 in the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. JAEA and INET have cooperated since 1986 in the field of HTGR development, particularly on the HTTR and HTR-10 projects. This report describes the cooperation with emphasis on HTGR operation and maintenance techniques between JAEA and INET and outlines cooperation activities during the fiscal year 2005. (author)

  14. Status of recent utilization of JAEA AMS MUTSU and the revision of the charge

    Yamamoto, Nobuo; Kinoshita, Naoki; Kabuto, Shoji; Tanaka, Takayuki

    2010-01-01

    Tandetron Accelerator Mass Spectrometer in the Japan Atomic Energy Agency Mutsu office (JAEA AMS Mutsu: High Voltage Engineering Europa product, Model 4130-AMS) consists of 3MV tandem type accelerator and the 2 beam lines for measurement of isotope ratio for carbon and iodine. Steady operation of carbon beam line was started in December, 1999 and that of iodine beam line was started in May, 2003. This facility was initially used for studies on transport processes of radionuclides in marine environment. From the fiscal year 2006, this facility became a shared facility to provide data for various projects at JAEA and others. This paper describes the status of recent utilization of JAEA AMS MUTSU, and the revision of the charge from fiscal year 2010. (author)

  15. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2009

    2010-08-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2009 was the fifteenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2009 on 32 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; eleven of which ended in 2009. Of these, six were related to fast breeder reactors, two to the nuclear fuel cycle, and three to geological disposal/geoscience. (author)

  16. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2011

    2012-08-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as “universities, etc.” below), which means that the fiscal year 2011 was the seventeenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2011 on 27 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; thirteen of which ended in 2011. Of these, seven were related to fast breeder reactors, two to the nuclear fuel cycle, one to radiation safety, and three to geological disposal/geoscience. (author)

  17. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2007

    2008-10-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) of the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2007 was the thirteenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2007 on 32 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; twelve of which ended in 2007. Of these, six were related to fast breeder reactors, two to the nuclear fuel cycle, and two to geological disposal/geoscience. (author)

  18. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2008

    2009-09-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2008 was the fourteenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2008 on 32 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; twelve of which ended in 2008. Of these, six were related to fast breeder reactors, one to the nuclear fuel cycle, one to radiation safety, and four to geological disposal/geoscience. (author)

  19. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2012

    2013-11-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2012 was the eighteenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2012 on 20 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; ten of which ended in 2012. Of these, three were related to fast breeder reactors, five to the nuclear fuel cycle, and two to geological disposal/geoscience. (author)

  20. FRENDY: A new nuclear data processing system being developed at JAEA

    Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi; Suyama, Kenya; Fukahori, Tokio

    2017-09-01

    JAEA has provided an evaluated nuclear data library JENDL and nuclear application codes such as MARBLE, SRAC, MVP and PHITS. These domestic codes have been widely used in many universities and industrial companies in Japan. However, we sometimes find problems in imported processing systems and need to revise them when the new JENDL is released. To overcome such problems and immediately process the nuclear data when it is released, JAEA started developing a new nuclear data processing system, FRENDY in 2013. This paper describes the outline of the development of FRENDY and both its capabilities and performances by the analyses of criticality experiments. The verification results indicate that FRENDY properly generates ACE files.

  1. Proceedings of the 1st JAEA/KAERI information exchange meeting on HTGR and nuclear hydrogen technology

    Sato, Hiroyuki; Sakaba, Nariaki; Nishihara, Tetsuo; Yan, Xing L.; Hino, Ryutaro

    2007-03-01

    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 Program 13th of the JAEA/KAERI Implementation, 'Development of HTGR and Nuclear Hydrogen Technology'. JAEA and KAERI mutually showed the status and future plan of the HTTR (High-Temperature Engineering Test Reactor) project in Japan and of the NHDD (Nuclear Hydrogen Development and Demonstration) project in Korea, respectively, and discussed collaboration items. This proceedings summarizes all materials of presented technical discussions on HTGR and hydrogen production technology as well as the meeting briefing including collaboration items. (author)

  2. JAEA's actions and contributions to the strengthening of nuclear non-proliferation

    Suda, Kazunori; Suzuki, Mitsutoshi; Michiji, Toshiro

    2012-06-01

    Japan, a non-nuclear weapons state, has established a commercial nuclear fuel cycle including LWRs, and now is developing a fast neutron reactor fuel cycle as part of the next generation nuclear energy system, with commercial operation targeted for 2050. Japan Atomic Energy Agency (JAEA) is the independent administrative agency for conducting comprehensive nuclear R&D in Japan after the merger of Japan Atomic Energy Research Institute (JAERI) and Japan Nuclear Cycle Development Institute (JNC). JAEA and its predecessors have extensive experience in R&D, facility operations, and safeguards development and implementation for new types of nuclear facilities for the peaceful use of nuclear energy. As the operator of various nuclear fuel cycle facilities and numerous nuclear materials, JAEA makes international contributions to strengthen nuclear non-proliferation. This paper provides an overview of JAEA's development of nuclear non-proliferation and safeguards technologies, including remote monitoring of nuclear facilities, environmental sample analysis methods and new efforts since the 2010 Nuclear Security Summit in Washington D.C.

  3. A new blanket tritium recovery experiment with intense DT neutron source at JAEA/FNS

    Ochiai, Kentaro, E-mail: ochiai.kentaro@jaea.go.jp [Japan Atomic Energy Agency, 2-166 Omotedate Obuchi, Rokkasho, Aomori 039-3212 (Japan); Edao, Yuki [Japan Atomic Energy Agency, 2-4 Shirane Shirakata, Tokai, Ibaraki 319-1195 (Japan); Hoshino, Tsuyoshi [Japan Atomic Energy Agency, 2-166 Omotedate Obuchi, Rokkasho, Aomori 039-3212 (Japan); Kawamura, Yoshinori [Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193 (Japan); Ohta, Masayuki; Kwon, Saerom; Konno, Chikara [Japan Atomic Energy Agency, 2-4 Shirane Shirakata, Tokai, Ibaraki 319-1195 (Japan)

    2016-11-01

    Highlights: • For detail investigation of the tritium recovery performance on the fusion reactor blanket, we have started a new blanket tritium recovery experiment with ionization chamber at JAEA/FNS. • A new improved container was provided for the appropriate tritium measurement by IC and also utilized for the enhancement of TPR in the new container. The TPR was calculated with a calculation code MCNP5 and some typical nuclear data libraries and then the radioactivity of the tritium recovery with LSC corresponded with that of calculation. • The tritium release curves by the IC outputs are similar to those by the LSC output. However, it was indicated that the quantitative measurement by IC needed further improvement for the tritium recovery. - Abstract: We have performed the tritium release experiment on the fusion reactor blanket at JAEA/FNS since 2009, and then clarified the ratio of tritium release and the recovered tritium chemical form. In order to acquire the detailed tritium recovery performances, we have started a new blanket tritium recovery experiment with ionization chamber (IC) at JAEA/FNS. For the appropriate tritium measurement with IC, we improved the experimental container and carried out with an intense DT neutron source at JAEA/FNS. From our new experiment, the tritium recovery radioactivity from the LSC measurement corresponds with the calculation within 6%. However, it was pointed out that further improvement in the quantitative tritium measurement by IC method was needed.

  4. Proceedings of the fourth JAEA-US EPA workshop on radiation risk assessment

    Endo, Akira; Boyd, Michael

    2007-02-01

    This report is the proceedings of the fourth workshop jointly organized by the Japan Atomic Energy Agency (JAEA) and the United States Environmental Protection Agency (US EPA) under the terms of agreement for cooperation in the field of radiation protection. The workshop was sponsored by the Nuclear Science and Engineering Directorate and was held at the Nuclear Science Research Institute, the Tokai Research and Development Center, JAEA, on November 7-8, 2006. The objective of the workshop was to exchange and discuss recent information on radiation effects, radiation risk assessment, radiation dosimetry, emergency response, radiation protection standards, and waste management. Twenty-two papers were presented by experts from JAEA, US EPA, the National Academies, Oak Ridge National Laboratory, Washington State University and the US Nuclear Regulatory Commission. Three keynotes addressed research on radiation effects and radiation protection at JAEA, the latest report on health risks from exposure to low levels of ionizing radiation published by the National Research Council (BEIR VII Phase 2), and recent developments in Committee 2 for the forthcoming recommendations of the International Commission on Radiological Protection (ICRP). The workshop provided a good opportunity for identifying future research needed for radiation risk assessment. The 22 of the presented papers are indexed individually. (J.P.N.)

  5. Present status and future challenges of nuclear forensics technology developments in JAEA

    Kimura, Yoshiki; Shinohara, Nobuo; Okubo, Ayako; Toda, Nobufumi; Funatake, Yoshio; Kataoka, Osamu; Matsumoto, Tetsuya; Watahiki, Masaru; Kuno, Yusuke

    2014-01-01

    Japan Atomic Energy Agency (JAEA) has started a nuclear forensics (NF) technology development project from JFY 2011, according to the National Statement of Japan in Nuclear Security Summit 2010. This paper will present the progress and future prospects of the development project during JFY 2011 to 2013. The project on NF technology in JAEA includes the development of analytical technologies such as isotope and impurity measurements, morphology analysis, age determination technique, and the prototype of nuclear forensics library (NFL) for future national NFL. Some analytical devices were installed for the analytical technology developments, and various uranium materials produced in JAEA facilities at Ningyo-toge have been measured to verify the analytical technologies. A nuclear material database of the prototype NFL was also developed with brief tools of multivariate analysis and image analysis. The implementation of the analytical technologies, the development of advanced analytical technologies and the system improvements of the prototype NFL will be continued from JFY 2014 in JAEA. The national regime and national response plan are remained as a big challenge to establish the national NF capabilities in Japan. (author)

  6. Summaries of research and development activities by using JAEA computer system in FY2005. April 1, 2005 - March, 31, 2006

    2006-10-01

    Center for Promotion of Computational Science and Engineering (CCSE) of Japan Atomic Energy Agency (JAEA) installed large computer systems including super-computers in order to support research and development activities in JAEA. CCSE operates and manages the computer system and network system. This report presents usage records of the JAERI computer system and the big users' research and development activities by using the computer system in FY2005 (April 1, 2005 - March 31, 2006). (author)

  7. Recent progress on R and D of innovative extractants and adsorbents for partitioning of minor actinides at JAEA

    Kimura, Takaumi; Morita, Yasuji; Koma, Yoshikazu

    2010-01-01

    The R and D effort on partitioning of minor actinides (MA) at the Japan Atomic Energy Agency (JAEA) has been concentrated on development and improvement of innovative extractants and adsorbents as the fundamental studies and of MA recovery process as the advanced aqueous reprocessing system in fast reactor cycle technology development (FaCT) project. This paper reviews current status and prospects of the R and D activities on the partitioning of MA at JAEA. (authors)

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

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

    2011-12-15

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

  9. Report of Committee for JAEA Internationalization Initiative. Focusing on the activities of local teams

    2015-10-01

    The 'Committee for JAEA Internationalization Initiative' was established in 2010 with the view to discuss the policy and improvement plans for JAEA's achievement of an international center of excellence (ICOE), which include improving the environment to accept foreign researchers, etc. The existing issues to be solved in the effort for ICOE and recommendations for the solutions, which were discussed in the committee, and challenges in developing human resources with a global mindset were written in the report summarizing the activities conducted in the following two years. This report was compiled focusing on the efforts in respective sites made during a period of two years from 2013 to 2014 by the local teams that were set up in accordance with the situation of the R and D centers hosting a number of foreign researchers, etc. based on the above-mentioned recommendations. (author)

  10. Comprehensive human resources development program for nuclear power at NuTEC/JAEA

    Ishimura, T.

    2010-03-01

    Nuclear Technology and Education Center (NuTEC) of the Japan Atomic Energy Agency (JAEA) aims at comprehensive nuclear education and training activities, which cover 1) education and training for national nuclear engineers, 2) cooperation with universities and 3) international contribution and cooperation. The main feature of NuTEC's training programs is that the curricula place emphasis on the laboratory exercises with well-equipped training facilities, including research reacotrs, and expertise of lecturers mostly from JAEA. The wide spectrum of cooperative activities have been pursued with universities and also with international organizations, such as IAEA, ENEN, CEA/INSTN and FNCA countries. The present paper descrives the overall HRD activities of NuTEC, especially in nuclear power field. (author)

  11. FRENDY: A new nuclear data processing system being developed at JAEA

    Tada Kenichi

    2017-01-01

    Full Text Available JAEA has provided an evaluated nuclear data library JENDL and nuclear application codes such as MARBLE, SRAC, MVP and PHITS. These domestic codes have been widely used in many universities and industrial companies in Japan. However, we sometimes find problems in imported processing systems and need to revise them when the new JENDL is released. To overcome such problems and immediately process the nuclear data when it is released, JAEA started developing a new nuclear data processing system, FRENDY in 2013. This paper describes the outline of the development of FRENDY and both its capabilities and performances by the analyses of criticality experiments. The verification results indicate that FRENDY properly generates ACE files.

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

    Nishio, Katsuhisa; Tsukada, Kazuaki; Koura, Hiroyuki

    2014-03-01

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

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

    Matsuda, Makoto; Takeuchi, Suehiro

    2010-12-01

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

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

    Matsuda, Makoto; Takeuchi, Suehiro

    2011-12-01

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

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

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

    2016-12-01

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

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

    Nagame, Yuichiro; Chiba, Satoshi; Mitsuoka, Shinichi

    2009-11-01

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

  17. Comprehensive Human Resources Development Program for Nuclear Power at NuTEC/JAEA

    Ishimura, T.

    2012-01-01

    Nuclear Technology and Education Center (NuTEC) of the Japan Atomic Energy Agency (JAEA) aims at comprehensive nuclear education and training activities, which cover 1) education and training for national nuclear engineers, 2) cooperation with universities and 3) international contribution and cooperation. The main feature of NuTEC's training programs is that the curricula place emphasis on the laboratory exercises with well-equipped training facilities, including research reacotrs, and expertise of lecturers mostly from JAEA. The wide spectrum of cooperative activities have been pursued with universities and also with international organizations, such as IAEA, ENEN, CEA/INSTN and FNCA countries. The present paper descrives the overall HRD activities of NuTEC, especially in nuclear power field. (author)

  18. Operational status of the JAEA-MUTSU tandetron AMS 2008-2009

    Kabuto, Shoji; Kinoshita, Naoki; Tanaka, Takayuki; Yamamoto, Nobuo

    2010-01-01

    A Tandetron Accelerator Mass Spectrometer (AMS) manufactured by High Voltage Engineering Europa in Netherlands had been set up at the Mutsu office of Aomori Research and Development Center, Japan Atomic Energy Agency (JAEA) in 1997. This AMS features 3MV Tandetron accelerator and two independence beamlines for 14 C and 129 I measurement. This AMS has measured both internal and external JAEA researcher's samples based on an open door policy since April 2006. Furthermore, the total operation time of this AMS from the routine operation started exceeds more than 20,000 hours in this year. In this report, we describe not only the summary of the current status and troubles from the previous symposium but also the upgrading of the operation system in this AMS which is carried out from June to July in 2009. (author)

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

    Nishio, Katsuhisa; Tsukada, Kazuaki; Koura, Hiroyuki

    2014-04-01

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

  20. Remote monitoring technologies and applications. JAEA-SNL technical cooperation experience in RM for nuclear transparency

    Matter, John

    2006-01-01

    In ten years of remote monitoring cooperation, Sandia National Laboratories (SNL) and the JAEA (formerly JNC) have developed technology and demonstrated it at the Joyo Experimental Reactor. The program goals were to develop technology to support international safeguards, help evaluate and standardize the technologies for safeguards uses, and demonstrate them for potential regional cooperation. This paper described three generations of remote monitoring systems at the Joyo Fresh Storage and at one of the Joyo Spent Fuel Ponds. Communications and control methods within the facility and between the facility and the remote viewer have changed rapidly. The current configuration is similar to an international safeguards installation, but provides a foundation for transparency cooperation between the JAEA and SNL. Plans to expand this cooperation to other partners are noted. (author)

  1. JAEA's efforts for regional transparency in the area of nuclear nonproliferation

    Hoffheins, Barbara; Kawakubo, Yoko; Inoue, Naoko

    2014-03-01

    The Japan Atomic Energy Agency (JAEA) has undertaken a joint R and D project with the US Department of Energy's National Nuclear Security Administration (DOE/NNSA) for the purposes of developing an Information Sharing Framework (ISF) for regional nonproliferation cooperation since July 2011. This project builds on nearly twenty years of technical cooperation between JAEA, its predecessor organizations and the DOE including the activities to define, develop and test transparency technologies and other multilateral efforts. The objective of current project is to design a viable information sharing process to support the goals of building confidence in the peaceful nature of regional nuclear programs. At the end of a two-year-effort, project partners, JAEA and Sandia National Laboratories (SNL), have defined the comprehensive requirements for an ISF that will ensure nonproliferation transparency success and sustainability. In October 2011, a parallel project with the similar title and objective was launched under the arrangement between the US DOE/NNSA and the Republic of Korea Ministry of Education, Science and Technology (MEST). Since then, JAEA, SNL, the Korea Institute for Nuclear Nonproliferation and Control (KINAC) and Korea Atomic Energy Institute (KAERI) have jointly carried out the project in a form of informal, multilateral cooperation. The project partners have identified needs and audience for ISF, and initiated the discussion to develop requirements for ISF through workshops, meetings, regular telephone conferences, etc. The activities include conducting a survey to identify stakeholders' needs and requirements for an ISF, launching a website to practice information sharing concepts, and presenting papers. This paper provides the historical context of the current project to establish ISF, and reports the progress to date and speculates on future directions. (author)

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

    Ryu, Woo-Seog; Ishihara, Masahiro

    2008-12-01

    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 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.)

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

    2006-05-01

    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.)

  4. Annual report of Fusion Research and Development Directorate of JAEA for FY2008 and FY2009

    Isei, Nobuaki

    2011-03-01

    This annual report provides an overview of major results and progress on research and development (R and D) activities at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) for FY2008 (from April 1, 2008 to March 31, 2009) and FY2009 (from April 1, 2009 to March 31, 2010), including those performed in collaboration with other research establishments of JAEA, research institutes, and universities. Concerning the ITER project, JAEA was nominated as the domestic agency by the Japanese government after the ITER Agreement took effect, and has fulfilled the obligations. In the development of superconducting conductors, JAEA constructed a technical platform for the fabrication of superconducting conductors for toroidal field (TF) coils ahead of other countries. JAEA immediately started and completed the construction of a plant to fabricate superconducting conductors, and started their fabrication ahead of other countries. In the development of gyrotron high-frequency heating equipment, since only the JAEA satisfies the ITER's procurement specifications among supplier countries, the ITER Organization requested JAEA to conduct confidence tests, and achieved results such as data acquisition that could contribute to the development of the ITER's operational scenario. For the development of neutral beam injectors, advantages of the multi-stage acceleration system developed by JAEA was recognized as a result of comparative experiments with single-stage acceleration systems developed in Europe for the particle acceleration system, and was adopted in the ITER's technical specifications. For the Broader Approach (BA) activities, JAEA was designated as the implementing agency by the Japanese government after the BA Agreement took effect, and has fulfilled the obligations and promoted three projects in the BA activities steadily through domestic cooperation and coordination with Europe. Concerning activities related to the International Fusion Energy

  5. Overview of R and D activities on tritium processing and handling technology in JAEA

    Yamanishi, Toshihiko, E-mail: yamanishi.toshihiko@jaea.go.jp [Japan Atomic Energy Agency, Tokai, Ibaraki 319-1195 (Japan); Nakamura, Hirofumi; Kawamura, Yoshinori; Iwai, Yasunori; Isobe, Kanetsugu; Oyaidsu, Makoto; Yamada, Masayuki; Suzuki, Takumi; Hayashi, Takumi [Japan Atomic Energy Agency, Tokai, Ibaraki 319-1195 (Japan)

    2012-08-15

    Highlights: Black-Right-Pointing-Pointer The tritium technologies have been studied at Tritium Process Laboratory of JAEA. Black-Right-Pointing-Pointer A monitoring method for the blanket system of a fusion reactor have been studied. Black-Right-Pointing-Pointer Basic studies on the tritium behavior in confinement system have been carried out. Black-Right-Pointing-Pointer Studies on the detritiation have been carried out as another significant activity. - Abstract: In JAEA, the tritium processing and handling technologies have been studied at TPL (Tritium Process Laboratory). The main R and D activities are: the tritium processing technology for the blanket recovery systems; the basic tritium behavior in confinement materials; and detritiation and decontamination. The R and D activities on tritium processing and handling technologies for a demonstration reactor (DEMO) are also planned to be carried out in the broader approach (BA) program by JAEA with Japanese universities. The ceramic proton conductor has been studied as a possible tritium processing method for the blanket system. The BIXS method has also been studied as a monitoring of tritium in the blanket system. The hydrogen transfer behavior from water to metal has been studied as a function of temperature. As for the behavior of high concentration tritium water, it was observed that the formation of the oxidized layer was prevented by the presence of tritium in water (0.23 GBq/cc). A new hydrophobic catalyst has been developed for the conversion of tritium to water. The catalyst could convert tritium to water at room temperature. A new Nafion membrane has also been developed by gamma ray irradiation to get the strong durability for tritium.

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

    Ishii, Tetsuro; Osa, Akihiko

    2009-04-01

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

  7. Collaboration between SCK·CEN and JAEA for partitioning and transmutation through accelerator-driven system

    2017-03-01

    This technical report reviews Research and Development (R and D) programs for the Partitioning and Transmutation (P and T) technology through Accelerator-Driven System (ADS) at Studiecentrum voor Kernenergie/Centre d'Etude de l'Énergie Nucléaire (SCK·CEN) and Japan Atomic Energy Agency (JAEA). The results obtained in the present Collaboration Arrangement between the two organizations for the ADS are also summarized, and possible further collaborations and mutual realizations in the future are sketched. (author)

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

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

    2006-09-01

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

  9. Site Characterization and Preliminary Performance Assessment Calculation Applied To JAEA-Horonobe URL Site of Japan

    Lim, Doo Hyun; Hatanaka, Koichiro; Ishii, Eiichi

    2010-01-01

    JAEA-Horonobe Underground Research Laboratory (URL) is designed for research and development on high-level radioactive waste (HLW) repository in sedimentary rock. For a potential HLW repository, understanding and implementing fracturing and faulting system, with data from the site characterization, into the performance assessment is essential because fracture and fault will be the major conductors or barriers for the groundwater flow and radionuclide release. The objectives are i) quantitative derivation of characteristics and correlation of fracturing/faulting system with geologic and geophysics data obtained from the site characterization, and ii) preliminary performance assessment calculation with characterized site information

  10. Site Characterization and Preliminary Performance Assessment Calculation Applied To JAEA-Horonobe URL Site of Japan

    Lim, Doo Hyun [NE Union Hill Road, Suite 200, WA 98052 (United States); Hatanaka, Koichiro; Ishii, Eiichi [Japan Atomic Energy Agency, Hokkaido (Japan)

    2010-10-15

    JAEA-Horonobe Underground Research Laboratory (URL) is designed for research and development on high-level radioactive waste (HLW) repository in sedimentary rock. For a potential HLW repository, understanding and implementing fracturing and faulting system, with data from the site characterization, into the performance assessment is essential because fracture and fault will be the major conductors or barriers for the groundwater flow and radionuclide release. The objectives are i) quantitative derivation of characteristics and correlation of fracturing/faulting system with geologic and geophysics data obtained from the site characterization, and ii) preliminary performance assessment calculation with characterized site information

  11. The first Studsvik AB - JAEA meeting for cooperation in nuclear energy research and development

    Ishihara, Masahiro; Yanagihara, Satoshi; Karlsson, Mikael; Stenmark, Anders

    2009-01-01

    Based on the implemental agreement between the Studsvik AB and the Japan Atomic Energy Agency (JAEA) for cooperation in nuclear energy research and development, the first annual meeting was held at Oarai Research and Development Center, Japan Atomic Energy Agency. In this meeting, information exchange on two cooperation areas, 'Radioactive waste treatment technology including recycling of materials' and 'Technical developments for the neutron irradiation experiments in materials testing reactors', was carried out, and future plan in cooperation was discussed. This report describes contents of information exchange and discussions in two cooperation areas. (author)

  12. Technical report on the project for improving the JAEA's enterprise resource planning system

    Kimura, Hideo; Aoyagi, Tetsuo; Sato, Taiichi; Sakai, Manabu; Suzuki, Hitoshi; Tsuji, Minoru; Hikasa, Naoki

    2011-09-01

    The financial accounting and contract management system of JAEA, built on a commercial ERP package, had suffered from serious problems of high lifecycle cost, poor response, and lack of extensibility, due to the too much customization to the ERP package, and disorganized software structure. To solve those problems, three approaches were applied; 1) conducting thorough analysis of business flow and fit/gap under the cooperation of users and system engineers, which enabled removing all customization brought to the ERP package; 2) dividing the system into subsystems each of which corresponds to a business unit, and clearly defining interfaces between the subsystems with international standards, which increases the transparency, extensibility and performance of the system; 3) outsourcing the development of the subsystems to multiple venders to reduce the development cost and controlling the risk of multiple outsourcing with a project management method used successfully in the very large R and D project in JAEA for developing JT60, a fusion plasma research facility. Those approaches can be useful for developing business information systems using commercial software to save time and cost, while meeting the unique requirements of an organization. (author)

  13. Benchmark experiment on molybdenum with graphite by using DT neutrons at JAEA/FNS

    Ohta, Masayuki, E-mail: ohta.masayuki@qst.go.jp [National Institutes for Quantum and Radiological Science and Technology, 2-166 Oaza-Obuchi-Aza-Omotedate, Rokkasho-mura, Kamikita-gun, Aomori (Japan); Kwon, Saerom; Sato, Satoshi [National Institutes for Quantum and Radiological Science and Technology, 2-166 Oaza-Obuchi-Aza-Omotedate, Rokkasho-mura, Kamikita-gun, Aomori (Japan); Konno, Chikara [Japan Atomic Energy Agency, 2-4 Shirakata-Shirane, Tokai-mura, Naka-gun, Ibaraki (Japan); Ochiai, Kentaro [National Institutes for Quantum and Radiological Science and Technology, 2-166 Oaza-Obuchi-Aza-Omotedate, Rokkasho-mura, Kamikita-gun, Aomori (Japan)

    2017-01-15

    Highlights: • A new benchmark experiment on molybdenum was conducted with DT neutron at JAEA/FNS. • Dosimetry reaction and fission rates were measured in the molybdenum assembly. • Calculated results with MCNP5 code were compared with the measured ones. • A problem on the capture cross section data of molybdenum was pointed out. - Abstract: In our previous benchmark experiment on Mo at JAEA/FNS, we found problems of the (n,2n) and (n,γ) reaction cross sections of Mo in JENDL-4.0 above a few hundred eV. We perform a new benchmark experiment on Mo with a Mo assembly covered with graphite and Li{sub 2}O blocks in order to validate the nuclear data of Mo in lower energy region than in the previous experiment. Several dosimetry reaction and fission rates are measured and compared with calculated ones with the MCNP5-1.40 code and the recent nuclear data libraries, ENDF/B-VII.1, JEFF-3.2, and JENDL-4.0. It is suggested that the (n,γ) reaction cross section of {sup 95}Mo should be larger in the tail region below the large resonance of 45 eV in these nuclear data libraries.

  14. Present status and future plan of development on National Nuclear Forensics Library at JAEA

    Kimura, Yoshiki; Shinohara, Nobuo; Funatake, Yoshio; Sato, Kaneaki; Toda, Nobufumi; Shinoda, Yoshiharu; Watahiki, Masaru; Kuno, Yusuke

    2013-01-01

    Japan Atomic Energy Agency (JAEA) has initiated R and D project on nuclear forensics technology such as analytical technologies towards the establishment of nuclear forensics capabilities in Japan. National Nuclear Forensics Library (NNFL) is one of the fundamental nuclear forensics capabilities and a prototype NNFL has been developed as one topic of the R and D project at JAEA. Main objective of NNFL is to determine whether a seized nuclear or other radioactive material from nuclear security event (e.g. illicit trafficking) is originated from one's country or not. Analytical data of the seized material are compared with the existing materials populated in a NNFL, and its attributions such as origin and history will be identified. This paper describes the current status and future plan on the development of prototype NNFL. The outline and the results of the participation in an international table top exercise on NNFL named 'Galaxy Serpent' are also reported in the present paper. (author)

  15. Progress on multi-nuclide AMS of JAEA-AMS-TONO

    Saito-Kokubu, Yoko; Matsubara, Akihiro; Miyake, Masayasu; Nishizawa, Akimitsu; Ohwaki, Yoshio; Nishio, Tomohiro; Sanada, Katsuki; Hanaki, Tatsumi

    2015-10-01

    The JAEA-AMS-TONO (Japan Atomic Energy Agency's Accelerator Mass Spectrometer established at the Tono Geoscience Center) facility has been used for the dating of geological samples. The AMS system is versatile, based on a 5 MV tandem Pelletron-type accelerator. Since its establishment in 1997, the AMS system has been used for measurement of carbon-14 (14C) mainly for 14C dating studies in neotectonics and hydrogeology, in support of JAEA's research on geosphere stability applicable to the long-term isolation of high-level radioactive waste. Results of the measurement of 14C in soils and plants has been applied to the dating of fault activity and volcanism. Development of beryllium-10 (10Be) and aluminum-26 (26Al) AMS systems are now underway to enhance the capability of the multi-nuclide AMS in studies of dating by cosmogenic nuclides. The 10Be-AMS system has already been used for routine measurements in applied studies and improvements of the measurement technique have been made. Now we plan to fine tune the system and perform test measurements to develop the 26Al-AMS system.

  16. Activities of JAEA in the International Science and Technology Center (ISTC)

    Hamada, Shozo

    2013-05-01

    Since the Headquarter of the International Science and Technology Center (ISTC) was established in Moscow, Russian Federation in 1994, Japan Atomic Energy Agency (JAEA), which includes both Japan Atomic Energy Research Institute and Japan has been made various, considerable contributions as well as participation in partner projects in ISTC activities. By the way, the Russian Federation Party, which is a Government Board Member of ISTC, made the statement that the Russian Federation would withdraw from ISTC until the end of 2015 in the 52th Government Board in held Moscow, 9 December 2010. This is based on the possible consequences of the Executive Order of the President of the Russian Federation dated 11 August 2010 with respect to the withdraw of the Russian Federation from ISTC. So that the Government Board has been discussing about the continuation and/or the establishment of a new organization for ISTC. In any case, the Headquarter of ISTC could stay at Moscow until the end of 2015 at latest. This time is considered as a transition period of ISTC and it is summarized that the collaborations, contributions of JAEA and outcomes from them for ISTC activities in this report. (author)

  17. Education and training for nuclear scientists and engineers at NuTEC/JAEA

    Kushita, Kouhei; Sugimoto, Jun; Sakamoto, Ryuichi; Arai, Nobuyoshi; Hattori, Takamitsu; Matsuda, Kenji; Ikuta, Yuko; Sato, K.

    2009-01-01

    Because of the increasing demand of nuclear engineers in recent years, which is sometimes called as the age of nuclear Renaissance, while nuclear engineers have been decreasing and technical knowledge and expertise have not necessarily been transferred to the younger generations, human resources development (HRD) has been regarded as one of the most important issues in the nuclear field in Japan as well as in the world. Nuclear Technology and Education Center (NuTEC) at Japan Atomic Energy Agency (JAEA) have conducted comprehensive nuclear education and training activities in the past half century, which cover; 1) education and training for domestic nuclear engineers, 2) cooperation with universities, and 3) international cooperation. The main feature of NuTEC's training programs is that emphasis is placed on the laboratory exercise with well-equipped training facilities and expertise of lecturers mostly from JAEA. The wide spectrum of cooperative activities have been pursued with universities, which includes newly developed remote-education system, and also with international organizations, such as with FNCA countries and IAEA. For the nuclear education and trainings, utilization of nuclear reactors is of special importance. Examples of training programs using nuclear reactors are reported. Future plan to use nuclear reactors such as JMTR for the nuclear educations is also introduced. (author)

  18. Outcome of cooperative program between JAEA and US DOE on decommissioning

    Shimada, Taro; Shiraishi, Kunio; Tachibana, Mitsuo; Ishigami, Tsutomu

    2009-07-01

    The Japan Atomic Energy Agency (JAEA: the former Japan Atomic Energy Research Institute) has been collecting wide variety of information on decommissioning nuclear facilities by the cooperative program with US Department of Energy (DOE) since 1988. In the course of the cooperation, the cooperative program has continued under the newly established specific memorandum in the field of decontamination and decommissioning nuclear facilities since 2001 on the framework agreement of USDOE and JAERI. On the other hand, the US DOE environmental management program, which was initiated in 1989, has developed resulting in achievement of dismantlement and decontamination and cleanup of nuclear facilities mainly used for Manhattan project and demonstration of various technologies developed for this program. In the cooperative activities, information on decommissioning activities including innovated technology developments has been exchanged with CP-5 and Mound plant as designated main facilities of DOE, and with JRR-2 and the reprocessing test facility of JAERI. The experiences and technologies applied in the environmental management program are expected to contribute to planning and implementing decommissioning nuclear facilities in JAEA. This report describes the summary of the information on decommissioning activities and technology development and deployment of the environmental management program in DOE obtained through the cooperation under the specific memorandum agreement. (author)

  19. Integral experiment on molybdenum with DT neutrons at JAEA/FNS

    Ohta, Masayuki, E-mail: ohta.masayuki@jaea.go.jp; Sato, Satoshi; Kwon, Saerom; Ochiai, Kentaro; Konno, Chikara

    2016-11-01

    Highlights: • An integral experiment on molybdenum was conducted with DT neutron at JAEA/FNS. • The experimental results were analyzed by MCNP5 with recent nuclear data libraries. • The calculated results generally show underestimation. • Problems on recent nuclear data of molybdenum were discussed. - Abstract: An integral experiment on molybdenum is performed with a DT neutron source at JAEA/FNS. A Mo assembly is covered with lithium oxide blocks in order to reduce background neutrons inside the assembly. Several reaction rates and fission rates are measured along the central axis inside the assembly and compared with calculated ones with the Monte Carlo transport code MCNP5-1.40 and recent nuclear data libraries of ENDF/B-VII.1, JENDL-4.0, and JEFF-3.2. The calculated results generally show underestimation. From our detailed analysis, it is concluded that the (n,2n) cross section data of all the Mo stable isotopes in JEFF-3.2 are more suitable than those in JENDL-4.0 and the (n,γ) cross section data of {sup 92}Mo, {sup 94}Mo, {sup 95}Mo, {sup 96}Mo, {sup 97}Mo, and {sup 100}Mo in JENDL-4.0 are overestimated.

  20. Visualization environment of the large-scale data of JAEA's supercomputer system

    Sakamoto, Kensaku [Japan Atomic Energy Agency, Center for Computational Science and e-Systems, Tokai, Ibaraki (Japan); Hoshi, Yoshiyuki [Research Organization for Information Science and Technology (RIST), Tokai, Ibaraki (Japan)

    2013-11-15

    On research and development of various fields of nuclear energy, visualization of calculated data is especially useful to understand the result of simulation in an intuitive way. Many researchers who run simulations on the supercomputer in Japan Atomic Energy Agency (JAEA) are used to transfer calculated data files from the supercomputer to their local PCs for visualization. In recent years, as the size of calculated data has gotten larger with improvement of supercomputer performance, reduction of visualization processing time as well as efficient use of JAEA network is being required. As a solution, we introduced a remote visualization system which has abilities to utilize parallel processors on the supercomputer and to reduce the usage of network resources by transferring data of intermediate visualization process. This paper reports a study on the performance of image processing with the remote visualization system. The visualization processing time is measured and the influence of network speed is evaluated by varying the drawing mode, the size of visualization data and the number of processors. Based on this study, a guideline for using the remote visualization system is provided to show how the system can be used effectively. An upgrade policy of the next system is also shown. (author)

  1. Mid-Term Direction of JAEA Nuclear Fuel Cycle Engineering Laboratories

    Ojima, H.; Sugiyama, T.; Tanaka, K.; Takeda, S.; Nomura, S.

    2009-01-01

    1. Introduction Nuclear Fuel Cycle Engineering Laboratories (NCL) of Japan Atomic Energy Agency (JAEA) has sufficient experience and ability through its 50 year operation to establish the next generation closed cycle. It strives to become a world-class Center Of Excellence. 2. Current activity in NCL: 1) - Recycling of MOX fuel: The Tokai Reprocessing Plant has reprocessed 29 tons of MOX fuel from the ATR Fugenh as a part of 1140 tons of cumulative spent fuel reprocessed. JAEA has supported the pre-operation of the Rokkasho Reprocessing Plant. An innovative MOX pellet fabrication process has been developed in the Plutonium Fuel Development Center, and a part of products obtained by the development are used as a fuel for core confirmation test for re-startup of the FBR Monjuh. Characterization of MOX containing Am and Np has been studied and a new data such as melting point and thermal conductivity were reported. In the Chemical Processing Facility, a hot lab., an advanced aqueous reprocessing technology has been tested for TRU recovery, economical improvement, etc., using irradiated MOX fuel from the FR Joyoh. 2) - Supporting Activity: JAEA has improved the effectiveness and efficiency of existing safeguards activities. The Integrated Safeguards approach for all facilities in NCL has been implemented since August, 2008, as a pioneer and a good example in the world. To reduce anxiety among local residents, NCL has explained its operation plans and exchanged information and opinions with them concerning potential risks to health and environment. Recently, stake-holder participation in the management of NCL was started from the view point of Corporate Social Responsibility. In April, 2008, the agreement was signed with Idaho National Laboratory for cooperation of personnel training in fuel cycle area. 3. Mid-Term Direction: In Japan, feasibility and direction of the transition period from the LWR era to the FBR era should be discussed for the next several years. Study

  2. Mid-Term Direction of JAEA Nuclear Fuel Cycle Engineering Laboratories

    Ojima, H.; Sugiyama, T.; Tanaka, K.; Takeda, S.; Nomura, S. [Tokai-mura, Ibaraki-ken 319-1194 (Japan)

    2009-06-15

    1. Introduction Nuclear Fuel Cycle Engineering Laboratories (NCL) of Japan Atomic Energy Agency (JAEA) has sufficient experience and ability through its 50 year operation to establish the next generation closed cycle. It strives to become a world-class Center Of Excellence. 2. Current activity in NCL: 1) - Recycling of MOX fuel: The Tokai Reprocessing Plant has reprocessed 29 tons of MOX fuel from the ATR Fugenh as a part of 1140 tons of cumulative spent fuel reprocessed. JAEA has supported the pre-operation of the Rokkasho Reprocessing Plant. An innovative MOX pellet fabrication process has been developed in the Plutonium Fuel Development Center, and a part of products obtained by the development are used as a fuel for core confirmation test for re-startup of the FBR Monjuh. Characterization of MOX containing Am and Np has been studied and a new data such as melting point and thermal conductivity were reported. In the Chemical Processing Facility, a hot lab., an advanced aqueous reprocessing technology has been tested for TRU recovery, economical improvement, etc., using irradiated MOX fuel from the FR Joyoh. 2) - Supporting Activity: JAEA has improved the effectiveness and efficiency of existing safeguards activities. The Integrated Safeguards approach for all facilities in NCL has been implemented since August, 2008, as a pioneer and a good example in the world. To reduce anxiety among local residents, NCL has explained its operation plans and exchanged information and opinions with them concerning potential risks to health and environment. Recently, stake-holder participation in the management of NCL was started from the view point of Corporate Social Responsibility. In April, 2008, the agreement was signed with Idaho National Laboratory for cooperation of personnel training in fuel cycle area. 3. Mid-Term Direction: In Japan, feasibility and direction of the transition period from the LWR era to the FBR era should be discussed for the next several years. Study

  3. JAEA key facilities for global advanced fuel cycle R and D

    Nomura, Shigeo; Yamamoto, Ryuichi [Nuclear Fuel Cycle Engineering Labos, JAEA, 4-33 Tokai-mura, Ibaraki, 319-1194 (Japan)

    2008-07-01

    Advanced fuel cycle will be realized with the mid and long term R and D during the long-term transition period from LWR cycle to advanced reactor fuel cycle. Most of JAEA facilities have been utilized to establish the current LWR and FBR (Fast Breeder Reactor) fuel cycle by implementing evolutionary R and D. An assessment of today's state experimental facilities concerning the following research issues: reprocessing, Mox fuel fabrication, irradiation and post-irradiation examination, waste management and nuclear data measurement, is made. The revolutionary R and D requests new issues to be studied: the TRU multi-recycling, minor actinide recycling, the assessment of proliferation resistance and the assessment of cost reduction. To implement the revolutionary R and D for advanced fuel cycle, however, these facilities should be refurbished to install new machines and process equipment to provide more flexible testing parameters.

  4. Development of system technology for routine 10Be measurement in the JAEA-AMS-TONO

    Matsubara, Akihiro; Saito-Kokubu, Yoko; Ishimaru, Tsuneari; Nishizawa, A.; Miyake, M.

    2013-01-01

    We have completed the development of system technology for routine 10 Be measurement with the 5 MV Pelletron system in the Tono Geoscience Center of Japan Atomic Energy Agency (JAEA). The function of separating 10 Be and 10 B provided in the gas cell set in the front of an ionization chamber was experimentally confirmed through observation of variation of ΔE 1 -E Res spectrum with the gas pressure of the gas cell. The test measurement with beryllium samples of an ice core shows that measured 10 Be/ 9 Be ratios were consistent with the values obtained by the group of the Micro Analysis Laboratory, Tandem accelerator (MALT) in the University of Tokyo. (author)

  5. R and D of atmosphere detritiation system for ITER in JAEA

    Hayashi, Takumi, E-mail: hayashi.takumi@jaea.go.jp [Tritium Technol. Gr.: Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki Pref. 319-1195 (Japan); Iwai, Yasunori; Kobayashi, Kazuhiro; Nakamura, Hirofumi; Yamanishi, Toshihiko [Tritium Technol. Gr.: Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki Pref. 319-1195 (Japan); Perevezentsev, Alexander [Tritium Plant Gr.: ITER Organization, Cadarache Site (France)

    2010-12-15

    In order to establish an effective ITER atmosphere detritiation system (DS), JAEA (Japan Atomic Energy Agency) has investigated the performance and the durability of the system at various incident/accident conditions in support of finalizing the DS conceptual design through the ITER design review. The current DS as the Safety Important Component (SIC) has been discussed and mainly consists of catalytic reactors, wet scrubber columns (SCs), and blowers. The functional failure of the DS designed with SC was evaluated using a database of failure experiences of various valves, controllers, and components. Regarding the tritium release into the biggest confinement sector of the Tokamak gallery, this design is improved by more than two orders of magnitude compared to the original DS designed with molecular sieves (MSs) dryer beds in the 2001 design report. This improvement is achieved mainly by the reduction of frequency of valve operation, like MS dryers requiring periodical regeneration, and by the standardized module arrangement of the DS with SC.

  6. Status of decommissioning and waste management in the Nuclear Science Research Institute of JAEA

    Okoshi, Minoru; Yamashita, Toshiyuki

    2007-01-01

    The Nuclear Science Research Institute (NSRI) of JAEA has some experiences of the decommissioning of research reactors and research laboratories including a reprocessing test facility. In order to dismantle those facilities safely, we paid much attention for the radiological protection of radiation workers taking into consideration of characteristics of each facility, especially to protect internal exposures. As the results of decommissioning activities, several thousands tons of solid radioactive wastes were generated. In the near future, we will start the treatment of these stored wastes by a super compactor, metal melting furnace and non-metal waste melting furnace to gain high volume reduction and to prepare stable waste forms for final disposal. In Japan, the clearance system was established in 2005 by amending the Nuclear Regulatory Law. The NSRI plans to release very slightly contaminated concrete debris for recycling, which was generated from the replacement of reactor core of research reactor (JRR-3), according to the clearance system. (author)

  7. Recent developments of JAEA's Monte Carlo Code MVP for reactor physics applications

    Nagaya, Y.; Okumura, K.; Mori, T.

    2013-01-01

    MVP is a general-purpose continuous-energy Monte Carlo code for neutron and photon transport calculations that has been developed since the late 1980's at Japan Atomic Energy Agency (JAEA, formerly JAERI). The MVP code is designed for nuclear reactor applications such as reactor core design/analysis, criticality safety and reactor shielding. This paper describes the MVP code and present its latest developments. Among the new capabilities of MVP we find: -) the perturbation method has been implemented for the change in k(eff); -) the eigenvalue calculations can be performed with an explicit treatment of delayed neutrons in which their fission spectra are taken into account; -) the capability of tallying the scattering matrix (group-to-group scattering cross sections); -) the implementation of an exact model for resonance elastic scattering; and -) a Monte Carlo perturbation technique is used to calculate reactor kinetics parameters

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

    2008-01-01

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

  9. Conference on development of JAEA knowledge management system, 2010 (Conference report)

    Notoya, Shin; Sasao, Eiji; Ota, Kunio; Shimizu, Kazuhiko

    2010-11-01

    In March 2010, a prototype of 'next generation' knowledge management system (KMS) and a status report (CoolRep H22) synthesizing the R and D results were made publicly available at the conclusion of R and D for the first Midterm Plan (October 2005 to March 2010). This could further reinforce the technical knowledge base and thus enable the geological disposal project and associated safety regulations to be continuously supported. The conference on 'Development of JAEA Knowledge Management System, 2010' was held on 16th June 2010 in Tokyo, with main aims of introducing KMS and CoolRep H22 to broader stakeholders, promoting their understanding and having input from them for further improvement of KMS. This report compiles presentation materials and comments to KMS and CoolRep H22 from participants. (author)

  10. A Review of Fusion and Tokamak Research Towards Steady-State Operation: A JAEA Contribution

    Mitsuru Kikuchi

    2010-11-01

    Full Text Available Providing a historical overview of 50 years of fusion research, a review of the fundamentals and concepts of fusion and research efforts towards the implementation of a steady state tokamak reactor is presented. In 1990, a steady-state tokamak reactor (SSTR best utilizing the bootstrap current was developed. Since then, significant efforts have been made in major tokamaks, including JT-60U, exploring advanced regimes relevant to the steady state operation of tokamaks. In this paper, the fundamentals of fusion and plasma confinement, and the concepts and research on current drive and MHD stability of advanced tokamaks towards realization of a steady-state tokamak reactor are reviewed, with an emphasis on the contributions of the JAEA. Finally, a view of fusion energy utilization in the 21st century is introduced.

  11. The second Studsvik AB - JAEA meeting for cooperation in nuclear energy research and development

    Ishihara, Masahiro; Yanagihara, Satoshi; Karlsson, Mikael; Stenmark, Anders

    2010-03-01

    The second annual meeting was held at Studsvik AB in Sweden to exchange information on radioactive waste treatment technology including recycling of materials and technical developments for the neutron irradiation experiments in materials testing reactors. The information exchange meeting was held on the basis of the implemental agreement between the Studsvik AB and the Japan Atomic Energy Agency (JAEA) for cooperation in nuclear energy research and development. The major items of the information exchange were the present status of waste treatment in both organizations including acceptance criteria of wastes in Studsvik facilities, experience and current status of RI production technology in both organizations as well as the sensor development. The future plan in cooperative program was also discussed. This report describes contents of the information exchange and discussions in two cooperation areas. (author)

  12. Outlines of JAEA's instructor training program and future prospects

    Hidaka, Akihide; Nakamura, Kazuyuki; Watanabe, Yoko; Yabuuchi, Yukiko; Arai, Nobuyoshi; Sawada, Makoto; Yamashita, Kiyonobu; Sawai, Tomotsugu; Murakami, Hiroyuki

    2015-01-01

    Nuclear Human Resource Development Center (NuHRDeC) of JAEA has conducted nuclear human resource development for more than 50 years since its establishment in 1958. NuHRDeC conducts international nuclear human resource development, so called “Instructor Training Program (ITP)”, which is a training scheme launched in 1996 in order to support Asian countries seeking peaceful use of nuclear energy. The ITP consists of 1) Instructor Training Course (ITC) in Japan, 2) Follow-up Training Course (FTC) in own countries organized by instructors trained at ITC in Japan, and 3) Nuclear Technology Seminar for bringing up nuclear trainers and leaders in Asian countries. The purpose of ITP is to develop a self-sustainable training system in Asian countries, which disseminates the knowledge and technology in their countries. After completing ITC trainings at NuHRDeC, the trainees are obliged to set up FTC in each country. They create own 1 or 2 weeks course curricula and allocate local lecturers including themselves. Two or three Japanese experts join the FTC to give technical advices and support to local lecturers. The present specialized fields of ITC are 1) Reactor engineering such as reactor physics, thermal engineering and reactor safety, 2) Environmental radioactivity monitoring, and 3) Nuclear emergency preparedness. The main feature of ITC is that the curricula places emphasis on the practical exercise with well-equipped training facilities, experimental laboratories utilizing the simulators of research reactor, and the expertise of lecturers mostly from JAEA. As of FY2014, ITC is applied to 8 countries; Indonesia, Thailand, Vietnam, Bangladesh, Kazakhstan, Malaysia, Philippines and Mongolia. The total number of participants at ITC since 1996 is approximately 300 and the participation of FTC has been increased significantly year after year with more than 3,000 in total. This result indicates that the ITP system has been effectively contributed to fostering local

  13. Summaries of research and development activities by using supercomputer system of JAEA in FY2015. April 1, 2015 - March 31, 2016

    2017-01-01

    Japan Atomic Energy Agency (JAEA) conducts research and development (R and D) in various fields related to nuclear power as a comprehensive institution of nuclear energy R and Ds, and utilizes computational science and technology in many activities. As shown in the fact that about 20 percent of papers published by JAEA are concerned with R and D using computational science, the supercomputer system of JAEA has become an important infrastructure to support computational science and technology. In FY2015, the system was used for R and D aiming to restore Fukushima (nuclear plant decommissioning and environmental restoration) as a priority issue, as well as for JAEA's major projects such as Fast Reactor Cycle System, Fusion R and D and Quantum Beam Science. This report presents a great number of R and D results accomplished by using the system in FY2015, as well as user support, operational records and overviews of the system, and so on. (author)

  14. Summaries of research and development activities by using supercomputer system of JAEA in FY2014. April 1, 2014 - March 31, 2015

    2016-02-01

    Japan Atomic Energy Agency (JAEA) conducts research and development (R and D) in various fields related to nuclear power as a comprehensive institution of nuclear energy R and Ds, and utilizes computational science and technology in many activities. As shown in the fact that about 20 percent of papers published by JAEA are concerned with R and D using computational science, the supercomputer system of JAEA has become an important infrastructure to support computational science and technology. In FY2014, the system was used for R and D aiming to restore Fukushima (nuclear plant decommissioning and environmental restoration) as a priority issue, as well as for JAEA's major projects such as Fast Reactor Cycle System, Fusion R and D and Quantum Beam Science. This report presents a great number of R and D results accomplished by using the system in FY2014, as well as user support, operational records and overviews of the system, and so on. (author)

  15. Summaries of research and development activities by using supercomputer system of JAEA in FY2013. April 1, 2013 - March 31, 2014

    2015-02-01

    Japan Atomic Energy Agency (JAEA) conducts research and development (R and D) in various fields related to nuclear power as a comprehensive institution of nuclear energy R and Ds, and utilizes computational science and technology in many activities. About 20 percent of papers published by JAEA are concerned with R and D using computational science, the supercomputer system of JAEA has become an important infrastructure to support computational science and technology utilization. In FY2013, the system was used not only for JAEA's major projects such as Fast Reactor Cycle System, Fusion R and D and Quantum Beam Science, but also for R and D aiming to restore Fukushima (nuclear plant decommissioning and environmental restoration) as a priority issue. This report presents a great amount of R and D results accomplished by using the system in FY2013, as well as user support, operational records and overviews of the system, and so on. (author)

  16. Summaries of research and development activities by using supercomputer system of JAEA in FY2012. April 1, 2012 - March 31, 2013

    2014-01-01

    Japan Atomic Energy Agency (JAEA) conducts research and development (R and D) in various fields related to nuclear power as a comprehensive institution of nuclear energy R and Ds, and utilizes computational science and technology in many activities. As more than 20 percent of papers published by JAEA are concerned with R and D using computational science, the supercomputer system of JAEA has become an important infrastructure to support computational science and technology utilization. In FY2012, the system was used not only for JAEA's major projects such as Fast Reactor Cycle System, Fusion R and D and Quantum Beam Science, but also for R and D aiming to restore Fukushima (nuclear plant decommissioning and environmental restoration) as apriority issue. This report presents a great amount of R and D results accomplished by using the system in FY2012, as well as user support, operational records and overviews of the system, and so on. (author)

  17. Summaries of research and development activities by using supercomputer system of JAEA in FY2011. April 1, 2011 - March 31, 2012

    2013-01-01

    Japan Atomic Energy Agency (JAEA) conducts research and development (R and D) in various fields related to nuclear power as a comprehensive institution of nuclear energy R and Ds, and utilizes computational science and technology in many activities. As more than 20 percent of papers published by JAEA are concerned with R and D using computational science, the supercomputer system of JAEA has become an important infrastructure to support computational science and technology utilization. In FY2011, the system was used for analyses of the accident at the Fukushima Daiichi Nuclear Power Station and establishment of radioactive decontamination plan, as well as the JAEA's major projects such as Fast Reactor Cycle System, Fusion R and D and Quantum Beam Science. This report presents a great amount of R and D results accomplished by using the system in FY2011, as well as user support structure, operational records and overviews of the system, and so on. (author)

  18. A new integral experiment on copper with DT neutron source at JAEA/FNS

    Kwon, Saerom, E-mail: kwon.saerom@jaea.go.jp; Sato, Satoshi; Ohta, Masayuki; Ochiai, Kentaro; Konno, Chikara

    2016-11-01

    Highlights: • Integral experiment on copper with DT neutron was performed under small influence of background neutrons which were efficiently absorbed in the Li{sub 2}O layers. • The experimental analyses were carried out using MCNP5-1.40 and the recent nuclear data libraries. • The underestimation issue of the reaction rates related to lower energy neutrons is focused on. • The combination of the {sup 63}Cu data in JEFF-3.2 and {sup 65}Cu data in JENDL-4.0 gave the best C/E. • The specific cross section data of copper should be reassessed. - Abstract: In order to validate copper nuclear data, an integral experiment on copper with the DT neutron source at JAEA/FNS had been performed over 20 years ago. The experiment had showed that ratios of the calculated values to the experimental ones (C/Es) related to lower energy neutrons had been drastically smaller than unity. In order to reveal reasons of the small C/Es, we newly performed the integral experiment on copper with the DT neutron source at JAEA/FNS. A quasi-cylindrical copper assembly of 315 mm in radius and 608 mm in depth was covered with Li{sub 2}O blocks of 51 mm in thickness for the front and side parts and 153 mm in thickness for the rear part to exclude background neutrons which might affect the measured data. We measured reaction rates with 5 activation foils and fission rates with 2 micro fission chambers at the center of the assembly. The experiment was analyzed by using MCNP5-1.40 with the recent nuclear data libraries, ENDF/B-VII.1, JEFF-3.2 and JENDL-4.0. As a result, the C/E of the reaction rate of the {sup 197}Au(n,γ){sup 198}Au reaction improved by 10% from the previous result and the combination of the {sup 63}Cu data in JEFF-3.2 and {sup 65}Cu data in JENDL-4.0 increased the C/E by more 10% because of the resonance data of the {sup 63}Cu in JEFF-3.2. Moreover, the calculated result with the {sup 63}Cu data in JEFF-3.2 and {sup 65}Cu data in JENDL-4.0 with 10% larger elastic

  19. Summaries of research and development activities by using JAEA computer system in FY2010. April 1, 2010 - March 31, 2011

    2012-02-01

    Japan Atomic Energy Agency (JAEA) conducts research and development (R and D) in various fields related to nuclear power as a comprehensive institution of nuclear energy R and Ds, and utilizes computational science and technology in many activities. The number of R and D results in JAEA by utilizing computational science and technology increased significantly to more than double in five years. Large computer system has become an important infrastructure to support computational science and technology utilization. In March 2010, Center for Computational Science and e-Systems (CCSE) introduced the nation's largest system and started operations to meet growing demand of calculation. Although the performance of new system is 14 times higher than that of old system, the utilization of new system reached 90% in the first three days, bearing out the strong demand of calculation in JAEA. This report presents a great amount of R and D results accomplished by using the system in its the first year of operation (FY2010), as well as user support structure, operational records and overviews of the system, and so on. (author)

  20. Transient analysis for lead-bismuth-cooled accelerator-driven system proposed by JAEA

    Sugawara, T.; Nishihara, K.; Tsujimoto, K.

    2015-01-01

    It is supposed that an Accelerator-driven System (ADS) is safer than conventional critical reactors since an ADS is driven by the external neutron source in the subcritical state. In this study, the transient analyses for the lead-bismuth cooled ADS proposed by JAEA were performed using the SIMMER-III and RELAP5/mod3.2 codes to investigate the possibility of core damage. In this research, 3 accidents: the protected loss of heat sink, the protected overcooling and the unprotected blockage accident were considered as typical ADS accidents. Through these calculations, it was confirmed that all calculation results, except for the protected loss of heat sink, fulfilled the no-damage criteria. In the protected loss of heat sink, the cladding tube temperature reached its melting temperature after 18-21 hours, although the calculation condition was very conservative. These results have led to requirements to design a safety system of the ADS to decrease the frequencies of accidents. (authors)

  1. Heavy-ion microbeam system at JAEA-Takasaki for microbeam biology

    Funayama, Tomoo; Wada, Seiichi; Yokota, Yuichiro

    2008-01-01

    Research concerning cellular responses to low dose irradiation, radiation-induced bystander effects, and the biological track structure of charged particles has recently received particular attention in the field of radiation biology. Target irradiation employing a microbeam represents a useful means of advancing this research by obviating some of the disadvantages associated with the conventional irradiation strategies. The heavy-ion microbeam system at Japan Atomic Energy Agency (JAEA)-Takasaki, which was planned in 1987 and started in the early 1990's, can provide target irradiation of heavy charged particles to biological material at atmospheric pressure using a minimum beam size 5 μm in diameter. A variety of biological material has been irradiated using this microbeam system including cultured mammalian and higher plant cells, isolated fibers of mouse skeletal muscle, silkworm (Bombyx mori) embryos and larvae, Arabidopsis thaliana roots, and the nematode Caenorhabditis elegans. The system can be applied to the investigation of mechanisms within biological organisms not only in the context of radiation biology, but also in the fields of general biology such as physiology, developmental biology and neurobiology, and should help to establish and contribute to the field of 'microbeam biology'. (author)

  2. Proceedings of the workshops on 'JAEA project researches at J-PARC/MLF'

    Kajimoto, Ryoichi; Maekawa, Fujio; Arima, Hiroshi; Yoshinari, Shizuka; Arai, Masatoshi

    2011-06-01

    The operation for public use of Materials and Life Science Experimental Facility (MLF) at Japan Proton Accelerator Research Complex (J-PARC) has started since the end of 2008. Rather stable neutron and muon beams at 120 kW are being supplied throughout 2010. Some of the instruments have already produced several good scientific outputs. Furthermore, operation at 200 kW, which exceeds the beam power of the ISIS facility in UK, has started since December 2010. In this promising situation for MLF, we hold three workshops for five neutron instruments which conducted researches for projects by Japan Atomic Energy Agency (JAEA) (project researches): 'Workshop on BL19 (Sep. 29)', 'Workshop on BL04+BL10 (Oct. 28)', and 'Workshop on BL01+BL14 (Oct. 29)'. There, status of the instruments and recent results of the project researches as well as a part of researches by general users were reported, and future directions and issues to be solved of the researches were discussed. This report includes abstracts, materials of the presentations and summary of discussions in the workshops. (author)

  3. Progress on multi-nuclide AMS of JAEA-AMS-TONO

    Saito-Kokubu, Yoko, E-mail: kokubu.yoko@jaea.go.jp [Japan Atomic Energy Agency, Toki, Gifu 509-5102 (Japan); Matsubara, Akihiro [Japan Atomic Energy Agency, Toki, Gifu 509-5102 (Japan); Miyake, Masayasu; Nishizawa, Akimitsu; Ohwaki, Yoshio; Nishio, Tomohiro; Sanada, Katsuki [Pesco Corp., Ltd., Toki, Gifu 509-5123 (Japan); Hanaki, Tatsumi [Japan Atomic Energy Agency, Toki, Gifu 509-5102 (Japan)

    2015-10-15

    The JAEA-AMS-TONO (Japan Atomic Energy Agency’s Accelerator Mass Spectrometer established at the Tono Geoscience Center) facility has been used for the dating of geological samples. The AMS system is versatile, based on a 5 MV tandem Pelletron-type accelerator. Since its establishment in 1997, the AMS system has been used for measurement of carbon-14 ({sup 14}C) mainly for {sup 14}C dating studies in neotectonics and hydrogeology, in support of JAEA’s research on geosphere stability applicable to the long-term isolation of high-level radioactive waste. Results of the measurement of {sup 14}C in soils and plants has been applied to the dating of fault activity and volcanism. Development of beryllium-10 ({sup 10}Be) and aluminum-26 ({sup 26}Al) AMS systems are now underway to enhance the capability of the multi-nuclide AMS in studies of dating by cosmogenic nuclides. The {sup 10}Be-AMS system has already been used for routine measurements in applied studies and improvements of the measurement technique have been made. Now we plan to fine tune the system and perform test measurements to develop the {sup 26}Al-AMS system.

  4. Waste handling and storage in the decontamination pilot projects of JAEA for environments of Fukushima

    Nakayama, S.; Kawase, K.; Iijima, K.; Kato, M. [Fukushima Environmental Safety Center, Headquarters of Fukushima Partnership Operations, Japan Atomic Energy Agency, Fukushima (Japan)

    2013-07-01

    After the Fukushima Daiichi nuclear accident, Japan Atomic Energy Agency (JAEA) was chosen by the national government to conduct decontamination pilot projects at selected sites in Fukushima prefecture. Despite tight boundary conditions in terms of timescale and resources, the projects served their primary purpose to develop a knowledge base to support more effective planning and implementation of stepwise regional remediation of the evacuated zone. A range of established, modified and newly developed techniques were tested under realistic field conditions and their performance characteristics were determined. The results of the project can be summarized in terms of site characterization, cleanup and waste management. A range of options were investigated to reduce the volumes of waste produced and to ensure that decontamination water could be cleaned to the extent that it could be discharged to normal drainage. Resultant solid wastes were packaged in standard flexible containers, labelled and stored at the remediation site (temporary storage until central interim storage becomes available). The designs of such temporary storage facilities were tailored to available sites, but all designs included measures to ensure mechanical stability (e.g., filling void spaces between containers with sand, graded cover with soil) and prevent releases to groundwater (impermeable base and cap, gravity flow drainage including radiation monitors and catch tanks). Storage site monitoring was also needed to check that storage structures would not be perturbed by external events that could include typhoons, heavy snowfalls, freeze/thaw cycles and earthquakes. (authors)

  5. Trial operation of the advanced volume reduction facilities for LLW at JAEA

    Nakashio, Nobuyuki; Higuchi, Hidekazu; Momma, Toshiyuki; Kozawa, Kazushige; Touhei, Toshio; Sudou, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Kou; Ishikawa, Joji; Kato, Mitsugu; Sato, Motoaki

    2007-01-01

    The Japan Atomic Energy Agency (JAEA) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level radioactive solid wastes. It will be able to produce waste packages for final disposal and to reduce the volume of stored wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former has cutting installations for large size wastes and the latter has melting units and a super compactor. Cutting installations in the WSRSF have been operating since July 1999. Radioactive wastes treated so far amount to 750 m 3 and the volume reduction ratio is from 1.7 to 3.7. The WVRF has been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation of the pretreatment system in the WVRF with radioactive wastes has partly started in FY2005. (author)

  6. Proceedings of the joint meeting of ultrafast pulse high intensity laser research collaboration and JAEA-KPSI 7th symposium on advanced photon research

    2007-03-01

    The Joint Meeting of Ultrafast Pulse High Intensity Laser Research Collaboration and JAEA-KPSI 7th Symposium on Advanced Photon Research was jointly held at Kansai Photon Research Institute, Japan Atomic Energy Agency (JAEA-KPSI) in Kizu, Kyoto on May 10-12, 2006. This report consists of contributed papers for the speeches and poster presentations including joint research and cooperative research performed in FY2004 and FY2005 with Japan Atomic Energy Research Institute (JAERI). The 47 of the presented papers are indexed individually. (J.P.N.)

  7. Development status on hydrogen production technology using high-temperature gas-cooled reactor at JAEA, Japan

    Shiozawa, Shusaku; Ogawa, Masuro; Hino, Ryutaro

    2006-01-01

    The high-temperature gas-cooled reactor (HTGR), which is graphite-moderated and helium-cooled, is attractive due to its unique capability of producing high temperature helium gas and its fully inherent reactor safety. In particular, hydrogen production using the nuclear heat from HTGR (up to 900 deg. C) offers one of the most promising technological solutions to curb the rising level of CO 2 emission and resulting risk of climate change. The interests in HTGR as an advanced nuclear power source for the next generation reactor, therefore, continue to rise. This is represented by the Japanese HTTR (High-Temperature Engineering Test Reactor) Project and the Chinese HTR-10 Project, followed by the international Generation IV development program, US nuclear hydrogen initiative program, EU innovative HTR technology development program, etc. To enhance nuclear energy application to heat process industries, the Japan Atomic Energy Agency (JAEA) has continued extensive efforts for development of hydrogen production system using the nuclear heat from HTGR in the framework of the HTTR Project. The HTTR Project has the objectives of establishing both HTGR technology and heat utilization technology. Using the HTTR constructed at the Oarai Research and Development Center of JAEA, reactor performance and safety demonstration tests have been conducted as planned. The reactor outlet temperature of 950 deg. C was successfully achieved in April 2004. For hydrogen production as heat utilization technology, R and D on thermo-chemical water splitting by the 'Iodine-Sulfur process' (IS process) has been conducted step by step. Proof of the basic IS process was made in 1997 on a lab-scale of hydrogen production of 1 L/h. In 2004, one-week continuous operation of the IS process was successfully demonstrated using a bench-scale apparatus with hydrogen production rate of 31 L/h. Further test using a pilot scale facility with greater hydrogen production rate of 10 - 30 m 3 /h is planned as

  8. Observation of high-power coherent synchrotron radiation in the THz region from the JAEA energy recovery linac

    Takahashi, Toshiharu; Okuda, Shuichi; Minehara, Eisuke J.; Hajima, Ryoichi; Sawamura, Masaru; Nagai, Ryoji; Kikuzawa, Nobihiro; Iijima, Hokuto; Nishitani, Tomohiro; Nishimori, Nobuyuki

    2007-01-01

    The energy recovery linac (ERL) is able to generate high-power coherent synchrotron radiation (CSR) in the terahertz and the millimeter-wave regions, because it produces shorter bunches than usual storage rings and a higher current than conventional linacs. The spectrum of CSR has been measured at the JAEA-ERL in the wavenumber range from 0.5 to 15 cm -1 . The detected power was 2x10 -4 W/cm -1 at 2.5 cm -1 for the average beam current of 17.7 μA. When the infrared FEL was operated with the undulator in the ERL, the CSR spectrum was shifted to the longer wavelengths because of the energy broadening of the electron beam. (author)

  9. Status of international cooperation in nuclear technology on testing/research reactors between JAEA and INP-NNC

    Kawamura, Hiroshi; Tsuchiya, Kunihiko; Takemoto, Noriyuki; Kimura, Akihiro; Tanimoto, Masataka; Izumo, Hironobu; Chakrov, Petr; Gizatulin, Shamil; Chakrova, Yelena; Ludmila, Chkushuina; Asset, Shaimerdenov; Nataliya, Romanova

    2012-02-01

    Based on the implementing arrangement between National Nuclear Center of the Republic of Kazakhstan (NNC) and the Japan Atomic Energy Agency (JAEA) for 'Nuclear Technology on Testing/Research Reactors' in cooperation in Research and Development in Nuclear Energy and Technology, four specific topics of cooperation (STC) have been carried out from June, 2009. Four STCs are as follows; (1) STC No.II-1 : International Standard of Instrumentation. (2) STC No.II-2 : Irradiation Technology of RI Production. (3) STC No.II-3 : Lifetime Expansion of Beryllium Reflector. (4) STC No.II-4 : Irradiation Technology for NTD-Si. The information exchange, personal exchange and cooperation experiments are carried out under these STCs. The status in the field of nuclear technology on testing/research reactors in the implementing arrangement is summarized, and future plans of these specific topics of cooperation are described in this report. (author)

  10. JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Refinement of thermodynamic data for tetravalent thorium, uranium, neptunium and plutonium

    Fujiwara, Kenso; Kitamura, Akira; Yui, Mikazu

    2010-03-01

    Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level and TRU radioactive wastes, the refinement of the thermodynamic data for the inorganic compounds and complexes of Thorium(IV), Uranium(IV), Neptunium(IV) and Plutonium(IV) was carried out. Refinement of thermodynamic data for the element was performed on a basis of the thermodynamic database for actinide published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Additionally, the latest data after publication of thermodynamic data by OECD/NEA were reevaluated to determine whether the data should be included in the JAEA-TDB. (author)

  11. Direct measurements of employees involved in the Fukushima Daiichi Nuclear Power Station accident for internal dose estimates. JAEA's experiences

    Kurihara, Osamu; Kanai, Katsuta; Nakagawa, Takahiro; Takada, Chie; Momose, Takumaro; Furuta, Sadaaki [Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, Tokai, Ibaraki (Japan)

    2012-11-15

    Japan Atomic Energy Agency (JAEA) performed internal dose measurements of employees involved in the Fukushima Daiichi nuclear power station accident. Nuclear Fuel Cycle Engineering Laboratories (NFCEL), one of the JAEA's core centers, examined 560 of these employees by direct (in vivo) measurements during the period from April 20 to August 5 in 2011. These measurements consisted of whole-body counting for radiocesium and thyroid counting for radioiodine. The whole-body counting was conducted with two types of whole-body counters (WBCs): a standing-type WBC with two large NaI(Tl) detectors (Fastscan{sup TM}, Canberra Inc.) and a chair-type WBC with HPGe detectors (GC5021, Canberra Inc.) installed in a shielded chamber made of 20-cm-thick steel. The thyroid counting was mainly performed using one of the two HPGe detectors equipped with the chair-type WBC. The subjects examined in this work were divided into two groups: Group 1 was the first 39 subjects who were measured up to June 17, 2011 and Group 2 was the remaining 521 subjects who were measured on and after June 18, 2011. The performance of our direct measurements was validated by comparing measurement results of the Group 1 subjects using two different methods (e.g., the standing-type WBC vs. the chair-type WBC). Tentative internal dose estimates of the subjects of Group 1 were also performed based on the assumption of a single intake scenario on either March 12, when the first hydrogen explosion occurred at the station or the first day of work after the accident. It was found that the contribution of {sup 131}I to the total internal dose greatly exceeded those of {sup 134}Cs and {sup 137}Cs, the other major nuclides detected in the measurements. The maximum committed effective dose (CED) was found in a male subject whose thyroid content of {sup 131}I was 9760 Bq on May 23, 2011; the CED of this subject was estimated to be 600 mSv including a small contribution of {sup 134}Cs and {sup 137}Cs. The typical

  12. Results of whole body counting for JAEA staff members engaged in the emergency radiological monitoring for the Fukushima nuclear disaster

    Takada, Chie; Kurihara, Osamu; Kanai, Katsuta; Nakagawa, Takahiro; Tsujimura, Norio; Momose, Takumaro [Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, Tokai, Ibaraki (Japan)

    2012-11-15

    A massive earthquake and tsunami on March 11, 2011, resulted in the release of an enormous amount of radioactive materials into the environment. On the day after the earthquake the Japan Atomic Energy Agency (JAEA) began emergency radiological monitoring. Measurements with a whole body counter (WBC) for the staff members who had returned from Fukushima began at the end of March because a power blackout for several days and lingering increased ambient radiation levels had rendered the WBCs inoperable. The measured activity level for {sup 131}I due to inhalation for emergency staff varied from below detection limit to 7 kBq, which corresponds to an estimated initial intake range of <1 to 60 kBq when extrapolated back to the date the staff began the monitoring in Fukushima. The measured activity levels for {sup 134}Cs and {sup 137}Cs were both in the ranges from below detection limit to 3 kBq. When using the median values for each set of measurements, the ratio of the initial intake of {sup 131}I to {sup 137}Cs was 11. The maximum committed effective dose of 0.8 mSv was recorded for a member of the 4th monitoring team dispatched from March 15 to 20. (author)

  13. Study on characteristics of sedimentary rock at the Horonobe site. Report of collaboration research between CRIEPI and JAEA

    Kiho, Kenzo; Oyama, Takahiro; Suzuki, Koichi; Nakata, Eiji; Tanaka, Shiro; Miyakawa, Kimio; Ishii, Eiichi; Takahashi, Kazuharu; Kunimaru, Takanori; Tsukui, Rota; Fukushima, Tatsuo; Seya, Masami; Hama, Katsuhiro; Aoki, Kazuhiro

    2006-01-01

    CRIEPI (Central Research Institute of Electric Power Industry) and JAEA (Japan Atomic Energy Agency) have been conducting a collaboration research to develop methodology for the characterization of geological environment since FY 2002. This report describes the results of the collaboration research in mainly FY 2003. As the collaboration research, the following research results were obtained. (1) Study on the diagenesis of the sedimentary rock of the Noegene Tertiary. The maximum burial depth of the formation can be estimated. (2) Study on the chemical weathering of the soft sedimentary rock. The acidic water can be caused by the chemical weathering of the rock in the Koetoi formation. (3) Study on the pore water extraction. The hydrochemical condition at the Horonobe site can be estimated by the results of the chemical analyses of extracted pore water, and the different pressure of the extraction results the different chloride contents of the pore water. (4) Study on exploration method considering the physical property of the rock. The depth profile of the mechanical properties can be estimated by the results of physical logging in the borehole. (5) Study on the applicability of the controlled drilling system to the Horonobe site. The controlled drilling system can be applicable to drill the directional borehole. (author)

  14. Annual report on major results and progress of Fusion Research and Development Directorate of JAEA from April 1, 2006 to March 31, 2007

    Suzuki, Satoshi; Ishii, Yasutomo; Sukegawa, Atsuhiko; Iwai, Yasunori; Nakamura, Hiroo; Sugie, Tatsuo

    2008-08-01

    This annual report provides an overview of major results and progress on research and development (R and D) activities at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from April 1, 2006 to March 31, 2007, including those performed in collaboration with other research establishments of JAEA, research institutes, and universities. In JT-60, as a result of ferritic steel tiles (FSTs) installation to reduce the toroidal field ripple and the application of the real time current profile control, high boot strap current fraction (∼0.7) has successfully been sustained about 8 s. In addition, the conceptual design of JT-60SA, which was placed as a combined project of JA-EU Satellite Tokamak Programme under the Broader Approach Programme and JAEA's programme for national use, was progressed. In theoretical and analytical researches, studies on ITB events and their triggers, plasma shape effect on edge stability and driven magnetic island evolution in rotating plasmas were progressed. In the NEXT project, computer simulations of the plasma turbulence were progressed. In fusion reactor technologies, R and Ds for ITER and fusion DEMO plants have been carried out. For ITER, a steady state operation of the 170GHz gyrotron up to 10min with 0.82MW was demonstrated. Also current density of the neutral beam injector has been extended to 146A/m 2 at 0.84MeV. In the ITER Test Blanket Module (TBM), designs and R and Ds of Water and Helium Cooled Solid Breeder TBMs including tritium breeder/multiplier materials were progressed. Tritium processing technology for breeding blankets and neutronics integral experiments with a blanket mockup were also progressed. For ITER and DEMO blankets, studies on neutron irradiation effects and ion irradiation effects on F82H steel characteristics were continued using HFIR, TIARA and so on. In the IFMIF program, transitional activities to EVEDA were continued. In the ITER Program, under the framework of the ITER

  15. Study on characteristics of sedimentary rock at the Horonobe site (2). Report of collaboration research between CRIEPI and JAEA

    Oyama, Takahiro; Kiho, Kenzo; Suzuki, Koichi; Nakata, Eiji; Tanaka, Shiro; Hasegawa, Takuma; Nakata, Kotaro; Nagaoka, Toru; Nakamura, Takamichi; Fukushima, Tatsuo; Ishii, Eiichi; Kunimaru; Takanori; Hama, Katsuhiro; Iwatsuki, Teruki; Sugita, Yutaka; Yabuuchi, Satoshi; Miyahara, Shigenori; Takahashi, Kazuharu

    2010-01-01

    CRIEPI (Central Research Institute of Electric Power Industry) and JAEA (Japan Atomic Energy Agency) have been conducting a collaboration research to develop methodology for the characterization of geological environment since FY 2002. This report describes the results of the collaboration research in mainly from FY 2004 to FY 2008. As the collaboration research, the following research results were obtained. (1) Study on the slaking property. We discovered the spherical silica (amorphous silica) in siliceous rock (Opalin chert) between the Koetoi and Wakkanai Formation. The permeability of this chert (10 -12 m/sec) decreases to compare with near depth diatomaceous mudstone (10 -10 m/sec). This diatomaceous mudstone dose not rapidly slakes. Excavated disturbed zone(EdZ) at -140 m tunnel was estimated with drilled cores and gas flows from the tunnel wall. (2) Study on the chemical weathering of the sedimentary rock. The weathering property was investigated of mudstone at an outcrop and east shaft. Weathering profile was divided oxidized, dissolved, transition and fresh zone. Oxidation was limited to the vicinity of surface. (3) Study on the pore water extraction methodology. Sample preparation under N 2 condition before porewater squeezing to prevent oxidation showed that the squeezed porewater chemistry was affected by the sample storage period before squeezing. (4) Study on exploration method considering the physical property of the rock. The depth profile of the mechanical and permeability properties can be estimated by the results of physical logging in the borehole and laboratory measurements of core samples. (5) Study on the applicability of the controlled drilling system to the Horonobe site. The controlled drilling system was applied to the Hokushin site and the Kami-horonobe site in the Horonobe town. At the Kami-horonobe site, the system was applied to drill the Omagari fault and characterize the hydro-geology around the fault. The controlled drilling was

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

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

    2013-12-01

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

  17. JAEA's research on the effects of seawater and radiation on corrosion of Zircaloy and PCV/RPV steels

    Tsukada, Takashi; Motooka, Takafumi; Nakano, Junichi

    2014-01-01

    In order to implement successfully a lot of work for the extraction of fuel assemblies from spent fuel pool (SFP) and also for the removal of fuel debris from reactor pressure vessel (RPV) and primary containment vessel (PCV) at the Fukushima Daiichi Nuclear Power Station (NPS) of Tokyo Electric Power Co., it is necessary to investigate and to prevent the degradation of structural materials of the fuel assemblies and PCV/RPV which are exposed to the gamma radiation and water containing seawater ingredient, because those factors are influencing and possibly accelerating corrosion of the materials. Therefore, at the Japan Atomic Energy Agency (JAEA), we are carrying out the research related to the corrosion issues which may affect the integrity of fuel assemblies and reactor vessels, i.e. PCV and reactor pressure vessel (RPV), from a viewpoint of the effect of gamma radiation and diluted seawater on corrosion behavior as described in this review. In SFP, hydrazine (N_2H_4) was added to salt-containing water in order to reduce dissolved oxygen (DO). Therefore, deoxygenation behavior by N_2H_4 addition was investigated at the ambient temperature. To evaluate the effects of radiolysis on the initiation of pitting corrosion on Zircaloy-2 in water containing sea salt, the pitting potentials of Zircaloy-2 were evaluated. The experimental results showed that the pitting potential under irradiation was slightly higher than that under conditions in which no radiation was present. Corrosion tests of PCV/RPV steels were conducted in diluted seawater at 50degC under gamma-ray irradiation of dose rates of 4.4 and 0.2 kGy/h. To assess the effect of N_2H_4 as an oxygen scavenger under gamma-ray irradiation in PCV condition, 10 and 100 mg/L N_2H_4 were added to the diluted seawater. When gas phase in test flask was replaced with N_2, corrosion weight loss of the steels decreased remarkably. (author)

  18. Outline of the activity for the environmental recovery and the R and D of remoteradiation monitoring. Activities for the environmental recovery by JAEA

    Yoneya, Masayuki; Sanada, Yukihisa

    2015-01-01

    The radioactive materials that had been released from the TEPCO Fukushima Daiichi Nuclear Power Station accident polluted the environments of Fukushima Prefecture and its surrounding areas. The Japan Atomic Energy Agency (JAEA) has been conducting a variety of activities for dealing with environmental pollution toward the reconstruction of Fukushima. After the power plant accident, radiation monitoring using manned helicopters was started, and continuous surveys that were standardized by JAEA are being carried out by the Nuclear Regulatory Agency. In the remote radiation monitoring, unmanned helicopters in addition to manned helicopters have been used in the survey of areas with high dose rate and riverbeds. The monitoring with unmanned helicopters was performed within the 5 km distance from the power plant, and the temporal change trends of dose rate were calculated. The types of mounted detectors were NaI and LaBr_3 scintillation detectors, which are capable of discriminating gamma-ray energy. As for the unmanned airplanes, Unmanned Airplane Radiation Monitoring System (URAMS) was developed in collaboration with the Japan Aerospace Exploration Agency (JAXA). URAMS has advantages such as long-distance communications and long cruising distance. (A.O.)

  19. Long-term outlook of energy demand and supply in Japan. Estimation of energy demand and supply for 'Nuclear Energy Vision 2100' of JAEA

    Tatematsu, Kenji; Kawasaki, Hirotsugu; Nemoto, Masahiro; Murakami, Masakazu

    2009-06-01

    In this study, we showed an energy demand and supply scenario toward the year 2100 in Japan, which underlies JAEA's 'Nuclear Energy Vision 2100' published in October 2008. This energy demand and supply scenario aimed at the coexistence of the reduction of the carbon dioxide emission and the energy security through reduction of the fossil fuel usage, positive electrification and the nuclear energy usage. We reduced the ratio of the fossil fuel in the primary energy supply to about 1/3 and extend the share of renewable and nuclear energy to 70% from current 15%. As a result, the carbon dioxide emission was reduced to current 10%, and it developed that the half was the contribution of the nuclear energy. (author)

  20. JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Selection of thermodynamic data of cobalt and nickel

    Kitamura, Akira; Yui, Mikazu; Kirishima, Akira; Saito, Takumi; Shibutani, Sanae; Tochiyama, Osamu

    2009-11-01

    Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level and TRU wastes, the selection of the thermodynamic data on the inorganic compounds and complexes of cobalt and nickel have been carried out. For cobalt, extensive literature survey has been performed and all the obtained literatures have been carefully reviewed to select the thermodynamic data. Selection of thermodynamic data of nickel has been based on a thermodynamic database published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA), which has been carefully reviewed by the authors, and then thermodynamic data have been selected after surveying latest literatures. Based on the similarity of chemical properties between cobalt and nickel, complementary thermodynamic data of nickel and cobalt species expected under the geological disposal condition have been selected to complete the thermodynamic data set for the performance assessment of geological disposal of radioactive wastes. (author)

  1. JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Selection of thermodynamic data of selenium

    Doi, Reisuke; Kitamura, Akira; Yui, Mikazu

    2010-02-01

    Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level and TRU radioactive wastes, the selection of the thermodynamic data on the inorganic compounds and complexes of selenium was carried out. Selection of thermodynamic data of selenium was based on a thermodynamic database of selenium published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). The remarks of a thermodynamic database by OECD/NEA found by the authors were noted in this report and then thermodynamic data was reviewed after surveying latest literatures. Some thermodynamic values of iron selenides were not selected by the OECD/NEA due to low reliability. But they were important for the performance assessment of geological disposal of radioactive wastes, so we selected them as a tentative value with specifying reliability and needs of the value to be determined. (author)

  2. JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Refinement of thermodynamic data for trivalent actinoids and samarium

    Kitamura, Akira; Fujiwara, Kenso; Yui, Mikazu

    2010-01-01

    Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level radioactive and TRU wastes, the refinement of the thermodynamic data for the inorganic compounds and complexes of trivalent actinoids (actinium(III), plutonium(III), americium(III) and curium(III)) and samarium(III) was carried out. Refinement of thermodynamic data for these elements was based on the thermodynamic database for americium published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Based on the similarity of chemical properties among trivalent actinoids and samarium, complementary thermodynamic data for their species expected under the geological disposal conditions were selected to complete the thermodynamic data set for the performance assessment of geological disposal of radioactive wastes. (author)

  3. 20 Years of Achievement and Future Challenge for International Capacity Building Regarding Safeguards and SSAC at Japan Atomic Energy Agency (JAEA)

    Senzaki, M.; Naoi, Y.; Kuribayashi, T.; Okumura, Y.

    2015-01-01

    Developing human resources in the fields of nuclear non-proliferation and safeguards is critical to promote the peaceful use of nuclear energy. The shortfall of human resources in such fields presents a serious challenge. It has, therefore, become important to urgently develop human resources and thereby to ensure. With a long experience in practicing Japan's nuclear non-proliferation policy, JAEA has been contributing since the 1990s to international human-resource development. More than 300 people from about 40 countries have joined the training courses organized by the Integrated Support Center for Nuclear Non-proliferation and Nuclear Security (ISCN) of JAEA. These courses use lectures, workshops, group discussions, and facility tours to teach knowledge of the basic concepts of IAEA safeguards, SSAC requirements, and safeguards tools to government officials who are responsible for safeguards implementation and to operators who are engaged in nuclear-material accounting and control. Based on Japan's statement at the 2010 Nuclear Security Summit, ISCN was established in December 2010. ISCN places top priority on providing support for the development of future leaders, the development of legal and regulatory infrastructure, and the fostering of nuclear non-proliferation culture. For further advancement, ISCN also examines the current situations of the Asian nations that ISCN supports, based on discussions made between the Japanese government and the IAEA. It works on formulating new training courses that focus on specific themes, such as NDA training and table-top exercises for CA under the AP, identified through needs surveys. ISCN is committed to the development of human resources in the field of safeguards and work closely with governmental organizations in Japan and with other Asian countries, the IAEA, US DOE, European Commission, FNCA, and APSN. (author)

  4. Integral test of International Reactor Dosimetry and Fusion File with Li{sub 2}O assembly and DT neutron source at JAEA/FNS

    Sato, Satoshi, E-mail: sato.satoshi92@jaea.go.jp [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken (Japan); Kwon, Saerom; Ohta, Masayuki [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken (Japan); Ochiai, Kentaro [Japan Atomic Energy Agency, Rokkasho-mura, Kamikita-gun, Aomori-ken (Japan); Konno, Chikara [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken (Japan)

    2016-11-01

    In order to validate a new library of dosimetry cross section data, International Reactor Dosimetry and Fusion File release 1.0 (IRDFF 1.0), not only for DT neutrons but also for neutrons with energy of less than 14 MeV, we perform an integral test with a Li{sub 2}O rectangular assembly of 60.7 cm in thickness and a DT neutron source at JAEA/FNS. We place a lot of activation foils at depths of 10.1 cm and 30.4 cm for measurements of dosimetry reaction rates in small space along the central axis in the assembly, measure decay gamma-rays from the activation foils with high-purity Ge detectors after the DT neutron irradiation by the foil activation technique, and deduce a variety of dosimetry reaction rates. We calculate the reaction rates by using a Monte Carlo code MCNP5-1.40 and the nuclear data library ENDF/B-VII.1 with the IRDFF-v.1.05 as the response functions for the dosimetry reactions. The calculation results generally show good agreements with the measured ones, and it can be confirmed that most of the data in IRDFF-v.1.05 are valid for the neutron field in the Li{sub 2}O assembly with the DT neutrons.

  5. Improvement in beam quality of the JAEA AVF cyclotron for focusing heavy-ion beams with energies of hundreds of MeV

    Kurashima, Satoshi; Miyawaki, Nobumasa; Okumura, Susumu; Oikawa, Masakazu; Yoshida, Ken-ichi; Kamiya, Tomihiro; Fukuda, Mitsuhiro; Satoh, Takahiro; Nara, Takayuki; Agematsu, Takashi; Ishibori, Ikuo; Yokota, Watalu; Nakamura, Yoshiteru

    2007-01-01

    In order to achieve a heavy-ion microbeam with an energy of hundreds of MeV applied to the research fields of biotechnology and materials science, the JAEA AVF cyclotron (K = 110) has been upgraded to provide a high quality beam with a smaller energy spread and a higher current stability. A flat-top (FT) acceleration system of the cyclotron, designed to produce ion beams with an energy spread of ΔE/E ≤ 0.02%, has been developed to reduce chromatic aberrations in the lenses of the focusing microbeam system. The FT acceleration system provides uniform energy gain of the beam by superimposing a fifth-harmonic voltage on the fundamental one. In addition, stabilization of the acceleration rf voltage and the phase were achieved to accelerate the high quality beam and to provide it stably to the microbeam system connected to a cyclotron beam line. In the latest experiment, we have succeeded to accelerate 260 MeV 20 Ne 7+ with an energy spread of 0.05% in FWHM using the FT acceleration system

  6. JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Selection of thermodynamic data of molybdenum

    Kitamura, Akira; Kirishima, Akira; Saito, Takumi; Shibutani, Sanae; Tochiyama, Osamu

    2010-06-01

    Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level radioactive and TRU wastes, the selection of the thermodynamic data on the inorganic compounds and complexes of molybdenum were carried out. We focused to select thermodynamic data of aqueous species and compounds which could form under repository conditions for the disposal of radioactive wastes, i.e. relatively low concentration of molybdenum and from near neutral through alkaline conditions. Selection of thermodynamic data was based on the guidelines by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Extensive literature survey was performed and all the obtained articles were carefully reviewed to select the thermodynamic data for molybdenum. Thermodynamic data at 25degC and zero ionic strength were determined from accepted thermodynamic data which were considered to be reliable. We especially paid attention to select formation constant of molybdate ion (MoO 4 2- ) with hydrogen ion (H + ) in detail. This is the first report in showing selection of thermodynamic data for molybdenum with detailed reviewing process. (author)

  7. Analyses of iron and concrete shielding experiments at JAEA/TIARA with JENDL/HE-2007, ENDF/B-VII.1 and FENDL-3.0

    Konno, Chikara; Ochiai, Kentaro; Sato, Satoshi; Ohta, Masayuki

    2015-01-01

    IAEA released a new Fusion Evaluated Nuclear Data Library, FENDL-3.0, in 2012. FENDL-3.0 extends the neutron energy range from 20 MeV to greater than 60 MeV. Now there is increasing interest in nuclear data above 20 MeV. Thus we have analyzed the iron and concrete shielding experiments with the 40 and 65 MeV neutron sources at TIARA in Japan Atomic Energy Agency with the latest high-energy nuclear data libraries, JENDL/HE-2007, ENDF/B-VII.1 and FENDL-3.0. The Monte Carlo code MCNP-5 and ACE files of JENDL/HE-2007, ENDF/B-VII.1 and FENDL-3.0, which are supplied from JAEA, LANL and IAEA, respectively, were used for this analysis. The collimated neutron beam and test shields were modeled in the analysis. The measured source neutron data were adopted in the analysis. The followings are found out from the results; (1) Iron experiments: The calculation result with FENDL-3.0 agrees with the measured one best. That with JENDL/HE-2007 fairly agrees with the measured one. On the contrary that with ENDF/B-VII.1 drastically overestimates the measured one. It is confirmed that this overestimation is due to the smaller non-elastic scattering data of "5"6Fe in ENDF/B-VII.1. (2) Concrete experiments: The calculation result with ENDL/HE-2007 agrees with the measured one best, while those with FENDL-3.0 and ENDF/B-VII.1 drastically overestimate the measured one. It is confirmed that this overestimation is due to both the larger elastic and smaller non-elastic scattering data of "1"6O in FENDL-3.0 and ENDF/B-VII.1.

  8. Proceedings of the 5th workshop of 'quantum complex phenomena, -superconductivity, magnetism and phonon-' under the NIMS-RIKEN-JAEA cooperative research program on quantum beam science and technology

    Shamoto, Shin-ichi; Kodama, Katsuaki

    2012-08-01

    The 5th workshop of the NIMS-RIKEN-JAEA Cooperative Research Program 'Quantum Complex Phenomena, -Superconductivity, Magnetism and Phonon-' was held on January 23-24, 2012 at KKR Hakone Miyanoshita. This workshop is aimed to reveal the mechanism of quantum complex phenomena for the developments of next generation functional materials on the basis of 'Joint Research Agreement for the Pioneering R and D with Quantum Beam Technology' concluded by NIMS, RIKEN and JAEA on December 20, 2006. The neutron facilities in Tokai, i.e., the research reactor JRR-3 and the proton accelerator J-PARC (Japan Proton Accelerator Research Complex), were damaged by the Tohoku-Kanto earthquake on March 11, 2011. J-PARC members' devoted efforts for the recovery made it possible to successfully produce neutron beam in the midnight of January 24, just after this workshop. Also at JRR-3 all the repair works of the reactor facilities and buildings have been completed by the end of the fiscal year 2011. Yet, the safety analysis report is to be submitted and after its positive review by the national regulatory authority, the JRR-3 can undergo the regular periodic inspection to resume its operation. Under this circumstance, characteristic technologies, instruments, and distinguished researches of each institute about 'Superconductivity, Magnetism and Phonon' are introduced and discussed in addition to research outcomes of this Joint Research Agreement including a future prospect of this research area. This report includes abstracts and materials of the presentations in the workshop. (author)

  9. Development of a He/CdI$_2$ gas-jet system coupled to a surface-ionization type ion-source in JAEA-ISOL: towards determination of the first ionization potential of Lr (Z = 103)

    Sato, T K; Sato, N; Tsukada, K; Toyoshima, A; Ooe, K; Miyashita, S; Kaneya, Y; Osa, A; Schädel, M; Nagame, Y; Ichikawa, S; Stora, T; Kratz, J V

    2015-01-01

    We report on development of a gas-jet transport system coupled to a surface ionization ion-source in the JAEA-ISOL (Isotope Separator On-Line) system. As a new aerosol material for the gas-jet system, CdI2, which has a low boiling point of 713 °C, is exploited to prevent deposition of the aerosol material on the surface of the ion-source. An additional filament is newly installed in the previous ion-source to provide uniform heating of an ionizer. The present system is applied to the measurement of absolute efficiencies of various short-lived lanthanide isotopes produced in nuclear reactions.

  10. Annual report on major results and progress of Naka Fusion Research Establishment of JAERI from April 1 to September 30, 2005 and Fusion Research and Development Directorate of JAEA from October 1, 2005 to March 31, 2006

    Yoshida, Hidetoshi; Oasa, Kazumi; Hayashi, Takao; Nakamura, Hiroo; Ogawa, Hiroaki

    2006-09-01

    This annual report provides an overview of major results and progress on research and development (R and D) activities at Naka Fusion Research Establishment of Japan Atomic Energy Research Institute (JAERI) during the period from April 1 to September 30, 2005 and at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from October 1, 2005 to March 31, 2006, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities. In JT-60, ferritic steel tiles (FSTs) were installed inside the vacuum vessel of JT-60U to reduce the toroidal field ripple. After the installation of FSTs, a high normalized beta plasma at β N ∼2.3 was sustained for 28.6s with ELMy H-mode confinement as required for an ITER hybrid operation scenario. National Centralized Tokamak was placed as the ITER satellite tokamak in collaboration with the EU fusion community, and the facility design was modified strongly in support of ITER. In theoretical and analytical researches, studies on H-mode confinement, ITB in reversed shear plasmas, aspect ratio effects on external MHD modes and magnetic island evolution in a rotating plasma were progressed. Progress was also made in the NEXT project in which the behaviors of collisionless MHD modes and the dynamics of zonal flows were simulated. In fusion reactor technologies, R and Ds for ITER and fusion DEMO plants have been carried out. For ITER, a steady state operation of the 170GHz gyrotron up to 1000 s with 0.2 MW was demonstrated. Also current density of the neutral beam injector has been extended to 134A/m 2 at 0.75MeV. In the ITER Test Blanket Module (TBM), designs of Water and Helium Cooled Solid Breeder TBMs and R and Ds of tritium breeder/multiplier materials were progressed. Tritium processing technology for breeding blankets was also progressed. For the DEMO reactors, high temperature superconductor such as Bi2212 has been examined. In plasma facing

  11. Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage. Progress report on NUMO-JAEA collaborative research in FY2011 (Joint research)

    Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Makino, Hitoshi; Hayano, Akira; Mitsui, Seiichiro; Taniguchi, Naoki; Oda, Chie; Kitamura, Akira; Osawa, Hideaki; Semba, Takeshi; Hioki, Kazumasa; Kamei, Gento; Ebashi, Takeshi; Kubota, Shigeru; Kurosawa, Susumu; Goto, Junichi; Goto, Takahiro; Ishii, Eiichi; Inagaki, Manabu; Moriya, Toshifumi; Suzuki, Satoru; Ohi, Takao; Ichihara, Takayuki; Ishida, Keisuke; Ishiguro, Katsuhiko; Tsuchi, Hiroyuki

    2012-09-01

    JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and performance assessment in preliminary investigation stage. The topics of such joint research are (1) study on selection of host rock, (2) study on development of scenario, (3) study on setting nuclide migration parameters, (4) study on ensuring quality of knowledge. With regard to (1), in terms of hydraulic properties, items for assessing rock property, and assessment methodology of groundwater travel time has been organized with interaction from site investigation. With regard to (2), the existing approach has been embodied, in addition, the phenomenological understanding regarding dissolution of and nuclide release from vitrified waste, corrosion of the overpack, long-term performance of the buffer are summarized. With regard to (3), the approach for parameter setting has been improved for sorption and diffusion coefficient of buffer/rock, and applied and tested for parameter setting of key radionuclides. With regard to (4), framework for ensuring quality of knowledge has been studied and examined aimed at the likely disposal facility condition. (author)

  12. Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage (3). Progress report on NUMO-JAEA collaborative research in FY2013 (Joint research)

    Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Makino, Hitoshi; Wakasugi, Keiichiro; Mitsui, Seiichiro; Kitamura, Akira; Oda, Chie; Ishidera, Takamitsu; Suyama, Tadahiro; Hatanaka, Koichiro; Kamei, Gento; Yoshikawa, Hideki; Senba, Takeshi; Seo, Toshihiro; Kurosawa, Susumu; Goto, Junichi; Shibutani, Sanae; Goto, Takahiro; Kubota, Shigeru; Inagaki, Manabu; Moriya, Toshifumi; Suzuki, Satoru; Ishida, Keisuke; Nishio, Hikaru; Makiuchi, Akie; Fujihara, Hiroshi

    2015-03-01

    JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and post-closure performance assessment in preliminary investigation stage. With regard to (1) study on host rock suitability in terms of hydrology, based on some examples of developing method of hydro-geological structure model, acquired knowledge are arranged using the tree diagram, and model uncertainty and its influence on the evaluation items were discussed. With regard to (2) study on scenario development, the developed approach for “defining conditions” has been reevaluated and improved from practical viewpoints. In addition, the uncertainty evaluation for the effect of use of cementitious material, as well as glass dissolution model, was conducted with analytical evaluation. With regard to (3) study on setting radionuclide migration parameters, based on survey of precedent procedures, multiple-approach for distribution coefficient of rocks was established, and the adequacy of the approach was confirmed through its application to sedimentary rock and granitic rock. Besides, an approach for solubility setting was developed including the procedure of selection of solubility limiting solid phase. The adequacy of the approach was confirmed through its application to key radionuclides. (author)

  13. Presentation to JAEA Visitors, July 24, 2012

    Gavron, Victor

    2012-01-01

    There are 7 Reasons for characterizing spent fuel nuclide concentrations: (1) Provide IAEA with the capability to independently verify the mass of plutonium at any site that has spent fuel; (2) Shipper/receiver difference; (3) Determination of the input accountability mass of an electrochemical (pyro-chemical) processing facility; (4) Continuity of knowledge at spent fuel storage site; (5) Optimal reloads through knowledge of true actinide content; (6) Burnup credit for fuel transport and storage; and (7) Provide confidence to the public that the shipment of spent fuel around the world is being undertaken in a rigorous manner, assuring that material is not diverted during shipment. Types of fuel of interest are: Fast Reactor Fuel, Normal burnup low enriched uranium (LEU), Mixed oxide (MOX), Low burnup LEU, and Research reactor. MCNPX calculates the slowing down and the energy spread for a given time. The principles are: (1) Neutrons slow down in LSDS; (2) Slow neutrons capture preferentially on a fission resonance; (3) Fission emits high-energy neutrons; (4) High-energy neutrons detected in threshold detector (that is not sensitive to slow neutrons) (e.g., 238 U, 232 Th); and (5) The detection time is characteristic of the slow neutron energy. Following each PSR pulse, the entire signal is digitized in 2 nanosecond intervals, and subsequently analyzed Analysis involves applying a digital filter to extract fission pulses in a background of initial oscillations and noise throughout. Some of the noise is not random. Depending on the threshold setting and filter parameters, both the normalization and the trend change. Original PNNL LSDS design required a 1-meter radius cylindrical LSDS. Much higher efficiency would allow us to use a (1.2m) LSDS (this is the LANL LSDS size), or a less intense source, or a combination of both. We still estimate 10 16 total neutrons from the source to obtain 2-3% precision in 239 Pu and 235 U assay.

  14. The history and library statistics of JAEA library activities

    Itabashi, Keizo [Japan Atomic Energy Agency, Intellectual Resources Dept., Tokai, Ibaraki (Japan)

    2012-03-15

    The history and library statistics of the Japan Atomic Energy Agency library activity were summarized. Former Japan Atomic Energy Research Institute and the former Japan Nuclear Cycle Development Institute merged in October, 2005, and Japan Atomic Energy Agency is established. Properly speaking, the library statistics of old two corporations should have been summarized, but statistics of the Japan Nuclear Cycle Development Institute is not yet obtained. Then, although it is stated as the Japan Atomic Energy Agency library, it limits to the description about the old Japan Atomic Energy Research Institute library before 2004. (author)

  15. The history and library statistics of JAEA library activities

    Itabashi, Keizo

    2012-03-01

    The history and library statistics of the Japan Atomic Energy Agency library activity were summarized. Former Japan Atomic Energy Research Institute and the former Japan Nuclear Cycle Development Institute merged in October, 2005, and Japan Atomic Energy Agency is established. Properly speaking, the library statistics of old two corporations should have been summarized, but statistics of the Japan Nuclear Cycle Development Institute is not yet obtained. Then, although it is stated as the Japan Atomic Energy Agency library, it limits to the description about the old Japan Atomic Energy Research Institute library before 2004. (author)

  16. JAEA FBR Plant Engineering Center annual report 2011

    2012-11-01

    The FBR Plant Engineering Center was established on April 1, 2009 located in a research building, of which care is taken by the International Nuclear Information Training Center, Tsuruga Head Office, at Shiraki in Tsuruga. The mission of the center is to perform R and D (research and development) works both for analysis of operational experiences at the prototype fast breeder reactor “Monju” and for technology development concerning design and operation of “Monju”. Moreover it is also required to apply the results to next generation fast breeder reactors, which is an important role of Advanced Nuclear System Research and Development Directorate. And in these R and D activities, it is expected to conduct the works in cooperation with domestic or foreign research organizations or universities by a joint-study or a collaborative-work manner. The R and D activities have been carried out specifically on the “demonstration of the reliability as a power generation plant” and “establishment of sodium handling technology”, which are originally intended missions of “Monju”. And the other R and Ds have been promoted both for the plant engineering, such as plant maintenance, to effectively use an existing reactor in order to apply the R and D results to a future demonstration reactor, and for the irradiation test study, such as advanced fuel irradiation, to use “Monju” as an irradiation test bed. In order to perform these R and D activities, five R and D groups have been set up in the center. They are operation-and-maintenance engineering, sodium engineering, reactor-core-and-fuel engineering, plant engineering, and safety engineering groups. However, the Japanese atomic energy policy is being reviewed after the accident of the Fukushima Daiichi nuclear power station caused by a tsunami generated by the Tohoku-district-off-the-Pacific-Ocean Earthquake on March 11, 2011, and all the R and D activities using “Monju” have been suspended since late 2011. And the researchers of fast breeder reactors are waiting for a decision on the nuclear energy policy by the Japanese government. Three years have passed since the center was established. The research activities of the center have recently begun to thrive at last, though the surrounding environment is not so good as mentioned above. Therefore, I decided to compile this annual report for research activities of early 2011. This annual report is intended for a report of the activities of individual researcher in the center rather than that of the progress of the center as a whole. I hope this annual report will provide support to our researchers in attempting to communicate with people who are making progress on a similar field. (author)

  17. Operational status of the JAEA-Mutsu tandetron AMS

    Kabuto, Shoji; Kinoshita, Naoki; Amano, Hikaru; Watanabe, Yukiya; Baba, Masami

    2008-01-01

    A Tandetron AMS (Accelerator Mass Spectrometer) had been set up at the Japan Atomic Energy Agency (formerly the Japan Atomic Energy Research Institute), Mutsu in 1997. The AMS features 3MV Tandetron accelerator and two independent beamlines for 14 C and 129 I measurement. In this paper, we describe the current status and troubles for the Tandetron AMS with the showing of examples from the last year. (author)

  18. SNL/JAEA Collaborations on Sodium Fire Benchmarking.

    Clark, Andrew Jordan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Denman, Matthew R [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Takata, Takashi [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ohshima, Hiroyuki [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-11-01

    Two sodium spray fire experiments performed by Sandia National Laboratories (SNL) were used for a code - to - code comparison between CONTAIN - LMR and SPHINCS. Both computer codes are used for modeling sodium accidents in sodium fast reactors. The comparison between the two codes provides insights into the ability of both codes to model sodium spray fires. The SNL T3 and T4 experiments are 20 kg sodium spray fires with sodium spray temperature s of 200 deg C and 500 deg C, respe ctively. Given the relatively low sodium temperature in the SNL T3 experiment, the sodium spray experienced a period of non - combustion. The vessel in the SNL T4 experiment experienced a rapid pressurization that caused of the instrumentation ports to fail during the sodium spray. Despite these unforeseen difficulties, both codes were shown in good agreement with the experiment s . The subsequent pool fire that develops from the unburned sodium spray is a significant characteristic of the T3 experiment. SPHIN CS showed better long - term agreement with the SNL T3 experiment than CONTAIN - LMR. The unexpected port failure during the SNL T4 experiment presented modelling challenges. The time at which the port failure occurred is unknown, but is believed to have occur red at about 11 seconds into the sodium spray fire. The sensitivity analysis for the SNL T4 experiment shows that with a port failure, the sodium spray fire can still maintain elevated pressures during the spray.

  19. Recent activities on water detritiation technology in JAEA

    Iwai, Yasunori, E-mail: iwai.yasunori@jaea.go.jp [Japan Atomic Energy Agency, Tokai, Naka, Ibaraki 319-1195 (Japan); Kubo, Hitoshi; Ohshima, Yusuke; Noguchi, Hiroshi; Taniuchi, Junichi [Tanaka Kikinzoku Kogyo K.K., Wadai, Tsukuba, Ibaraki 300-4247 (Japan)

    2016-11-01

    Highlights: • Water detritiation technology has been developed for the Japanese fusion DEMO plant. • Durability of an ion exchange membrane was checked with concentrated tritiated water. • Hydrophobic catalyst of SiO{sub 2} substrate has been developed for water detritiation. - Abstract: Japan Atomic Energy Agency has developed the water detritiation technology for CECE process considering the escalation in quantity and tritium concentration of tritiated water to be processed toward realization of the Japanese fusion DEMO plant. A commercial ion exchange perfluoro-membrane for concentrated tritiated water electrolyzer is durable against irradiation up to 1500 kGy in view of mechanical strength and ion exchange capacity. Concerning hydrophobic catalyst for LPCE column, a new method of manufacturing catalysts involving hydrophobic processing with an inorganic substance base has been developed. The catalyst created with this method has achieved the highest exchange efficiency, equivalent to 1.3 times the previously most powerful efficiency.

  20. Present status of R and D on nuclear forensics at JAEA

    Kimura, Yoshiki; Sakurai, Satoshi; Sato, Kaneaki; Toda, Nobufumi; Shinoda, Yoshiharu; Okubo, Ayako; Magara, Masaaki; Watahiki, Masaru; Kuno, Yusuke

    2012-01-01

    The national statement made by the Japan Government at 2010 Nuclear Security Summit (Washington D.C., U.S.A.) was to develop its nuclear forensics detection and analysis technologies in a three-year period and to share them with the international community to contribute to strengthening the nuclear security regime. The Japan Atomic Energy Agency, the organization that possesses analytical capabilities with the potential to fulfill this nuclear forensics mission, started R and D on nuclear forensics technology from JFY 2011. The main areas of development are isotopic ratio analysis, impurity analysis, uranium age determination, etc. The cooperation with US-DOE and EC-JRC were also started to effectively promote the technical development. In the presentation reported will be progress in R and D to establish nuclear forensics analytical capabilities and international cooperation. (author)

  1. Report on JAEA's Reimei Research Program. April 1, 2006 - March 31, 2007

    Ikezoe, Hiroshi

    2008-02-01

    The Reimei (Dawn) Research Program is a research project based on public application to be conducted within the framework of the Reimei Research Promotion project of the Japan Atomic Energy Agency. The objective of the program is to encourage original and/or unique ideas in the field of the new frontier research of atomic energy science. The number of the research subjects accepted in the fiscal year 2007 was 8. These research subjects were carried out in collaboration with Advanced Science Research Center. The summaries of these research subjects were compiled in this report. We hope that new researches will be grown and developed by the help of Reimei Research Promotion project. The 8 of the presented papers are indexed individually. (J.P.N.)

  2. Review of JAEA activities on the IFMIF liquid lithium target in FY2006

    Ida, Mizuho; Nakamura, Hiroo; Miyashita, Makoto; Sugimoto, Masayoshi; Chida, Teruo; Furuya, Kazuyuki; Yoshida, Eiichi; Hirakawa, Yasuhi; Miyake, Osamu; Hirabayashi, Masaru; Ara, Kuniaki

    2008-03-01

    Engineering Validation Design and Engineering Design Activity (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF) is under going. IFMIF is an accelerator-based Deuterium-Lithium (D-Li) neutron source to produce intense high energy neutrons and a sufficient irradiation volume for testing candidate materials for fusion reactors. To realize such a condition, 40 MeV deuteron beam with a current of 250 mA is injected into high speed liquid Li flow with a speed of 20 m/s. In target system, nuclear heating due to neutron causes thermal stress especially on a back-wall of the target assembly. In addition, radioactive species such as beryllium-7, tritium and activated corrosion products are generated. In this report, thermal stress analyses of the back-wall, mechanical tests on weld specimen made of the back-wall material, estimations of beryllium-7 behavior and worker dose at the IFMIF Li loop and consideration on major EVEDA tasks are summarized. (author)

  3. Recent Developments of JAEA's Monte Carlo Code MVP for Reactor Physics Applications

    Nagaya, Yasunobu; Okumura, Keisuke; Mori, Takamasa

    2014-06-01

    This paper describes the recent development status of a Monte Carlo code MVP developed at Japan Atomic Energy Agency. The basic features and capabilities of MVP are overviewed. In addition, new capabilities useful for reactor analysis are also described.

  4. Reports of JAEA's Reimei Research Program. April 1, 2009 - March 31, 2010

    Nagame, Yuichiro

    2011-02-01

    The Reimei (Dawn) Research Program is conducted based on public application to encourage original and/or unique ideas in the field of new frontier research of atomic energy sciences. The eight research subjects were accepted in the fiscal year 2009 that were carried out in collaboration with Advanced Science Research Center. The summaries of these research subjects are compiled in this report. We hope that new frontier research projects will be developed through the present Reimei Research Program. The 8 of the presented papers are indexed individually. (J.P.N.)

  5. Reports on JAEA's Reimei Research Program. April 1, 2012 - March 31, 2013

    Nagame, Yuichiro

    2014-03-01

    The Reimei (Dawn) Research Program is conducted based on public application to encourage original and/or unique ideas in the field of new frontier research on atomic energy sciences. Candidates for the offering have been extended beyond the country since the fiscal year of 2010. The seven research subjects including two ongoing ones were accepted in the fiscal year 2012 that were carried out in collaboration with Advanced Science Research Center. The three successive projects, in particular, have achieved substantial progress through the effective international collaboration. The summaries of these research subjects are compiled in this report. We hope that new frontier research projects will be developed through the present Reimei Research Program. (author)

  6. Tritium safety study using Caisson Assembly (CATS) at TPL/JAEA

    Hayashi, T.; Kobayashi, K.; Iwai, Y.; Isobe, K.; Nakamura, H.; Kawamura, Y.; Shu, W.; Suzuki, T.; Yamada, M.; Yamanishi, T.

    2008-01-01

    Tritium confinement is required as the most important safety Junction for a fusion reactor. In order to demonstrate the confinement performance experimentally, an unique equipment, called CATS: Caisson Assembly for Tritium Safety study, was installed in Tritium Process Laboratory of Japan Atomic Energy Agency and operated for about 10 years. Tritium confinement and migration data in CATS have been accumulated and dynamic simulation code was accumulated using these data. Contamination and decontamination behavior on various materials and new safety equipment functions have been investigated under collaborations with a lot of laboratories and universities. (authors)

  7. Improvement of JCDS, a computational dosimetry system in JAEA for neutron capture therapy

    Kumada, Hiroaki; Yamamoto, Kazuyoshi; Matsumura, Akira; Yamamoto, Tetsuya; Nakagawa, Yoshinobu; Kageji, Teruyoshi

    2006-01-01

    JCDS, a computational dosimetry system for neutron capture therapy, was developed by Japan Atomic Energy Agency. The system has been sophisticated to facilitate dose planning so far. In dosimetry with JCDS for BNCT clinical trials at JRR-4, several absorbed doses and the dose distributions are determined by a voxel model consisted of 2x2x2mm 3 voxel cells. By using the detailed voxel model, accuracy of the dosimetry can be improved. Clinical trials for melanoma and head-and-neck cancer as well as brain tumor were started using hot version of JCDS in 2005. JCDS is also being of improved so as to enable a JCDS application to dosimetry by PHITS as well as dosimetry by MCNP. By using PHITS, total doses of a patient by a combined modality therapy, for example a combination of BNCT and proton therapy, can be estimated consistently. Moreover, PET images can be adopted in combination with CT and MRI images as a farsighted approach. JCDS became able to identify target regions by using the PET values. (author)

  8. Reports on JAEA's Reimei Research Program. April 1, 2011 - March 31, 2012

    Nagame, Yuichiro

    2012-10-01

    The Reimei (Dawn) Research Program is conducted based on public application to encourage original and/or unique ideas in the field of new frontier research on atomic energy sciences. Canditates for the offering have been extended beyond the country since the fiscal year of 2010. The five research subjects including three ongoing ones were accepted in the fiscal year 2011 that were carried out in collaboration with Advanced Science Research Center. The three successive projects, in particular, have achieved substantial progress through the effective international collaboration. The summaries of these research subjects are compiled in this report. We hope that new frontier research projects will be developed through the present Reimei Research Program. (author)

  9. Proposed development of novel diagnostics for intense, ultrafast laser-plasma experiments at JAEA-KPSI

    Bolton, Paul R.; Tatchyn, Roman; Fukuda, Yuji; Kando, Masaki; Daito, Izuru; Ma, Jinglong; Chen, Liming; Pirozhkov, Alexander; Tajima, Toshiki

    2007-01-01

    Development of new diagnostics is critical for future laser-plasma accelerators, laser-driven light sources and for x-ray FELs. Recent laser wakefield electron acceleration developments and novel beam-based light source schemes (such as free electron lasers) obviate the need for next generation ultrafast diagnostics, capable of temporal resolution of a few femtoseconds (and in some cases attoseconds) for laser pulses (high order harmonics), x-ray pulses and electron bunches. Single shot detection capability in noninvasive and parasitic modes is also important. Alterations of laser pulse spectra and the associated dynamics can be informative diagnostics. The portion of a high intensity laser pulse that is transmitted through a self-induced underdense plasma (such as in laser wakefield acceleration LWFA schemes) carries the effects of plasma processes it has experienced. A distinction between the self-modulated laser wakefield (SMLWF) acceleration regime and the forced laser wakefield (FLWF) acceleration regime is in the spectral signature of the transmitted ir laser pulse. The former regime generates sidebands from stimulated Raman forward scattering (SRS-F) and the latter exhibits general spectral broadening that evidences ir laser pulse compression. Transmitted spectral effects can diagnose these acceleration regimes. Existing noninvasive electro-optic (EO) schemes for detection of ultrashort electron bunches are limited by material properties to temporal resolution at the 50-100 femtosecond level. While timing jitter at conventional accelerators is of this order (or greater), single bunch longitudinal profile measurements can require improvement of at least an order of magnitude. A new FO technique is described here which monitors enhancement and associated dynamics of spectral components in a probe pulse. Three correlation schemes for detecting ultrashort x-ray pulses are described. Two-photon absorption in tailored ion targets is proposed for scanning auto-correlation detection of coherent x-ray pulses where the ion species can be adjusted according to the x-ray photon energy. The well established x-ray/ir cross-correlation obtained with Auger and photoelectron energy spectra that are modulated by coincident ir laser pulses is summarized briefly. Finally, a novel single shot, x-ray/ir cross-correlation scheme based on ir group velocity dispersion in a plasma column is described. (author)

  10. Reports on JAEA's Reimei Research Program. April 1, 2013 - March 31, 2015

    Nagame, Yuichiro

    2016-03-01

    The Reimei (Dawn) Research Program is conducted based on public application to encourage original and/or unique ideas in the field of new frontier research on atomic energy sciences. Candidates for the offering have been extended beyond the country since the fiscal year of 2010. The seven research subjects were accepted in the fiscal year of 2013, and six of them were carried out in the fiscal year of 2014, too. They have achieved substantial progress through the effective international collaboration. The summaries of these research subjects are compiled in this report. We hope that new frontier research projects will be developed through the present Reimei Research Program. (author)

  11. Nuclear power: Preparing for the future, 30 November 2006, Tokyo, Japan. Japan Atomic Energy Agency (JAEA) lecture

    ElBaradei, M.

    2006-01-01

    The public's perception of risk has a strong influence on a country's energy choices. As with civil aviation, bioengineering, or any other advanced technology, nuclear power does not come with absolute safety guarantees. What is important is that the risks and benefits are clearly understood. All members of the nuclear community - scientists, operators and safety regulators - should make every effort to provide accurate and easily understood information to improve public understanding of the risks and benefits of nuclear energy. Common misconceptions can be of great influence in shaping public acceptance of nuclear power. How a given nation balances the risk of a nuclear accident against other factors - such as air pollution, dammed rivers, mining accidents, or dependency on foreign fuel supplies - is already a matter of complexity and legitimate debate. It is essential that the nuclear community be seen as transparent and open in its activities, to increase understanding and confidence in the safe operations of nuclear facilities

  12. Sophistication of 14C measurement at JAEA-AMS-MUTSU. Attempt on a small quantity of sample

    Tanaka, Takayuki; Kabuto, Shoji; Kinoshita, Naoki; Yamamoto, Nobuo

    2010-01-01

    In the investigations on substance dynamics using the molecular weight and chemical fractionation, the utilization of 14 C measurement by an accelerator mass spectrometry (AMS) have started. As a result of the fractionation, sample contents required for AMS measurement have been downsized. We expect that this trend toward a small quantity of sample will be steadily accelerated in the future. As 14 C measurement by AMS established at Mutsu office require about 2 mg of sample content at present, our AMS lags behind the others in the trend. We try to downsize the needed sample content for 14 C measurement by our AMS. In this study, we modified the shape of the target-piece in which the sample is packed and which is regularly needed to radiocarbon measurement by our AMS. Moreover, we improved on the apparatus needed to pack the sample. As a result of the improvement, we revealed that it is possible to measure the 14 C using our AMS even by the amount of the sample of about 0.5 mg. (author)

  13. Uncertainty propagation for the coulometric measurement of the plutonium concentration in CRM126 solution provided by JAEA

    Morales-Arteaga, Maria [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-11-07

    This GUM WorkbenchTM propagation of uncertainty is for the coulometric measurement of the plutonium concentration in a Pu standard material (C126) supplied as individual aliquots that were prepared by mass. The C126 solution had been prepared and as aliquoted as standard material. Samples are aliquoted into glass vials and heated to dryness for distribution as dried nitrate. The individual plutonium aliquots were not separated chemically or otherwise purified prior to measurement by coulometry in the F/H Laboratory. Hydrogen peroxide was used for valence adjustment.

  14. Construction of monoenergetic neutron calibration fields using 45Sc(p, n)45Ti reaction at JAEA.

    Tanimura, Y; Saegusa, J; Shikaze, Y; Tsutsumi, M; Shimizu, S; Yoshizawa, M

    2007-01-01

    The 8 and 27 keV monoenergetic neutron calibration fields have been developed by using (45)Sc(p, n)(45)Ti reaction. Protons from a 4-MV Pelletron accelerator are used to bombard a thin scandium target evaporated onto a platinum disc. The proton energies are finely adjusted to the resonance to generate the 8 and 27 keV neutrons by applying a high voltage to the target assemblies. The neutron energies were measured using the time-of-flight method with a lithium glass scintillation detector. The neutron fluences at a calibration point located at 50 cm from the target were evaluated using Bonner spheres. A long counter was placed at 2.2 m from the target and at 60 degrees to the direction of the proton beam in order to monitor the fluence at the calibration point. Fluence and dose equivalent rates at the calibration point are sufficient to calibrate many types of the neutron survey metres.

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

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

    2016-07-01

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

  16. Survey on current status of laboratory test method and experimental consideration for establishing standardized procedure of material containing bentonite. Report of collaboration research between JAEA and CRIEPI (Joint research)

    Tanai, Kenji; Kikuchi, Hirohito; Nakamura, Kunihiko; Tanaka, Yukihisa; Hironaga, Michihiko

    2010-08-01

    In the current concept of repository for radioactive waste disposal, compacted bentonite as well as bentonite based material will be used as an engineered barrier mainly for inhibiting migration of radioactive nuclides. In most cases, properties of bentonite, such as low permeability etc., are obtained by laboratory tests. However, results of laboratory tests of bentonite often vary considerably even if index parameter, such as effective clay density, is constant. One of the causes of the variability is considered to be lack of standardized method of laboratory test for bentonite. Thus standardization of laboratory test methods for bentonite is needed. So, investigation for establishing standardized laboratory test method of bentonite is conducted based on the results of survey on current status of laboratory test method for bentonite. In particular, the literature survey as well as laboratory tests were conducted to find factors affecting the results of laboratory tests for bentonite and to estimate their degree of influence. The following conclusions are obtained through this study. (1) Hydraulic conductivity test. According to the results of literature survey, it is revealed that constant pressure permeability test and consolidation test are currently used for measuring hydraulic conductivity of bentonite and that (a) hydraulic gradient, (b) local seepage flow between lateral surface of the specimen and lateral wall of the container, (c) water pressure which is applied to the specimen, (d) degree of saturation and (e) size of the specimen possibly affect the results of the constant pressure permeability test, while (f) friction between lateral surface of the specimen and lateral wall of the container accompanied by deformation of the specimen, (g) consolidation pressure together with factors (d), (e) affect the results of the consolidation test. Literature which describes that factors (a), (b) and (e) affect the results of the constant pressure permeability test is not found. In the constant pressure permeability test, the effect of factor (c) can be avoided by setting applied water pressure difference for seepage flow smaller than the swelling pressure. In the constant pressure permeability test, the effect of factor (d) is also avoided by infiltrating water into the specimen one-dimensionally so that air does not remain in the specimen and by applying back pressure during seepage flow test. In the consolidation test, a correction method for the effect of friction is needed because the effect of the factor (f) is inevitable. It is revealed that one-dimensionally infiltration of water into the specimen is difficult because of the structure of the consolidation test apparatus. There is no literature which describes the effects of factors (e) and (g) on the results of the consolidation test conducted for bentonite specimen. According to the reasons mentioned above, it is currently desirable to use the constant pressure permeability test for compacted bentonite. (2) Swelling pressure test. According to the literature survey, confined type testing apparatuses and apparatuses which are similar to the consolidation test apparatuses are used for measuring swelling pressure. Factors affecting results of swelling pressure tests are saturation of the specimen, size of the specimen and difference of apparatus. Saturation of the specimen set in confined type testing apparatus can be raised easily by one-dimensional infiltration of water through the specimen and by applying backpressure. It is revealed that size of the specimen affects the test results if effective clay density is larger than 1.6 Mg/m 3 . Though swelling pressure measured by the confined type test apparatus is larger than that by apparatuses which are similar to the consolidation test apparatuses, further study is needed to clarify the cause of the difference. (3) Thermophysical properties measurement. There seems no problem in measuring thermal conductivity and thermal diffusivity by the current four methods for uniformly mixed specimens of sand-bentonite mixture. However, heterogeneity of sand content and moisture content in the specimen affects the results of measurement. Therefore, procedure for mixing bentonite and admixture uniform and procedure for prohibiting migration of water content by covering the specimen by wrapping are necessary. (author)

  17. The birth of the J-PARC

    Nagamiya, Shoji

    2008-01-01

    The J-PARC Project started in 2001 as a joint project between two organizations, JAEA and KEK. This article describes a) an early history on how people struggled to construct high-intensity proton accelerators, b) a creation of a joint effort between JAEA and KEK, and c) the birth of the J-PARC. (author)

  18. Progress report on neutron science. April 1, 2005 - March 31, 2006

    Moriai, Atsushi; Takeda, Masayasu; Kurihara, Kazuo

    2007-03-01

    This issue summarizes research progress in neutron science at Japan Atomic Energy Agency (JAEA) by utilizing the research reactor JRR-3 during the period between April 1, 2005 and March 31, 2006. This report contains highlights in research by 13 neutron research groups at JAEA and 89 summary articles. (author)

  19. The remote transmission test of the GUAM measurement data by the wireless LAN

    Asano, Takashi; Fujiwara, Shigeo; Takahashi, Saburo; Nemoto, Tadayuki; Sato, Takashi; Kuniyasu, Kazufusa; Hiruta, Kazuhiko

    2008-01-01

    JAEA has developed and demonstrated the Remote Monitoring (RM) technology on the safeguards equipment at the storage area in PFPF to improve the efficiency of the inspection activity. JAEA is considering the expansion of the RM technology to the safeguards equipment in the process area to improve the efficiency of the inspection activity under the integrated safeguards. JAEA considers that the cabling cost and work in the facility will be reduced to apply the wireless LAN to the RM technology. JAEA performed the confirmatory testing of the performance of the Glove box Unattended Assay and Monitoring system (GUAM) and the remote transmission of the GUAM measurement data by the wireless LAN in cooperation with Japan Nuclear Fuel Limited. In this test, JAEA confirmed it's possible to establish the wireless LAN networking in the process area. This paper reports the applicability of the wireless LAN to the RM technology based on the results of the confirmatory testing. (author)

  20. Progress in radiation application to industry and agriculture

    Kume, Tamikazu

    2006-01-01

    Utilization of radiation in Japan has been actively promoted by various agencies including the Takasaki Radiation Chemistry Research Establishment of JAERI (presently Japan Atomic Energy Agency: JAEA). The JAEA-Takasaki was established in April 1963 for the purpose of promoting research and development (R and D) activities with gamma rays and electron beams. The JAEA-Takasaki's activities were addressed principally to industry and agriculture. In Japan, purpose of utilization of radiation is aiming at increasing welfare and quality of life of our peoples. (author)

  1. Minutes of 'Technical Committee for Geological Isolation Research and Development (1st time)'

    Sasaki, Yasuo; Torata, Shinichiro

    2007-03-01

    In order to plan and conduct a program of research and development (R and D) for geological disposal of high-level radioactive waste in JAEA-Tokai, JAEA decided to receive technical comments and advices from the Technical Committee for geological isolation R and D. This committee, which is constituted of specialists who do not belong to JAEA, has evaluated the program, taking into account of the status of geological disposal technology in Japan as well as foreign countries. This report compiles the minutes of the first meeting held in July 2006. (author)

  2. The evaluation outline to 'root cause analysis report (revision) of the event which the penetration hole generated by the main exhaust pipe duct of the reprocessing plant' reported by Japan Atomic Energy Agency

    2013-06-01

    JNES evaluated the report which JAEA presented in October 2012 at the Nuclear Regulation Authority on the root cause analysis regarding the penetration hole on the main exhaust pipe duct in the JAEA reprocessing plant. The evaluation of the root cause analysis was done based on the guideline of the Regulation Authority evaluating the root cause analysis carried out by the enterprise side and concluded that the evaluation extending as to JAEA's organizational system was effective as a countermeasure for a recurrence, the present report representing the outline of the evaluation. (S. Ohno)

  3. Role of technical reports as a means of scientific information distribution in the field of nuclear science and technology

    Ishikawa, Masashi

    2013-06-01

    Japan Atomic Energy Agency (JAEA) has published more than twenty-thousand technical reports on the internet to provide detailed results of research and development activities. In JAEA technical reports, detailed results, experimental data, findings etc. are recorded. Technical report is effective for communication among scientists and engineers for research development in a big science like nuclear research. The number of downloads of JAEA technical reports is over 4.7 million per a year. Technical reports have many advantages for carrying research results of big projects than journal articles. It is also useful for knowledge management to transfer research results and achievements to the following generation. To improve JAEA technical reports to meet the needs of scientists and engineers and assisting the knowledge management is proposed. (author)

  4. Establishment of Japan Atomic Energy Agency and strategy for nuclear non-proliferation studies

    Senzaki, Masao; Kurasaki, Takaaki; Inoue, Naoko

    2005-01-01

    Japan Atomic Energy Agency (JAEA) was established on October 1, 2005, after the merger of Japan Atomic Energy Research Institute and Japan Nuclear Cycle Development Institute. JAEA is the only governmental nuclear research and development institute in Japan. It will engage in research activities ranging from basic research to practical applications in the nuclear field and will operate research laboratories, reactors, a reprocessing plant and a fuel fabrication plant. At the same time, the Nuclear Nonproliferation Science and Technology Center (NPSTC) was also established inside of JAEA to conduct the studies on the strategy for nuclear nonproliferation studies. Five roles that JAEA should play for nuclear nonproliferation were identified and four offices were established in the center to carry out those five roles effectively. To conduct the research and development for nuclear nonproliferation efficiently, the center aims to be a 'Research Hub' based on Partnership' with other organizations. (author)

  5. Activities on Fast Reactor Knowledge Preservation in Japan

    Uto, Nariaki; Ohira, Hiroaki

    2013-01-01

    Japanese FRs are stepping up from Joyo, Monju to JSFR with efforts to overcome the Fukushima no. 1 Nuclear Power Station Accidents, including focus on ensuring and enhancing safety of these FRs. Japan (JAEA) has made continuous and contributive efforts to supply FR information to IAEA/INIS. JAEA has also contributed to a global dissemination of its R&D activities through JOPSS English version, which will be beneficial to worldwide FR development

  6. Prospects for regional cooperation. Regional cooperation in remote monitoring for nuclear nonproliferation and transparency

    Olsen, John

    2006-01-01

    The JAEA and Sandia National Laboratories (SNL) have cooperated for a decade in development and testing of remote monitoring technologies in support of international safeguards. With this technology approaching maturity, the JAEA/SNL partnership now envisions regional cooperation to use these technologies to advance nuclear transparency and strengthen nonproliferation, as well. This presentation summarizes the technical evolution and notes the opportunity for regional cooperation to include institutions in the ROK, as well as Japan and the US. (author)

  7. International standardization of instruments for neutron irradiation tests

    Tanimoto, Masataka; Shibata, Akira; Nakamura, Jinichi; Tsuchiya, Kunihiko; Cho, M.; Lee, C.; Park, S.; Choo, K.

    2012-01-01

    The JMTR in JAEA and HANARO in KAERI are the foremost testing/research reactors in the world and these are expected to contribute to many nuclear fields. As a part of instrument development in irradiation field, information exchange of instruments started from 2010 under the cooperation agreements between KAERI and JAEA. The instruments developed in JMTR and HANARO are introduced and cooperation experiments as future plan are discussed for international standardization. (author)

  8. CoolRep H22: Synthesis report on R and D results on geological disposal up to 2009

    Umeki, Hiroyuki; Hioki, Kazumasa; Osawa, Hideaki; Fujita, Tomoo; Shibata, Masahiro; Makino, Hitoshi; Takeuchi, Shinji; Ishimaru, Tsuneari

    2011-02-01

    The Japan Atomic Energy Agency (JAEA) has been performing research and development on geological disposal technology of high level radioactive waste. At the end of fiscal year 2009, the Geological Isolation Research and Development Directorate of JAEA made publicly available the 'CoolRep H22', which is a web-based report that summarizes the R and D results, on its website. This document reports the contents of CoolRep H22. (author)

  9. Annual report of Nuclear Emergency Assistance and Training Center. April 1, 2010 - March 31, 2011

    Katagiri, Hiromi; Okuno, Hiroshi; Sawahata, Masayoshi; Ikeda, Takeshi; Sato, Sohei; Terakado, Naoya; Nagakura, Tomohiro; Nakanishi, Chika; Fukumoto, Masahiro; Yamamoto, Kazuya; Abe, Minako; Kawakami, Takeshi; Kikuchi, Masayuki; Sumiya, Akihiro; Matsusaka, Masaru

    2011-12-01

    When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (JAEA) has the responsibility of providing technical support to the National government, local governments, police, fire station and license holders etc., because the JAEA is designated a Public Organization conforming to the Basic Law on Emergency Preparedness and the Basic Plan for Disaster Countermeasures. The Nuclear Emergency Assistance and Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an Off-Site Center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, dispatch specialists as required, supplies emergency equipment and materials to the National Government and local governments. NEAT provides various lectures and training courses concerning nuclear disaster prevention for those personnel taking an active part in emergency response organizations at normal time. NEAT also researches on nuclear disaster prevention and cooperates with international organizations. Concerning about the assistance to the Accident of Fukushima No.1 Nuclear Power Station caused by the Great East Japan Earthquake at 11 March, 2011, JAEA assisted activities including environmental radiation monitoring, environmental radioactivity analyses, resident public consulting etc., with its full scale effort. NEAT served as the center of these supporting activities of JAEA. This annual report summarized these activities of JAEA/NEAT in the fiscal year 2010. (author)

  10. Annual report of Nuclear Emergency Assistance and Training Center. April 1, 2011 - March 31, 2012

    Katagiri, Hiromi; Okuno, Hiroshi; Okamoto, Akiko; Ikeda, Takeshi; Tamura, Kenichi; Nagakura, Tomohiro; Nakanishi, Chika; Yamamoto, Kazuya; Abe, Minako; Sato, Sohei; Kawakami, Takeshi; Kikuchi, Masayuki; Sumiya, Akihiro; Matsusaka, Masaru

    2012-08-01

    When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (JAEA) has the responsibility of providing technical support to the National government, local governments, police, fire stations and nuclear operators etc., because the JAEA has been designated as the Designated Public Institution under the Basic Act on Disaster Control Measures and the Act on Response to Armed Attack Situations, etc.. The Nuclear Emergency Assistance and Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an Off-Site Center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, dispatches specialists as required, and supplies the National Government and local governments with emergency equipments and materials. NEAT provides various exercise and training courses concerning nuclear disaster prevention to those personnel taking an active part in emergency response organizations at normal times. NEAT also researches on nuclear disaster prevention and cooperates with international organizations. Concerning the assistance to the Accident at Fukushima Nuclear Power Station caused by the Great East Japan Earthquake on 11 March, 2011, JAEA has assisted activities including environmental radiation monitoring, environmental radioactivity analyses, and response to telephone inquiries from residents etc., with utmost effort. NEAT has served as the center of these supporting activities of JAEA. This annual report summarized these activities of JAEA/NEAT in the fiscal year 2011. (author)

  11. Evaluated and estimated solubility of some elements for performance assessment of geological disposal of high-level radioactive waste using updated version of thermodynamic database

    Kitamura, Akira; Doi, Reisuke; Yoshida, Yasushi

    2011-01-01

    Japan Atomic Energy Agency (JAEA) established the thermodynamic database (JAEA-TDB) for performance assessment of geological disposal of high-level radioactive waste (HLW) and TRU waste. Twenty-five elements which were important for the performance assessment of geological disposal were selected for the database. JAEA-TDB enhanced reliability of evaluation and estimation of their solubility through selecting the latest and the most reliable thermodynamic data at present. We evaluated and estimated solubility of the 25 elements in the simulated porewaters established in the 'Second Progress Report for Safety Assessment of Geological Disposal of HLW in Japan' using the JAEA-TDB and compared with those using the previous thermodynamic database (JNC-TDB). It was found that most of the evaluated and estimated solubility values were not changed drastically, but the solubility and speciation of dominant aqueous species for some elements using the JAEA-TDB were different from those using the JNC-TDB. We discussed about how to provide reliable solubility values for the performance assessment. (author)

  12. The uranium waste fluid processing examination by liquid and liquid extraction method using the emulsion flow method

    Kanda, Nobuhiro; Daiten, Masaki; Endo, Yuji; Yoshida, Hideaki; Mita, Yutaka; Naganawa, Hirochika; Nagano, Tetsushi; Yanase, Nobuyuki

    2015-03-01

    Spent centrifuges which had used for the development of the uranium enrichment technology are stored in the uranium enrichment facility located in Ningyo-toge Environmental Center, Japan Atomic Energy Agency (JAEA). Our technology of the centrifugal machine processing are supposed to separate the radioactive material adhered on surface of inner parts of centrifuges by the wet way decontamination method using the ultrasonic bath filled dilute sulfuric acid and water, and it is generated the neutralization sediment (sludge) by the processing of the radioactive waste fluid with the decontamination. JAEA had been considering the applicability of a streamlining and reduction of the processing of the sludge by decreases radioactive concentration including the sludge through the removes uranium from the radioactive waste fluid. As part of considerations, JAEA have been promoting technological developments of the uranium extraction separation using The Emulsion Flow Extraction Method (a theory propounded by JAEA-Nuclear Science and Engineering Center) in close coordination and cooperation between with JAEA-Nuclear Science and Engineering Center and Ningyo-toge Environmental Center from 2007 fiscal year. This report describes the outline of the application test using actual waste fluid of dilute sulfuric acid and water by developed the examination system introducing the emulsion flow extraction method. (author)

  13. From neutron science project to J-PARC. From the viewpoint of JAERI

    Oyama, Yukio

    2006-01-01

    Japan Atomic Energy Research Institute (JAERI), at present Japan Atomic Energy Agency (JAEA), has been developing particle accelerators since its establishment in 1956 for obtaining basic data on the neutron. Also reactor-based neutron sciences have been developed at JAERI/JAEA. Under the so-called omega project which was started in 1988, JAERI/JAEA has been conducting researches on Engineering Test Accelerator for the nuclear transmutation and has built a Basic Test Accelerator. In 1996, a special team for neutron science promotion was organized and pushed R and D works on proton accelerators, targets, neutron engineering, radiation safety and so on. Integration of proton accelerator projects at JAERI and KEK (Institute for High Energy Physics) was proposed in 1998, and both institutes agreed to establish a unified proton accelerator facility, J-PARC. JAEA is promoting the industrial application of neutrons. Also the research on nuclear transmutation at J-PARC, which is not endorsed yet, is an essential objective for JAEA. (K.Y.)

  14. Preparation and evaluation of reference materials for accountancy analysis. (2) Evaluation results

    Sumi, Mika; Abe, Katsuo; Kageyama, Tomio; Nakazawa, Hiroaki; Takamatsu, Mai; Kacchi, Tomokazu; Murakami, Toshiki; Ai, Hironobu

    2009-01-01

    Destructive analysis for accountancy at nuclear fuel facilities should attain international target values for measurement uncertainties in safeguarding nuclear materials (ITVs). Since measurement uncertainties of isotope dilution mass spectrometry depend on uncertainties of spikes (standard materials) used, utilizing highly reliable standard material is essential. The LSD spikes prepared under collaboration work with JAEA and JNFL has different Pu/U ratio and smaller nuclear material in a spike compared with the LSD spikes used a safeguard laboratories, and the value of Pu which separated and purified from MOX and used as raw material for one of the LSD spike prepared at JAEA were measured at JAEA. Uncertainties of the prepared LSD spikes and the measurement results of actual samples with these LSD spikes were evaluated based on ISO-GUM and compared with ITVs. (author)

  15. Mizunami Underground Research Laboratory Project. Annual report for fiscal year 2015

    Hama, Katsuhiro; Iwatsuki, Teruki; Matsui, Hiroya; Mikake, Shinichiro; Ishibashi, Masayuki; Onoe, Hironori; Takeuchi, Ryuji; Nohara, Tsuyoshi; Sasao, Eiji; Ikeda, Koki; Koide, Kaoru

    2016-12-01

    The Mizunami Underground Research Laboratory (MIU) project is being pursued by the Japan Atomic Energy Agency (JAEA) to enhance the reliability of geological disposal technologies through investigations of the deep geological environment in the crystalline host rock (granite) at Mizunami City in Gifu Prefecture, central Japan. On the occasion of the research program and management system revision of the entire JAEA organization in 2014, JAEA identified three important issues on the geoscientific research program: 'Development of countermeasure technologies for reducing groundwater inflow', 'Development of modeling technologies for mass transport' and 'Development of drift backfilling technologies', based on the latest results of the synthesizing research and development (R and D). The R and D on three important issues has been carrying out on the MIU project. In this report, the current status of R and D activities and construction in 2015 is summarized. (author)

  16. Progress report on neutron science. April 1, 2006 - March 31, 2007

    Takeda, Masayasu; Ohhara, Takashi; Moriai, Atsushi

    2008-03-01

    There are 13 research groups in neutron science and technology in the Quantum Beam Science Directorate (QuBS) and Advanced Science Research Center (ASRC) of Japan Atomic Research Agency (JAEA). A wide variety of research is performed by these group: neutron scattering (condensed matter physics, polymer science, biology, and residual stress analysis), prompt gamma-ray analysis, neutron radiography, neutron optics, and development of a neutron spectrometer, neutron beam handling device and neutron detector. This issue summarizes research progress in neutron science and technology including activities of the Nuclear Science and Engineering Directorate of JAEA, and of the COMMON USE PROGRAM of JAEA utilizing the research reactor JRR-3 during the period between April 1, 2006 and March 31, 2007. This report contains highlights of research by these 13 neutron research groups of QuBS and ASRC, introducing 68 experimental reports. (author)

  17. Review of research on simulation engineering in FY2009

    2011-03-01

    Research on simulation engineering for nuclear applications, based on 'the plan for meeting the mid-term goal of the Japan Atomic Energy Agency', has been performed at Center for Computational Science and e-Systems, Japan Atomic Energy Agency (CCSE/JAEA). CCSE established the committee consisting outside experts and authorities which does research evaluation and advices for the assistance of the research and development. This report summarizes results of the evaluation by the committee on the followings. (1) Research and development on simulation engineering performed at CCSE/JAEA in FY2009. (2) Research and development on simulation engineering performed at CCSE/JAEA in the period of the midterm plan (October 1st, 2005 - March 31st, 2010). (author)

  18. Laser R and D project in this 5-year term

    Sugiyama, Akira; Kiriyama, Hiromitsu; Ochi, Yoshihiro; Mori, Michiaki; Tanaka, Momoko; Sasao, Fumitaka; Kosuge, Atsushi; Okada, Hajime

    2011-01-01

    Main theme of our group in this middle term JAEA program is a development of high-averaged power short pulse laser system pumped by LDs (laser diodes). To realize this next term laser system, we have just started considering a Yb doped ceramics laser with a several members of KPSI. We have also developed a laser system named QUADRA (high-Quality Ultra ADvanced RAdiation Sources) in C-Phost program. In the first term up to FYH22, essential studies for QUADRA have been investigated. In the second term, QUADRA development will be merged with the next term laser system in JAEA to produce high powered THz radiation. In addition to these developments, we support to improve the performances of conventional high-power laser system, J-KAREN for the requirement of advanced application studies in this middle term JAEA program. (author)

  19. Current status and a short history of grey literature. Focusing on the international conference on grey literature

    Ikeda, Kiyoshi

    2010-01-01

    'Grey literature' is a loosely defined term whose application is rather complex, but it is also an important source of information for academic researchers. Today, the spread of the Internet has led to changes not only in the circulation but also in the role and definition of 'grey literature'. This article therefore presents a short history of the definition of 'grey literature', with central focus on topics discussed by the International Conference on Grey Literature. After this, the current status and future prospects of 'grey literature' in the digital society are described. Finally, the article introduces the JAEA Library's activities on 'grey literature', particularly the acquisition of proceedings and the editing and dissemination of the JAEA Reports (technical reports of JAEA). (author)

  20. Evaluating and categorizing the reliability of distribution coefficient values in the sorption database (4)

    Suyama, Tadahiro; Tachi, Yukio; Ganter, Charlotte; Kunze, Susanne; Ochs, Michael

    2011-02-01

    Sorption of radionuclides in bentonites and rocks is one of the key processes in the safe geological disposal of radioactive waste. Japan Atomic Energy Agency (JAEA) has developed sorption database (JAEA-SDB) which includes extensive compilation of sorption K d data by batch experiments, extracted from published literatures. JAEA published the first SDB as an important basis for the H12 performance assessment (PA), and has been continuing to improve and update the SDB in view of potential future data needs, focusing on assuring the desired quality level and practical applications to K d -setting for the geological environment. The JAEA-SDB includes more than 24,000 K d data which are related with various conditions and methods, and different reliabilities. Accordingly, the quality assuring (QA) and classifying guideline/criteria has been developed in order to evaluate the reliability of each K d value. The reliability of K d values of key radionuclides for bentonite, mudstone, granite and Fe-oxide/hydroxide, Al-oxide/hydroxide has been already evaluated. These QA information has been made available to access through the web-based JAEA-SDB since March, 2009. In this report, the QA/classification of selected entries in the JAEA-SDB, focusing on key radionuclides (Th, Np, Am, Se and Cs) sorption on tuff existing widely in geological environment, was done following the approach/guideline defined in our previous report. As a result, the reliability of 560 K d values was evaluated and classified. This classification scheme is expected to make it possible to obtain quick overview of the available data from the SDB, and to have suitable access to the respective data for K d -setting in PA. (author)

  1. Evaluating and categorizing the reliability of distribution coefficient values in the sorption database (3)

    Ochs, Michael; Kunze, Susanne; Suyama, Tadahiro; Tachi, Yukio; Yui, Mikazu

    2010-02-01

    Sorption of radionuclides in bentonites and rocks is one of the key processes in the safe geological disposal of radioactive waste. Japan Atomic Energy Agency (JAEA) has developed sorption database (JAEA-SDB) which includes extensive compilation of sorption K d data by batch experiments, extracted from published literatures. JAEA published the first SDB as an important basis for the H12 performance assessment (PA), and has been continuing to improve and update the SDB in view of potential future data needs, focusing on assuring the desired quality level and practical applications to K d -setting for the geological environment. The JAEA-SDB includes more than 24,000 K d data which are related with various conditions and methods, and different reliabilities. Accordingly, the quality assuring (QA) and classifying guideline/criteria has been developed in order to evaluate the reliability of each K d value. The reliability of K d values of key radionuclides for bentonite and mudstone system has been already evaluated. To use these QA information, the new web-based JAEA-SDB was published in March, 2009. In this report, the QA/classification of selected entries for key radionuclides (Th, Np, Am, Se and Cs) in the JAEA-SDB was done following the approach/guideline defined in our previous report focusing granite rocks which are related to reference systems in H12 PA and possible applications in the context of URL activities, and Fe-oxide/hydroxide, Al-oxide/hydroxide existing widely in geological environment. As a result, the reliability of 1,373 K d values was evaluated and classified. This classification scheme is expected to make it possible to obtain quick overview of the available data from the SDB, and to have suitable access to the respective data for K d -setting in PA. (author)

  2. Conceptual design study of high temperature gas-cooled reactor for plutonium incineration

    Goto, Minoru

    2013-01-01

    JAEA has started a conceptual design study of a Pu burner HTGR, which is called CBHTR (Clean Burn High Temperature gas-cooled Reactor). CBHTR’s fuel is TRISO-coated fuel particle with PuO 2 -YSZ (Yttria- Stabilized Zirconia) kernel, which increase proliferation resistance, safety of geological disposal, and Pu incineration. CBHTR can decrease Puf ratio from 60% to 20% with 520 GWd/t. In the future, 15% of electricity capacity is employed by 7 of CBHTRs and 59 of U-HTRs. JAEA has a R and D plan of manufacturing technology of TRISO-coated fuel with PuO 2 -YSZ kernel

  3. Public meetings on radiation and its health effects caused by the Fukushima nuclear accident

    Sugiyama, K.; Ayame, J.; Takashita, H.; Yamamoto, R.

    2013-01-01

    The Japan Atomic Energy Agency (JAEA) has held public meetings on radiation and its health effects mainly for parents of students in kindergartens, elementary schools, and junior high schools in Fukushima and Ibaraki prefectures after the Fukushima nuclear accident. These meetings are held based on our experience of practicing risk communication activities for a decade in JAEA with local residents. By analyzing questionnaires collected after the meetings, we confirmed that interactive communication is effective in increasing participants' understanding and in decreasing their anxiety. Most of the participants answered that they understood the contents and that it eased their mind. (authors)

  4. The performance of photons rainbow-colored energy experimental lecture schools in the kids' science museum of photons

    Hoshiya, Taiji; Sasaki, Kazuya; Nishikawa, Masahiro

    2008-01-01

    The Kansai Photon Science Institute (KPSI) of Japan Atomic Energy Agency (JAEA) has been promoting various activities of public understanding of science and technology, to be focused on the photon science, which is characterized by activities on science lectures and science events based on science and experiment classrooms, by utilizing the science museum of the JAEA (The Kids' Science Museum of Photons). In this phase, the KPSI extends systematically trial activities of the science museum to be as an experimental apparatus for studying on science and technology, including the program for promoting activities on public understanding of science and technology at the region. (author)

  5. Seawater movement in the Japan Sea inferred from 14C measurement in seawater

    Otosaka, Shigeyoshi; Tanaka, Takayuki; Togawa, Orihiko; Amano, Hikaru; Aramaki, Takafumi

    2008-01-01

    Research Group for Environmental Science, JAEA has carried out oceanographic observations in the Japan Sea since 1997 to clarify the biogeochemical cycle in the Japan Sea. More than 3,000 seawater samples for measurement of radiocarbon were collected during the observations, and radiocarbon in the seawater samples was measured at AMS facility in JAEA Mutsu. In this paper, formation and circulation of water mass in the northern Japan Sea were discussed using analysis of radiocarbon and hydrographic data (e.g. salinity, temperature, nutrients). (author)

  6. Analysis on the atmospheric dispersion of radioactive materials

    Nagai, Haruyasu

    2012-01-01

    JAEA has been developing a new prediction system of comprehensive movement, SPEEDI-MP (SPEEDI Multi-model Package), which can treat continuously and strictly with the migration behavior of radioactive materials at atmosphere, sea, and land region. JAEA has been further promoting the detail analysis of atmospheric migration of radioactive materials dispersed by an accident. Then, using a part of this system, the atmospheric-diversion prediction system, WSPEEDI-II, the atmospheric diversion mass and the atmospheric diffusion analysis were carried out. This issue reports the summary. (M.H.)

  7. Review of research on simulation engineering in FY2007

    2009-02-01

    Research on simulation engineering for nuclear applications, based on the plan for meeting the mid-term goal of the Japan Atomic Energy Agency', has been performed at Center for Computational Science and e-Systems, Japan Atomic Energy Agency (CCSE/JAEA). CCSE established the committee consisting outside experts and authorities which does research evaluation and advices for the assistance of the research and development. This report summarizes the result of the evaluation by the committee on the research on simulation engineering performed at CCSE/JAEA in FY2007. (author)

  8. Review of research on simulation engineering in FY2008

    2010-02-01

    Research on simulation engineering for nuclear applications, based on 'the plan for meeting the mid-term goal of the Japan Atomic Energy Agency', has been performed at Center for Computational Science and e-Systems, Japan Atomic Energy Agency (CCSE/JAEA). CCSE established the committee consisting outside experts and authorities which does research evaluation and advices for the assistance of the research and development. This report summarizes the result of the evaluation by the committee on the research on simulation engineering performed at CCSE/JAEA in FY2008. (author)

  9. Environmental performance data in environmental report 2015

    Suzuki, Yurina; Kanai, Katsuta; Sato, Sadayuki; Tatebe, Kazuaki

    2016-03-01

    In September, 2015 Japan Atomic Energy Agency (JAEA) published the Environmental Report 2015 concerning the activities of FY 2014 under 'Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc., by Facilitating Access to Environmental Information, and Other Measures'. This report has been edited to show detailed environmental performance data in FY 2014 as the base of the Environmental Report 2015. This report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA. (author)

  10. Proceedings of the 10th symposium on advanced photon research

    2010-06-01

    The 10th Symposium on Advanced Photon Research was held at Kansai Photon Science Institute, Japan Atomic Energy Agency (JAEA-KPSI) in Kizugawa, Kyoto on October 21 - 22, 2009. This report consists of invited and contributed papers presented at the oral and poster sessions in the Symposium. The 38 of the presented papers are indexed individually. (J.P.N.)

  11. Present status and future plans of the study for preparation of Pu reference materials

    Sumi, Mika; Kageyama, Tomio; Suzuki, Toru

    2007-01-01

    All accountancy analysis at the Plutonium Fuel Development Center of JAEA is performed by isotope dilution mass spectrometry with well-characterized standard materials. Though Pu reference materials has been supplied from foreign country, importing those Pu materials is gradually becoming more difficult and may be almost impossible to import them in future. Thus, in order to establish the capability and expertise for the preparation of Pu reference materials, JAEA has started collaborative work with NBL who has high skills for preparing and supplying nuclear reference materials for long periods. One of the targets of this collaboration is preparation of standard material for IDMS (LSD spike). MOX powder which has been stored in JAEA was dissolved and Purified to obtain Pu solution. A small portion of the Purified solution was transported to NBL for analysis. LSD spike will be prepared from this Pu solution and then validation analysis and performance test including stability test will be performed with NBL and JAEA. This report presents status and future plans for the collaboration work. (author)

  12. Future for nuclear data research. Human resources

    Baba, Mamoru

    2006-01-01

    A comment is given on the problem of human resources to support the future nuclear data activity which will be indispensable for advanced utilization of nuclear energy and radiations. Emphasis is put in the importance of the functional organization among the nuclear data center (JAEA), industries and universities for provision of human resources. (author)

  13. R and D in support of ASTRID and JSFR: cross-analysis and identification of possible areas of cooperation

    Devictor, Nicolas; Chikazawa, Yoshitaka; Saez, Manuel; Rodriguez, Gilles; Hayafune, Hiroki

    2013-01-01

    The Commissariat a L'energie Atomique et aux energies Alternatives (CEA) and the Japan Atomic Energy Agency (JAEA) intend to develop prototype or demonstration sodium-cooled fast reactors (SFRs) within two decades. The common final goal of their respective programs is SFR commercialization. The target of a commercial SFR for CEA and JAEA is basically consistent with Generation IV goals. Based on their industrial backgrounds and feedback from past and existing reactor experiences, CEA and JAEA have selected pool and loop configurations for the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) and the Japanese Sodium-Cooled Fast Reactor (JSFR), respectively. CEA and JAEA have cross-analyzed both pool and loop concepts (ASTRID and demonstration JSFR, respectively). The analysis results show that both concepts are technologically feasible and meet design goals. From the viewpoint of collaboration, the analysis identifies a wide range of collaborative areas in several fields: design principles (e.g., design target and design standard); development of components and systems; development of component parts, devices, or subsystems; design methods; simulation tools; etc.(authors)

  14. General-purpose Monte Carlo codes for neutron and photon transport calculations. MVP version 3

    Nagaya, Yasunobu

    2017-01-01

    JAEA has developed a general-purpose neutron/photon transport Monte Carlo code MVP. This paper describes the recent development of the MVP code and reviews the basic features and capabilities. In addition, capabilities implemented in Version 3 are also described. (author)

  15. Research of the tasks on risk communication enforcement (Contract research)

    Tanaka, Masaru; Aoyama, Isao; Ishizaka, Kaoru; Ohata, Yuki; Fukuike, Iori; Miyagawa, Hiroshi; Ishimori, Yuu

    2017-01-01

    From 1955 to 2001, Japan Atomic Energy Agency (JAEA) carried out research and development projects related to uranium exploration, mining, refining, conversion and enrichment at/around Ningyo-toge in Japan. Subsequently, JAEA has been carrying out remediation of the uranium mine legacy sites and decommissioning of the nuclear fuel cycle facilities. JAEA has many experiences of communication with local stakeholders from these projects. Among such experiences, management of the waste rock sites became local concern in 1988, 27 years after completion of the exploration. The issue was resolved in 2012 after several efforts. From this experience, it was suggested that the lack of information sharing with local stakeholders and that the inadequate support to stakeholder's requests caused the delay of problem solving. Therefore, sustainable relationship with local stakeholders for over decades is important for JAEA Ningyo-toge Environmental Engineering Center. As reference, similar domestic cases were investigated and strategies for risk communication were planned. As follows; (1) Clarify roles and responsibilities of communication staffs for sustainable communicating with local residents. (2) Identify gaps in risk communication knowledge among center and local residents and work toward filling those gaps. (3) Improve the effectiveness of Ningyo-toge center's website and PR-magazines as primary mechanism for communicating with wide stakeholders. (4) Investigate new communication methods for sustainable communicating, such as combination of environmental restoration studies by experts and environmental learning activities by residents. (author)

  16. Progress of the research and development on the geological disposal technology of HLW with aid of the industry/university collaboration system and fixed term researcher system

    Yamada, Fumitaka; Sonobe, Hitoshi; Igarashi, Hiroshi

    2008-02-01

    In Japan Atomic Energy Agency (JAEA), various systems associated with the collaboration with industries and universities on the Nuclear Fuel Cycle and the Postdoctoral Fellow system, etc. are enacted. These systems have been operated considering the needs of JAEA's program, industry and academia, resultantly contributed, for example, to basic research and the project development. The activities under these collaboration systems contain personal exchanges, the publication of the accomplishments and utilization of those, in research and development concerning geological disposal technology of high-level radioactive waste (HLW). These activities have progressed in Power Reactor and Nuclear Fuel Development Corporation (PNC) and Japan Nuclear Cycle Development Institute (JNC), which are the successive predecessors of JAEA, through JAEA. The accomplishments from these systems have been not only published as papers in journals and individual technical reports but also integrated into the project reports, accordingly contributed to the advancement of the national program on the geological disposal of HLW. In this report, the progress of the research and development under these systems was investigated from the beginning of the operation of the systems. The contribution to the research and development on geological disposal technology of HLW was also studied. On the basis of these studies, the future utilization of the systems of the collaboration was also discussed from the view point of the management of research and development program. A CD-ROM is attached as an appendix. (J.P.N.)

  17. Proceedings of the 13th symposium on advanced photon research

    2013-09-01

    The 13th Symposium on Advanced Photon Research was held at Kansai Photon Science Institute, Japan Atomic Energy Agency (JAEA-KPSI) in Kizugawa-shi, Kyoto on November 15 - 16, 2012. This report consists of invited and contributed papers presented at the oral and poster sessions in the Symposium. (author)

  18. Design, fabrication and transportation of Si rotating device

    Kimura, Nobuaki; Imaizumi, Tomomi; Takemoto, Noriyuki; Tanimoto, Masataka; Saito, Takashi; Hori, Naohiko; Tsuchiya, Kunihiko; Romanova, Nataliya; Gizatulin, Shamil; Martyushov, Alexandr; Nakipov, Darkhan; Chakrov, Petr; Tanaka, Futoshi; Nakajima, Takeshi

    2012-06-01

    Si semiconductor production by Neutron Transmutation Doping (NTD) method using the Japan Materials Testing Reactor (JMTR) has been investigated in Neutron Irradiation and Testing Reactor Center, Japan Atomic Energy Agency (JAEA) in order to expand industry use. As a part of investigations, irradiation test of silicon ingot for development of NTD-Si with high quality was planned using WWR-K in Institute of Nuclear Physics (INP), National Nuclear Center of Republic of Kazakhstan (NNC-RK) based on one of specific topics of cooperation (STC), Irradiation Technology for NTD-Si (STC No.II-4), on the implementing arrangement between NNC-RK and the JAEA for 'Nuclear Technology on Testing/Research Reactors' in cooperation in research and development in nuclear energy and technology. As for the irradiation test, Si rotating device was fabricated in JAEA, and the fabricated device was transported with irradiation specimens from JAEA to INP-NNC-RK. This report described the design, the fabrication, the performance test of the Si rotating device and transportation procedures. (author)

  19. Background and record of AMS measurements in JMSF

    Shima, Shigeki; Gasa, Sin'ichi

    2010-01-01

    Japan Marine Science Foundation (JMSF) has become a member of the users in the JAEA-Mutsu-AMS from 1999 and has determined concentrations of 14 C and 129 I in a wide variety of samples. They were relevant to radioecology, geology, and archaeology as well as oceanography. In this report, our activities over the past 10 years are described. (author)

  20. Proceedings of the 9th symposium on advanced photon research

    2010-03-01

    The 9th Symposium on Advanced Photon Research was held at Kansai Photon Science Institute, Japan Atomic Energy Agency (JAEA-KPSI) in Kizugawa, Kyoto on July 31- August 1, 2008. This report consists of invited and contributed papers presented at the oral and poster sessions in The Symposium. The 25 of the presented papers are indexed individually. (J.P.N.)

  1. Workshop on regional cooperation in remote monitoring for transparency and nonproliferation

    Olsen, John; Inoue, Naoko; Hori, Masato; Hashimoto, Yu; Mochiji, Toshiro

    2006-06-01

    The Workshop on Regional Cooperation in Remote Monitoring for Transparency and Nonproliferation on 8-9 February at O'arai, Japan, brought together remote monitoring experts to share technical experience and consider potential uses of remote monitoring for nuclear transparency and strengthened nonproliferation. Sponsored by the Nuclear Nonproliferation Science and Technology Center (NPSTC) of the Japan Atomic Energy Agency (JAEA), this event gathered thirty five attendees from the JAEA, the Republic of Korea's National Nuclear Management and Control Agency (NNCA), the International Atomic Energy Agency (IAEA), and U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA). U.S. technical experts represented Sandia National Laboratories (SNL) and Los Alamos National Laboratory (LANL). Workshop discussions and interactions met or surpassed all goals: On the technical front, the JAEA, NNCA, and SNL exchanged presentations on their respective uses and technical approaches to remote monitoring. These included systems for both international safeguards and transparency. The IAEA shared valuable guidance on future remote monitoring system requirements. Following the presentations SNL conducted training in remote monitoring for technical personnel. In parallel project planning discussions, the JAEA, NNCA, SNL and the U.S. DOE reaffirmed mutual interest in regional cooperation in remote monitoring that could eventuate in exchange of safeguards-related data. A productive off-the-record session by all parties considered the path forward and established intermediate steps and time scales. The 15 of the presented papers are indexed individually. (J.P.N.)

  2. Proceedings of the 11th symposium on advanced photon research

    2011-03-01

    The 11th Symposium on Advanced Photon Research was held at Kansai Photon Science Institute, Japan Atomic Energy Agency (JAEA-KPSI) in Kizugawa, Kyoto on June 24 - 25, 2010. This report consists of invited and contributed papers presented at the oral and poster sessions in the Symposium. The 29 of the presented papers are indexed individually. (J.P.N.)

  3. Annual report of Nuclear Technology and Education Center. April 1, 2008 - March 31, 2009

    2010-03-01

    This annual report summarizes the activities of Nuclear Technology and Education Center (NuTEC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2008. This year is the 50th anniversary of NuTEC since the starting of the first training course in January, 1958 at the Radioisotope-School in Tokyo. On this occasion, a commemorative symposium was held and attended by around 150 participants. NuTEC flexibly designed and conducted out new training courses upon requests while conducting the annually scheduled training programs. In spite of some cancellations in an economic downturn, the number of trainees who completed the domestic training courses was 404, and that of those who completed the staff technical training courses was 862. As a result, the total number of trainees during this period grew over the previous fiscal year. 'Nuclear Training for METI Inspectors' was newly offered and also 'Qualification Course for the 3rd class radiation protection supervisor' was held at Tsuruga Technical High School. JAEA continued its cooperative activities with universities; cooperation with graduate school of University of Tokyo, cooperative graduate school program with 14 graduate schools and one under-graduate school, and newly began to cooperate with Tsuyama National College of Technology. JAEA also continued cooperative activities with Nuclear HRD Program initiated by MEXT and METI implemented in 2007. The joint course has continued networking with five universities including newly two universities utilizing the Japan Nuclear Education Network (JNEN). International cooperation was also conducted as scheduled. The joint training course and the instructor training program were conducted bilaterally with Indonesia, Thailand and Vietnam. JAEA exchanged a memorandum with CEA/INSTN and initiated preparatory work for on internship student from INSTN. Moreover, JAEA newly joined European Nuclear Education Network (ENEN) and began to prepare for new international training

  4. Studies on Enhancing Nuclear Transparency in the Asia-Pacific Region

    Kawakubo, Y.; Tomikawa, H.

    2015-01-01

    Nuclear transparency is defined as ''a cooperative process of providing information to all interested parties so that they can independently assess the safety, security, and legitimate management of nuclear materials'' by Sandia National Laboratories (SNL). Since the Asia- Pacific region has a broad spectrum of nuclear development underway and planned in the future, nuclear transparency is recognized as essential to provide additional assurance and enhance confidence building in this area. It is expected that elevated nuclear transparency should also supplement International Atomic Energy Agency (IAEA) safeguards. With this recognition, JAEA has committed various studies and activities for enhancing regional nuclear transparency mainly with U.S. Department of Energy (DOE) and its national laboratories. The efforts include concept study, development of secure data transmission technologies at the Experimental Fast Reactor ''Joyo'' for the use of regional nuclear transparency, and support for Council for Security and Cooperation in Asia Pacific (CSCAP) to develop internet-based transparency tools. JAEA also organized several workshops to discuss with stakeholder organizations to build acceptance for transparency tools and activities. Based on the past studies, JAEA, jointly with SNL, Korea Institute of Nuclear Nonproliferation and Control (KINAC) and Korea Atomic Energy Research Institute (KAERI), initiated a new phase of study in 2011 to design and establish an Information Sharing Framework (ISF) which was defined as ''a communication platform on which nuclear nonproliferation experts can provide and/or receive relevant information in a practical and sustainable manner''. During the period of two-year study, partner organizations identified essential elements to establish ISF and developed the requirements. Currently, JAEA and KINAC are planning to implement demonstration of ISF under Asia Pacific

  5. Annual report of Nuclear Emergency Assistance and Training Center. April 1, 2013 - March 31, 2014

    Sato, Takeshi; Muto, Shigeo; Akiyama, Kiyomitsu; Aoki, Kazufumi; Okamoto, Akiko; Kawakami, Takeshi; Kume, Nobuhide; Nakanishi, Chika; Koie, Masahiro; Kawamata, Hiroyuki; Nemotouchi, Toshimasa; Saito, Toru; Kato, Tadashi; Sumiya, Akio; Yamamoto, Kazuya; Sato, Sohei; Sumiya, Akihiro; Okuno, Hiroshi; Yoshida, Hiroshi; Kikuchi, Masayuki; Matsusaka, Masaru

    2015-02-01

    The Japan Atomic Energy Agency, which will be abbreviated as JAEA hereafter, was assigned as a designated public institution under the Disaster Countermeasures Basic Act and under the Armed Attack Situations Response Act. Based on these Acts, the JAEA has the responsibility of providing technical support to the national government and/or local governments in case of disaster responses or response in the event of a military attack, etc. In order to fulfill the tasks, the JAEA has established the Emergency Action Plan and the Civil Protection Action Plan. In case of a nuclear emergency, the Nuclear Emergency Assistance and Training Center (NEAT) dispatches specialists of JAEA, supplies the national government and local governments with emergency equipment and materials, and gives technical advice and information. In normal time, NEAT provides various exercises and training courses concerning nuclear disaster prevention to those personnel taking an active part in emergency response institutions of the national and local governments, police, fire fighters, self-defense forces, etc. in addition to the JAEA itself. The NEAT also researches nuclear disaster preparedness and response, and cooperates with international organizations. In the FY2013, the NEAT accomplished the following tasks: (1) Technical support activities as a designated public institution in cooperation with the national and local governments, etc. (2) Human resource development, exercise and training of nuclear emergency response personnel for the national and local governments, etc. (3) Researches on nuclear disaster preparedness and response, and sending useful information. (4) International contributions to Asian countries on nuclear disaster preparedness and response in collaboration with the international organizations. (author)

  6. Cryogenic structures of superconducting coils for fusion experimental reactor 'ITER'

    Nakajima, Hideo; Iguchi, Masahide; Hamada, Kazuya; Okuno, Kiyoshi; Takahashi, Yoshikazu; Shimamoto, Susumu

    2013-01-01

    This paper describes both structural materials and structural design of the Toroidal Field (TF) coil and Central Solenoid (CS) for the International Thermonuclear Experimental Reactor (ITER). All the structural materials used in the superconducting coil system of the ITER are austenitic stainless steels. Although 316LN is used in the most parts of the superconducting coil system, the cryogenic stainless steels, JJ1 and JK2LB, which were newly developed by the Japan Atomic Energy Agency (JAEA) and Japanese steel companies, are used in the highest stress area of the TF coil case and the whole CS conductor jackets, respectively. These two materials became commercially available based on demonstration of productivity and weldability of materials, and evaluations of 4 K mechanical properties of trial products including welded parts. Structural materials are classified into five grades depending on stress distribution in the TF coil case. JAEA made an industrial specification for mass production based on the ITER requirements. In order to simplify quality control in mass production, JAEA has used materials specified in the material section of 'Codes for Fusion Facilities - Rules on Superconducting Magnet Structure (2008)' issued by the Japan Society of Mechanical Engineers (JSME) in October 2008, which was established using an extrapolation method of 4 K material strengths from room temperature strength and chemical compositions developed by JAEA. It enables steel suppliers to easily control the quality of products at room temperature. JAEA has already started actual production with several manufacturing companies. The first JJ1 product to be used in the TF coil case and the first JK2LB jackets for CS were completed in October and September 2013, respectively. (author)

  7. Annual report of Nuclear Emergency Assistance and Training Center. April 1, 2012 - March 31, 2013

    Sato, Takeshi; Muto, Shigeo; Okuno, Hiroshi; Katagiri, Hiromi; Akiyama, Kiyomitsu; Okamoto, Akiko; Koie, Masahiro; Ikeda, Takeshi; Nemotouchi, Toshimasa; Saito, Toru; Sumiya, Akio; Kawamata, Hiroyuki; Nakanishi, Chika; Hirayama, Yusuke; Yamamoto, Kazuya; Sato, Sohei; Sumiya, Akihiro; Kawakami, Takeshi; Kikuchi, Masayuki; Aoki, Kazufumi; Matsusaka, Masaru; Nagakura, Tomohiro; Nakamura, Koichi

    2014-02-01

    The Japan Atomic Energy Agency, which will be abbreviated as JAEA hereafter, was assigned as a designated public institution under the Disaster Countermeasures Basic Act and under the Armed Attack Situations Response Act. Based on these Acts, the JAEA has the responsibility of providing technical support to the National government and/or local governments in case of disaster responses or response in the event of a military attack, etc. In order to fulfill the tasks, the JAEA has established the Emergency Action Plan and the Civil Protection Action Plan. In case of a nuclear emergency, the Nuclear Emergency Assistance and Training Center (NEAT) of JAEA provides technical support activities to an Off-Site Center in any prefecture. Specifically, NEAT dispatches specialists, supplies the National Government and local governments with emergency equipment and materials, and gives technical advice and information. In normal time, NEAT provides various exercises and training courses concerning nuclear disaster prevention to those personnel taking an active part in emergency response institutions of the national and local governments, police, fire fighters, self-defense forces, etc. in addition to the JAEA itself. The NEAT also researches nuclear disaster preparedness and response, and cooperates with international organizations. In the FY2012, the NEAT accomplished the following tasks: (1) Technical support activities as a designated public institution in cooperation with the national and local governments, etc. (2) Human resource development, exercise and training of nuclear emergency response personnel for the national and local governments, etc. (3) Researches on nuclear disaster preparedness and response, and sending useful information. (4) International contributions to Asian countries on nuclear disaster preparedness and response in collaboration with the international organizations. The responses of the JAEA to the accident of TEPCO's Fukushima Daiichi Nuclear Power

  8. Annual report of Nuclear Technology and Education Center. April 1, 2009 - March 31, 2010

    2011-03-01

    This annual report summarizes the activities of Nuclear Technology and Education Center (NuTEC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2009. In this fiscal year, NuTEC flexibly designed and conducted new training courses upon requests while conducting the annually scheduled training programs, and actively enhanced the collaboration with academia and cooperation with international organizations. Probably due to the economic depression, the number of trainees who completed the national training courses in 2009 was 322, which is 20 percent less than the previous year. The number of those who completed the staff technical training courses was slightly increased to 787 in 2009. As a result, the total number of trainees during this period is about 6 percent less than the previous year. In order to correspond with the needs from outside of JAEA, five temporary courses were held upon the request from Nuclear and Industrial Safety Agency, Ministry of Economy, Trade and Industry. 'Risk communication course' was newly offered upon the request from Nuclear Safety Commission. Furthermore, we addressed the longstanding issue to take countermeasure against the aging accommodation facility. The web site was also improved so that users can directly send the application for enrollment in the training courses through internet. These new services actually started in fiscal year 2010. JAEA continued its cooperative activities with universities; cooperation with graduate school of University of Tokyo, and the cooperative graduate school program was enlarged to cooperate with totally 17 graduate schools (18 universities), one faculty of undergraduate school, and one technical college, including the newly joined 3 graduate schools (4 universities) in 2009. JAEA also continued cooperative activities with Nuclear HRD Program initiated by MEXT and METI in 2007. The joint course has continued networking with six universities including newly joined Osaka University through

  9. Welding of metallic fuel elements for the irradiation test in JOYO. Preliminary tests and welding execution tests (Joint research)

    Kikuchi, Hironobu; Nakamura, Kinya; Iwai, Takashi; Arai, Yasuo

    2009-10-01

    Irradiation tests of metallic fuels elements in fast test reactor JOYO are planned under the joint research of Japan Atomic Energy Agency (JAEA) and Central Research Institute of Electric Power Industry (CRIEPI). Six U-Pu-Zr fuel elements clad with ferritic martensitic steel are fabricated in Plutonium Fuel Research Facility (PFRF) of JAEA-Oarai for the first time in Japan. In PFRF, the procedures of fabrication of the fuel elements were determined and the test runs of the equipments were carried out before the welding execution tests for the fuel elements. Test samples for confirming the welding condition between the cladding tube and top and bottom endplugs were prepared, and various test runs were carried out before the welding execution tests. As a result, the welding conditions were finalized by passing the welding execution tests. (author)

  10. Approach for domestic preparation of standard material (LSD spike) for isotope dilution mass spectrometry

    Ishikawa, Fumitaka; Sumi, Mika; Chiba, Masahiko; Suzuki, Toru; Abe, Tomoyuki; Kuno, Yusuke

    2008-01-01

    The accountancy analysis of the nuclear fuel material at Plutonium Fuel Development Center of JAEA is performed by isotope dilution mass spectrometry (IDMS; Isotope Dilution Mass Spectrometry). IDMS requires the standard material called LSD spike (Large Size Dried spike) which is indispensable for the accountancy in the facilities where the nuclear fuel materials are handled. Although the LSD spike and Pu source material have been supplied from foreign countries, the transportation for such materials has been getting more difficult recently. This difficulty may affect the operation of nuclear facilities in the future. Therefore, research and development of the domestic LSD spike and base material has been performed at JAEA. Certification for such standard nuclear materials including spikes produced in Japan is being studied. This report presents the current status and the future plan for the technological development. (author)

  11. Status of {sup 99}Mo-{sup 99m}Tc production development by (n, {gamma}) reaction

    Tsuchiya, Kunihiko; Kaminaga, Masanori; Ishihara, Masahiro; Kawamura, Hiroshi [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan); Mutalib, Abdul [National Nuclear Energy Agency of Indonesia (BATAN), Tangerang (Indonesia); Chakrov, Petr [Institute of Nuclear Physics, National Nuclear Center of Republic of Kazakhstan (INP-NNC-RK), Almaty (Kazakhstan)

    2012-03-15

    Technetium-99m ({sup 99m}Tc) is one of the most commonly used radioisotopes in the field of nuclear medicine. As one of effective uses of the JMTR, JAEA has a plan to produce {sup 99}Mo by (n, {gamma}) method, a parent nuclide of {sup 99m}Tc. JAEA has performed R and D on production method of {sup 99}Mo-{sup 99m}Tc in JMTR cooperating with foreign organizations and relevant Japanese enterprises under the cooperation programs. In this paper, present status of R and D for production of {sup 99}Mo-{sup 99m}Tc in JMTR under international cooperation is introduced and constructions of the irradiation and PIE facilities at the JMTR site are also described. (author)

  12. Real-time personal exposure and health condition monitoring system

    Saitou, Isamu; Kanda, Hiroaki; Asai, Akio; Takeishi, Naoki; Ota, Yoshito [Hitachi Aloka Medical, Ltd., Measuring Systems Engineering Dept., Tokyo (Japan); Hanawa, Nobuhiro; Ueda, Hisao; Kusunoki, Tsuyoshi; Ishitsuka, Etsuo; Kawamura, Hiroshi [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)

    2012-03-15

    JAEA (Japan Atomic Energy Agency) and HAM (Hitachi Aloka Medical, Ltd) have proposed novel monitoring system for workers of nuclear facility. In these facilities, exposure management for workers is mainly used access control and personal exposure recordings. This system is currently only for reports management but is not confirmative for surveillance when work in progress. Therefore, JAEA and HAM integrate access control and personal exposure recordings and two real-time monitoring systems which are position sensing and vital sign monitor. Furthermore change personal exposure management to real-time management, this system integration prevents workers from risk of accidents, and makes possible take appropriate action quickly. This novel system is going to start for tentative operation, using position sensing and real-time personal dosimeter with database in Apr. 2012. (author)

  13. Cooperation on impingement wastage experiment of Mod. 9Cr-1Mo steel using SWAT-1R sodium-water reaction test facility

    Beauchamp, F.; Allou, A.; Nishimura, M.; Umeda, R.

    2013-01-01

    Conclusion: • 6 experiments were carried out in the SWAT-1R facility of JAEA Oarai R&D Center to study the wastage resistance of the Mod. 9Cr-1Mo steel (T91) straight tubes. • These experiments were performed under the cooperation between CEA and JAEA. • The experiments were conducted successfully: - all the tubes were punctured by the reaction jet, - wastage and steam/water leak rates were obtained, - experimental results brought some new determining sets of wastage data on T91. • This fruitful cooperation has contributed to: - expanding the wastage database on T91, - upgrading wastage rates prediction from modelling, - the safety demonstration of future steam generators units

  14. Report on survey on international Hub

    Ebisawa, Hirobumi; Hoshino, Junko; Hashimoto, Kazuichiro; Okada, Sohei

    2011-03-01

    Japan Atomic Energy Agency (JAEA) is promoting initiative to form an international Center of Excellence in line with its aim to accept more researchers/engineers from all over the world. Establishment of 'the Committee for JAEA Internationalization Initiative' was planned in 2010 so as to intensify this initiative, and in February, 2010, we visited research institutions in Europe, which include European Organization for Nuclear Research (CERN), the construction site of ITER in Cadarache, and Rutherford Appleton Laboratory (RAL), with the intention to survey and learn their advanced activities and systems in regard to the International Hub, so that the committee will be able to make fruitful discussion. This report describes strategy taken in each institution for an International Hub, and the state of each institution regarding acceptance and management of overseas researchers and engineers, research environment, living environment/health and welfare, and PR activities/coexistence with the local community. (author)

  15. Safety requirements expected to the prototype fast breeder reactor 'Monju'

    2014-11-01

    In July 2013, Nuclear Regulation Authority (NRA) has enforced new regulatory requirements in consideration of severe accidents for the commercial light water reactors (LWR) and also prototype power generation reactors such as the sodium-cooled fast reactors (SFR) of 'Monju' based on TEPCO Fukushima Daiichi nuclear power plant accident (hereinafter referred to as '1F accident') occurred in March 2011. Although the regulatory requirements for SFR will be revised by NRA with consideration for public comments, Japan Atomic Energy Agency (JAEA) set up 'Advisory Committee on Monju Safety Requirements' consisting of fast breeder reactor (FBR) and safety assessment experts in order to establish original safety requirements expected to the prototype FBR 'Monju' considering severe accidents with knowledge from JAEA as well as scientific and technical insights from the experts. This report summarizes the safety requirements expected to Monju discussed by the committee. (author)

  16. Annual report of Nuclear Technology and Education Center (April 1, 2005 - March 31, 2006)

    2006-12-01

    This report summarizes the activities of the Nuclear Technology and Education Center (NuTEC) of the Japan Atomic Energy Agency (JAEA) in the fiscal year 2005. On unification of JAERI and JNC on October, 2005, the former NuTEC of JAERI and the Human Resources Development Section of JNC were reorganized as the new NuTEC. Concomitantly, the training courses on nuclear emergency preparedness, held at the former NuTEC, was transferred to NEAT, JAEA, and the management related to university cooperation was assigned as one of the tasks of the new NuTEC. In total, the number of trainees for the general domestic training courses was 652, while that for the staff technical training courses was 616. The international training courses have also been carried out as planned. In addition, supportive activities for the Nuclear Professional School of Tokyo University, commenced in April, 2005, have been made mainly concerning the experimental exercises for the students. (author)

  17. Fundamental philosophy on the safety design of the HTTR-IS hydrogen production system

    Ohashi, Kazutaka; Nishihara, Tetsuo; Kunitomi, Kazuhiko

    2007-01-01

    Japan Atomic Energy Agency (JAEA) has been conducting an R and D work on the VHTR reactor system and IS hydrogen production system to realize hydrogen production using nuclear heat. As a part of this activity, JAEA is planning to connect an IS test system to the High Temperature Engineering Test Reactor (HTTR) to demonstrate its technical feasibility. This paper proposes a fundamental philosophy on the safety design of the HTTR-IS hydrogen production system including the methodology to select postulated abnormal events and its event sequences and to define safety functions of the IS system to ensure the reactor safety. Also the measure to clarify the IS system as non-reactor system is proposed. (author)

  18. Research and development for treatment and disposal technologies of TRU waste

    Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Nakanishi, Hiroshi; Sasaki, Ryoichi; Ichige, Satoru; Takahashi, Kuniaki; Meguro, Yoshihiro; Yamaguchi, Hiromi; Aoyama, Yoshio

    2007-09-01

    After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology. (author)

  19. Chemical Dissolution of Simulant FCA Cladding and Plates

    Daniel, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pierce, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); O' Rourke, P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-11-08

    The Savannah River Site (SRS) has received some fast critical assembly (FCA) fuel from the Japan Atomic Energy Agency (JAEA) for disposition. Among the JAEA FCA fuel are approximately 7090 rectangular Stainless Steel clad fuel elements. Each element has an internal Pu-10.6Al alloy metal wafer. The thickness of each element is either 1/16 inch or 1/32 inch. The dimensions of each element ranges from 2 inches x 1 inch to 2 inches x 4 inches. This report discusses the potential chemical dissolution of the FCA clad material or stainless steel. This technology uses nitric acid-potassium fluoride (HNO3-KF) flowsheets of H-Canyon to dissolve the FCA elements from a rack of materials. Historically, dissolution flowsheets have aimed to maximize Pu dissolution rates while minimizing stainless steel dissolution (corrosion) rates. Because the FCA cladding is made of stainless steel, this work sought to accelerate stainless steel dissolution.

  20. RM Based Bilateral Regional Cooperation and its Perspective in Korea

    Park, Seung Sik

    2010-01-01

    Remote monitoring (RM) is one alternative step to fulfill safeguards requirements in the member states. Korea installed a surveillance and unattended monitoring system in the ACPF (Advanced Spent Fuel Conditioning Process Facility) at the Korea Atomic Energy Research Institute (KAERI) in 2005. Data began to be shared through a virtual private network (VPN) started in 2006 with the Korea Institute of Nuclear Non-proliferation and Control (KINAC), KAERI, and the Sandia National Laboratories (SNL), as well. From 2009 the data are also being sent to the IAEA. Recently discussions have taken place to form a trilateral KINAC-SNL-JAEA (Japan Atomic Energy Agency) network using RM to strengthen the regional cooperative nonproliferation. The cooperation is supporting the basic ground of regional approaches for the peaceful use of nuclear energy. This paper addresses the main features of recent development to form a trilateral KINAC- SNL-JAEA network and a future prospective in nuclear nonproliferation and transparency via remote monitoring surveillance

  1. Report on survey on international hub

    Ebisawa, Hirobumi; Hoshino, Junko; Hashimoto, Kazuichiro; Okada, Sohei

    2011-06-01

    Japan Atomic Energy Agency (JAEA) is promoting initiative to form an international hub in line with its aim to accept more researchers/engineers from all over the world. Establishment of 'the Committee for JAEA Internationalization Initiative' was planned in 2010 so as to intensify this initiative, and in February, 2010, we visited research institutions in Europe, which include European Organization for Nuclear Research (CERN), the construction site of ITER in Cadarache, and Rutherford Appleton Laboratory (RAL), with the intention to survey and learn their advanced activities and systems in regard to the International Hub, so that the committee will be able to make fruitful discussion. This report describes strategy taken in each institution for an International Hub, and the state of each institution regarding acceptance and management of overseas researchers and engineers, research environment, living environment/health and welfare, and PR activities/coexistence with the local community. (author)

  2. ATF Neutron Irradiation Program Technical Plan

    Geringer, J. W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division; Katoh, Yutai [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division

    2016-03-01

    The Japan Atomic Energy Agency (JAEA) under the Civil Nuclear Energy Working Group (CNWG) is engaged in a cooperative research effort with the U.S. Department of Energy (DOE) to explore issues related to nuclear energy, including research on accident-tolerant fuels and materials for use in light water reactors. This work develops a draft technical plan for a neutron irradiation program on the candidate accident-tolerant fuel cladding materials and elements using the High Flux Isotope Reactor (HFIR). The research program requires the design of a detailed experiment, development of test vehicles, irradiation of test specimens, possible post-irradiation examination and characterization of irradiated materials and the shipment of irradiated materials to JAEA in Japan. This report discusses the technical plan of the experimental study.

  3. Assessment of damage domains of the High-Temperature Engineering Test Reactor (HTTR)

    Flores, Alain; Izquierdo, José María; Tuček, Kamil; Gallego, Eduardo

    2014-01-01

    Highlights: • We developed an adequate model for the identification of damage domains of the HTTR. • We analysed an anticipated operational transient, using the HTTR5+/GASTEMP code. • We simulated several transients of the same sequence. • We identified the corresponding damage domains using two methods. • We calculated exceedance frequency using the two methods. - Abstract: This paper presents an assessment analysis of damage domains of the 30 MW th prototype High-Temperature Engineering Test Reactor (HTTR) operated by the Japan Atomic Energy Agency (JAEA). For this purpose, an in-house deterministic risk assessment computational tool was developed based on the Theory of Stimulated Dynamics (TSD). To illustrate the methodology and applicability of the developed modelling approach, assessment results of a control rod (CR) withdrawal accident during subcritical conditions are presented and compared with those obtained by the JAEA

  4. Horonobe Underground Research Laboratory project. Investigation report for the 2006 fiscal year

    Matsui, Hiroya; Nakayama, Masashi; Sanada, Hiroyuki

    2008-05-01

    The Horonobe Underground Research Laboratory is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction Phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the results of the investigations for the 2006 fiscal year (2006/2007), the second year of the Phase 2 investigations. The investigations, which are composed of 'Geoscientific research' and 'R and D on the geological disposal of high-level radioactive waste (HLW)', were carried out according to 'Horonobe Underground Research Laboratory Project Investigation Program for the 2006 Fiscal Year'. The results of these investigations, along with the results which were obtained in other departments of Japan Atomic Energy Agency (JAEA), are properly offered to the implementations and the safety regulations. JAEA proceeded with the project in, collaboration with experts from domestic and overseas research organisation. (author)

  5. Horonobe Underground Research Laboratory project investigation report for the 2008 fiscal year

    Nakayama, Masashi; Sano, Michiaki; Sanada, Hiroyuki; Sugita, Yutaka

    2009-11-01

    The Horonobe Underground Research Laboratory Project is planned to extend over a period 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations' 'Phase 2: Construction Phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the results of the investigations for the 2008 fiscal year (2008/2009), the 4th year of the Phase 2 investigations. The investigations, which are composed of 'Geoscientific research' and 'R and D on geological disposal technology', were carried out according to 'Horonobe Underground Research Laboratory Project Investigation Program for the 2008 Fiscal year'. The results of these investigations, along with the results which were obtained in other departments of Japan Atomic Energy Agency (JAEA), are properly offered to the implementations and the safety regulations. For the sake of this, JAEA has proceeded with the project in collaboration with experts from domestic and overseas research organisations. (author)

  6. Development of inverse-planning system for neutron capture therapy

    Kumada, Hiroaki; Yamamoto, Kazuyoshi; Maruo, Takeshi

    2006-01-01

    To lead proper irradiation condition effectively, Japan Atomic Energy Agency (JAEA) is developing an inverse-planning system for neutron capture therapy (NCT-IPS) based on the JAEA computational dosimetry system (JCDS) for BNCT. The leading methodology of an optimum condition in the NCT-IPS has been applied spatial channel theory with adjoint flux solution of Botzman transport. By analyzing the results obtained from the adjoint flux calculations according to the theory, optimum incident point of the beam against the patient can be found, and neutron spectrum of the beam which can generate ideal distribution of neutron flux around tumor region can be determined. The conceptual design of the NCT-IPS was investigated, and prototype of NCT-IPS with JCDS is being developed. (author)

  7. Work and safety managements for on-site installation, commissioning, tests by EU of quench protection circuits for JT-60SA

    Yamauchi, Kunihito; Okano, Jun; Shimada, Katsuhiro; Ohmori, Yoshikazu; Terakado, Tsunehisa; Matsukawa, Makoto; Koide, Yoshihiko; Kobayashi, Kazuhiro; Ikeda, Yoshitaka; Fukumoto, Masahiro; Kushita, Kouhei N.

    2016-03-01

    The superconducting Satellite Tokamak machine “JT-60SA” under construction in Naka Fusion Institute is an international collaborative project between Japan Atomic Energy Agency (JAEA) as the Implementing Agency (IA) of Japan (JA) and Fusion for Energy (F4E) as the IA of Europe (EU). The contributions for this project are based on the supply of components, and thus European manufacturer shall conduct the installation, commissioning and tests on Naka site under the general supervision by F4E via the designated institute in each EU nation. This means that JAEA had an issue to manage the works by European workers and their safety although there is no direct contract. This report describes the approaches for the work and safety managements, which were agreed with EU after the negotiation, and the completed on-site works for Quench Protection Circuits (QPC) as the first experience for EU in JT-60SA project. (author)

  8. Radiation protection at nuclear fuel cycle facilities

    Endo, K.; Momose, T.; Furuta, S.

    2011-01-01

    Radiation protection methodologies concerning individual monitoring, workplace monitoring and environmental monitoring in nuclear fuel facilities have been developed and applied to facilities in the Nuclear Fuel Cycle Engineering Laboratories (NCL) of Japan Atomic Energy Agency (JAEA) for over 40 y. External exposure to photon, beta ray and neutron and internal exposure to alpha emitter are important issues for radiation protection at these facilities. Monitoring of airborne and surface contamination by alpha and beta/photon emitters at workplace is also essential to avoid internal exposure. A critical accident alarm system developed by JAEA has been proved through application at the facilities for a long time. A centralised area monitoring system is effective for emergency situations. Air and liquid effluents from facilities are monitored by continuous monitors or sampling methods to comply with regulations. Effluent monitoring has been carried out for 40 y to assess the radiological impacts on the public and the environment due to plant operation. (authors)

  9. Evaluation of hydrogen production system coupling with HTTR using dynamic analysis code

    Sato, Hiroyuki; Ohashi, Hirofumi; Inaba, Yoshitomo; Nishihara, Tetsuo; Hayashi, Koji; Inagaki, Yoshiyuki

    2006-01-01

    The Japan Atomic Energy Agency (JAEA) was entrusted 'Development of Nuclear Heat Utilization Technology' by Ministry of Education, Culture, Sports, Science and Technology. In this development, the JAEA investigated the system integration technology to couple the hydrogen production system by steam reforming with the High Temperature Engineering Test Reactor (HTTR). Prior to the construction of the hydrogen production system coupling with the HTTR, a dynamic analysis code had to be developed to evaluate the system transient behaviour of the hydrogen production system because there are no examples of chemical facilities coupled with nuclear reactor in the world. This report describes the evaluation of the hydrogen production system coupling with HTTR using analysis code, N-HYPAC, which can estimate transient behaviour of the hydrogen production system by steam reforming. The results of this investigation provide that the influence of the thermal disturbance caused by the hydrogen production system on the HTTR can be estimated well. (author)

  10. Horonobe Underground Research Laboratory project. Investigation report for the 2010 fiscal year

    Nakayama, Masashi; Sawada, Sumiyuki; Sugita, Yutaka

    2011-09-01

    The Horonobe Underground Research Laboratory Project is planned to extend over a period 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction Phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the results of the investigations for the 2010 fiscal year (2010/2011). The investigations, which are composed of 'Geoscientific research' and 'R and D on geological disposal technology', were carried out according to 'Horonobe Underground Research Laboratory Project Investigation Program for the 2010 Fiscal year'. The results of these investigations, along with the results which were obtained in other departments of Japan Atomic Energy Agency (JAEA), are properly offered to the implementations and the safety regulations. For the sake of this, JAEA has proceeded with the project in collaboration with experts from domestic and overseas research organisations. (author)

  11. Selection of design basis event for modular high temperature gas-cooled reactor

    Sato, Hiroyuki; Nakagawa, Shigeaki; Ohashi, Hirofumi

    2016-06-01

    Japan Atomic Energy Agency (JAEA) has been investigating safety requirements and basic approach of safety guidelines for modular High Temperature Gas-cooled Reactor (HTGR) aiming to increase internarial contribution for nuclear safety by developing an international HTGR safety standard under International Atomic Energy Agency. In this study, we investigate a deterministic approach to select design basis events utilizing information obtained from probabilistic approach. In addition, selections of design basis events are conducted for commercial HTGR designed by JAEA. As a result, an approach for selecting design basis event considering multiple failures of safety systems is established which has not been considered as design basis in the safety guideline for existing nuclear facility. Furthermore, selection of design basis events for commercial HTGR has completed. This report provides an approach and procedure for selecting design basis events of modular HTGR as well as selected events for the commercial HTGR, GTHTR300. (author)

  12. Environmental performance data in 'Japan Atomic Energy Agency Report 2016'

    Suzuki, Yurina; Kanai, Katsuta; Sato, Sadayuki; Tatebe, Kazuaki

    2017-03-01

    In September, 2016 Japan Atomic Energy Agency (JAEA) published results of environmental activity as a part of 'Japan Atomic Energy Agency Report 2016' concerning the activities of FY 2015 under 'Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc., by Facilitating Access to Environmental Information, and Other Measures'. This report has been edited to show detailed environmental performance data in FY 2015 as the base of the 'Japan Atomic Energy Agency Report 2016'. This report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA. (author)

  13. Development of the clearance level verification evaluation system. 2. Construction of the clearance data management system

    Kubota, Shintaro; Usui, Hideo; Kawagoshi, Hiroshi

    2014-06-01

    Clearance is defined as the removal of radioactive materials or radioactive objects within authorized practices from any further regulatory control by the regulatory body. In Japan, clearance level and a procedure for its verification has been introduced under the Laws and Regulations, and solid clearance wastes inspected by the national authority can be handled and recycled as normal wastes. The most prevalent type of wastes have generated from the dismantling of nuclear facilities, so the Japan Atomic Energy Agency (JAEA) has been developing the Clearance Level Verification Evaluation System (CLEVES) as a convenient tool. The Clearance Data Management System (CDMS), which is a part of CLEVES, has been developed to support measurement, evaluation, making and recording documents with clearance level verification. In addition, validation of the evaluation result of the CDMS was carried out by inputting the data of actual clearance activities in the JAEA. Clearance level verification is easily applied by using the CDMS for the clearance activities. (author)

  14. Establishment of 'Japan Atomic Energy Agency'. Its role and expectation

    Nakahara, Toru; Itakura, Shuichiro; Shiozawa, Shusaku; Hino, Ryutaro; Fujii, Yasuhiko; Sakurada, Michio; Kimura, Itsuro; Kikuyama, Kaoru

    2005-01-01

    In October 2005, the Japan Atomic Energy Agency (JAEA) was established as an independent administrative institution with the integration of the Japan Atomic Energy Research Institute (JAERI) and the Japan Nuclear Cycle Development Institute (JNC). JAEA is the only institute in Japan dedicated to comprehensive research and development in the field of nuclear energy. This paper put together a special article on its role and expectation. Firstly the essentials of comprehensive nuclear research and its future perspective were discussed mainly based on 'Framework for Nuclear Energy Policy' of the Atomic Energy Commission of Japan. Eight articles were followed on specific items such as quantum beams utilization, hydrogen production with nuclear heat, neutron science and ITER project, and put stress on joint works and smooth transfer of related technology to the private sector. (T. Tanaka)

  15. Development programs of cutting-edge technologies for measurement and detection of nuclear material for safeguards and security

    Seya, Michio; Wakabayashi, Shuji; Naoi, Yosuke; Ohkubo, Michiaki; Senzaki, Masao

    2011-01-01

    The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security ('ISCN', hereafter) of Japan Atomic Energy Agency (JAEA) has development programs of cutting-edge technologies for measurement and detection of nuclear materials for nuclear safeguards and security, under the sponsorship of Japanese government (MEXT: Ministry of Education, Culture, Sports, Science and Technology). ISCN started development programs of the following technologies this year. (1) NRF (Nuclear Resonance Fluorescence) NDA technology using laser Compton scattering (LCS) gamma-rays, (2) Alternative to 3 He neutron detection technology using inorganic solid scintillator. ISCN is also going to conduct a demonstration test of a spent fuel Pu-NDA system that is to be developed by LANL (Los Alamos National Laboratory) using very sophisticated neutron measurement technologies, under JAEA/USDOE cooperation agreement. This presentation shows the above programs of ISCN. (author)

  16. Input/output manual of light water reactor fuel performance code FEMAXI-7 and its related codes

    Suzuki, Motoe; Udagawa, Yutaka; Nagase, Fumihisa [Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan); Saitou, Hiroaki [ITOCHU Techno-Solutions Corp., Tokyo (Japan)

    2012-07-15

    A light water reactor fuel analysis code FEMAXI-7 has been developed for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which has been fully disclosed in the code model description published recently as JAEA-Data/Code 2010-035. The present manual, which is the counterpart of this description, gives detailed explanations of operation method of FEMAXI-7 code and its related codes, methods of Input/Output, methods of source code modification, features of subroutine modules, and internal variables in a specific manner in order to facilitate users to perform a fuel analysis with FEMAXI-7. This report includes some descriptions which are modified from the original contents of JAEA-Data/Code 2010-035. A CD-ROM is attached as an appendix. (author)

  17. Input/output manual of light water reactor fuel performance code FEMAXI-7 and its related codes

    Suzuki, Motoe; Udagawa, Yutaka; Nagase, Fumihisa; Saitou, Hiroaki

    2012-07-01

    A light water reactor fuel analysis code FEMAXI-7 has been developed for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which has been fully disclosed in the code model description published recently as JAEA-Data/Code 2010-035. The present manual, which is the counterpart of this description, gives detailed explanations of operation method of FEMAXI-7 code and its related codes, methods of Input/Output, methods of source code modification, features of subroutine modules, and internal variables in a specific manner in order to facilitate users to perform a fuel analysis with FEMAXI-7. This report includes some descriptions which are modified from the original contents of JAEA-Data/Code 2010-035. A CD-ROM is attached as an appendix. (author)

  18. Proceedings of the 2005 symposium on nuclear data

    Tahara, Yoshihisa; Fukahori, Tokio

    2006-11-01

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

  19. Survey on usage of electronic journals in Japan Atomic Energy Agency

    Ishikawa, Masashi; Fukazawa, Takeyasu

    2008-05-01

    Survey on usage of electronic journals was performed quantitatively by analyzing downloads accesses data to the 1,783 journals titles published by Elsevier in Japan Atomic Energy Agency (JAEA), 2006. Although JAEA researchers are interested in 1,028 journal titles among physics, chemistry, engineering, medicine, social sciences etc., it is found that 80% of total downloads was occupied by only 102 journal titles. To satisfy researcher's needs for electronic journals effectively, identification the core journals by librarians based on user's needs is rational way in cost. By shifting from print to electronic journals, the number of users increased by 30% and the number of papers read by researchers increased by 7 times. It is also found that many of researchers do not use SD (Science Directs) useful functions such as searching, linking to other bibliographic records, and alerting new information of electronic journals. To inform the useful functions to researchers by librarians is necessary. (author)

  20. Assistance to the Fukushima Daiichi NPP accident

    Sakuma, Minoru

    2012-01-01

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

  1. RM Based Bilateral Regional Cooperation and its Perspective in Korea

    Park, Seung Sik [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2010-10-15

    Remote monitoring (RM) is one alternative step to fulfill safeguards requirements in the member states. Korea installed a surveillance and unattended monitoring system in the ACPF (Advanced Spent Fuel Conditioning Process Facility) at the Korea Atomic Energy Research Institute (KAERI) in 2005. Data began to be shared through a virtual private network (VPN) started in 2006 with the Korea Institute of Nuclear Non-proliferation and Control (KINAC), KAERI, and the Sandia National Laboratories (SNL), as well. From 2009 the data are also being sent to the IAEA. Recently discussions have taken place to form a trilateral KINAC-SNL-JAEA (Japan Atomic Energy Agency) network using RM to strengthen the regional cooperative nonproliferation. The cooperation is supporting the basic ground of regional approaches for the peaceful use of nuclear energy. This paper addresses the main features of recent development to form a trilateral KINAC- SNL-JAEA network and a future prospective in nuclear nonproliferation and transparency via remote monitoring surveillance

  2. Real time simulator for material testing reactor

    Takemoto, Noriyuki; Imaizumi, Tomomi; Izumo, Hironobu; Hori, Naohiko; Suzuki, Masahide [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan); Ishitsuka, Tatsuo; Tamura, Kazuo [ITOCHU Techno-Solutions Corp., Tokyo (Japan)

    2012-03-15

    Japan Atomic Energy Agency (JAEA) is now developing a real time simulator for a material testing reactor based on Japan Materials Testing Reactor (JMTR). The simulator treats reactor core system, primary and secondary cooling system, electricity system and irradiation facility systems. Possible simulations are normal reactor operation, unusual transient operation and accidental operation. The developed simulator also contains tool to revise/add facility in it for the future development. (author)

  3. ITER technical term bilingual glossary year 2008 first half edition

    Sato, Koichi; Sengoku, Akio; Kitazawa, Sin-iti; Neyatani, Yuzuru; Koizumi, Koichi; Seki, Fumiko; Hasegawa, Shiori

    2008-09-01

    On October 24th, 2007, the Agreement on the Establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project (the 'ITER Agreement') came into force, and Japan Atomic Energy Agency (JAEA) was appointed to a Domestic Agency (DA). The DA will contribute to the ITER construction in cooperation with ITER Organization (IO) where many ITER-specific technical terms and abbreviations were used. This book is a collection of those terms and abbreviations translated to Japanese. (author)

  4. Calculation using MVP and MVP-BURN in JRR-3

    Komeda, Masao; Kato, Tomoaki; Murayama, Yoji; Yamashita, Kiyonobu

    2007-01-01

    MVP is the particle-transport Monte Carlo code that has been developed in JAEA. MVP-BURN is an added function to do burn-up calculation. It is easy to built complex structure like core for MVP. And it is easy to do calculations of keff, any reaction rate, flux, burn-up and so on. In this report, it is introduced MVP and MVP-BURN. And some sample calculations of JRR-3 are shown. (author)

  5. Development of Neutron Interferometer with Wide-Gapped ''BSE''s for Precision Measurements

    Seki, Y.; Kitaguchi, M.; Hino, M.; Funahashi, H.; Taketani, K.; Otake, Y.; Shimizu, H. M.

    2007-01-01

    We are developing large-dimensional cold-neutron interferometers with multilayer mirrors in order to investigate small interactions. In particular Jamin type interferometers composed of wide-gapped 'BSE's, which divide the beam completely, can realize the precision measurement of topological Aharonov-Casher effect. We have made a prototype with 200 μm gapped BSEs and confirmed the spatial separation of its two paths at monochromatic cold-neutron beamline MINE2 on JRR-3M reactor in JAEA

  6. Information Sharing Framework (ISF) for Facilitating Development of Fast Reactors and Fuel Cycles

    Kawakubo, Y.; Hoffheins, B.; Inoue, N.; Mongiello, R.; Baldwin, G.; Lee, N.Y.; Chung, Jinho; Kwon, Eun-ha

    2013-01-01

    Conclusion: • Requirements for ISF is currently under development by JAEA, SNL, KINAC and KAERI. • Requirements seek to help implement information sharing following PDCA cycle. • Requirements development is still underway, but expected to be finalized in near future. • Demonstration of ISF will be implemented as the next step. • ISF is expected to facilitate FR avoiding regional NP/NS concerns in a sustainable manner

  7. JAERI TANDEM annual report 2004. April 1, 2004 - March 31, 2005

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

    2006-01-01

    This annual report describes research activities, which have been performed with the JAERI tandem accelerator and its energy booster from April 1, 2004 to March 31, 2005. Summary reports of 48 papers, and lists of publication, personnel and cooperative research with universities are contained. The JAERI (Japan Atomic Energy Research Institute) have been unified with JNC (Japan Nuclear Fuel Cycle Development Institute) and became JAEA (Japan Atomic Energy Agency) on October 1st, 2005. (author)

  8. Establishment of the Japan Atomic Energy Agency

    Okazaki, Toshio

    2006-01-01

    A goal of the 21. century is for society to pursue 'sustainable economic development and prosperous life by recycling resources', thus rejecting 'development based on the waste of resources'. For Japan, which has limited energy resources, it is important to secure safe, inexpensive, environmentally friendly energy resources having long-term availability. To contribute to long-term energy security and solve global environmental issues, and to create advanced competitive science and technology, the Japan Atomic Energy Agency (JAEA) was established by integrating the Japan Atomic Energy Research Institute (JAERI) and the Japan Nuclear Cycle Development Institute (JNC) in October 2005. JAEA is endeavoring to establish nuclear fuel cycles, to contribute to social improvement through hydrogen production initiated by atomic energy, and to pursue research and development of thermonuclear fusion and quantum beam technology. This paper reviews the main R and D activities of JAEA. The structure of the paper is the following: 1. Introduction; 2. Japan Atomic Energy Agency; 3. Efforts to Commercialize the Fast Reactor Cycle; 4. Monju Progress; 5. Geological Disposal of High-Level Radioactive Waste R and D; 6. High Temperature Gas-Cooled Reactor System R and D; 7. Fusion Research and Development; 8. LWR Spent Fuel Reprocessing Technology; 9. Quantum Beam Technologies; 10. Nuclear Safety Research and Regulatory Applications; 11. Basic Science and Engineering Research; 12. Contribution to the Enhanced International Nonproliferation Regimes; 13. Conclusions. To summarize, JAEA will promote the above R and D activities, addressing the following commitments: - On problems that atomic energy faces, we shall extend technical assistance in response to the government and the industrial sectors. - We shall produce technical options to attain political goals to secure medium to long-term stable energy supplies and to solve global environmental issues. - With the high potentials of atomic

  9. Development of manufacturing technology for ITER TF Coil Structure

    Sakurai, Takeru, E-mail: sakurai.takeru@jaea.go.jp; Iguchi, Masahide; Nakahira, Masataka; Inagaki, Takashi; Matsui, Kunihiro; Koizumi, Norikiyo

    2016-11-01

    Highlights: • Heavy thick welding (Max. 287 mm) was performed by balance welding. • Figured out Attachment welding deformation including heavy thick welding. • The deformation of Segments welding was suppressed to 1/3 of previous method. • Based on this study, JAEA started actual ITER TF coil structure manufacturing. - Abstract: Japan Atomic Energy Agency (JAEA) performed a trial of A1 Segment manufacturing of Toroidal Field (TF) coil structure, which is a piece with a radius of curvature 3 m with square channel for coil. Even though both-side welding (balance welding) was preferred to one-side welding considering the welding deformation, it could not be applied to the previous trial due to the difficulty of overhead or horizontal welding by machine. Hence, one-side welding with strong restriction jig was applied in the previous trials. In the latest trial, JAEA adopted a manual balance welding with a development of manufacturing technology. As the result of A1 Segment Mainbody welding trial, welding deformation of the Outer Plate and the Side Plate could have been controlled closer to the target value. JAEA also tried Attachments welding, in which Pre-Compression Flange (PCF) and Extension are welded to A1 Segment Mainbody, and a Segments welding trial, which is a weld between A1 Segment and a part of A2 Segment. A2 Segment is a 3 m straight part with square channel for coil. The inclination of A1 Segment and A2 Segment due to the welding was 2.7 mm. By applying balance welding, the deformation by Segments welding was suppressed to about 1/3 of the one-side welding. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization.

  10. HTGR technology development in Japan advances so much. Leading world technology to global standards

    Ogawa, Masuro; Hino, Ryutaro; Kunitomi, Kazuhiko; Onuki, Kaoru; Inagaki, Yoshiyuki; Takeda, Tetsuaki; Sawa, Kazuhiro

    2007-01-01

    The JAEA has conducted research and development of HTGR for hydrogen production since 1969 and attained the operation of 950degC at reactor coolant outlet of the HTTR in 2004. This article describes present status and future plan of R and D in the area of HTGR technology and high temperature heat utilization and also introduces the design of the commercial HTGR cogeneration system based on R and D results leading to world standards. (T. Tanaka)

  11. Status of JSFR development in phase I FaCT project

    Aoto, Kazumi; Chikazawa, Yoshitaka; Kotake, Shoji; Ito, Takaya

    2011-01-01

    The Fast Reactor Cycle Technology Development (FaCT) project is pursuing commercialization of fast reactor cycle system around 2050 under cooperation of MEXT (Ministry of Education, Culture, Sports, Science and Technology), METI (Ministry of Economy, Trade and Industry), utilities, venders and JAEA (Japan Atomic Energy Agency). As results of the FaCT Phase I, the key technologies for Japan Sodium-cooled Fast Reactor (JSFR) has been evaluated. (author)

  12. Photo-medical valley. 'Photo medical research center'

    Kawanishi, Shunichi; Daido, Hiroyuki; Tajima, Toshiki

    2008-01-01

    To develop a much more compact cancer diagnosis and therapeutic instrument using high intensity laser technology, Japan Atomic Energy Agency (JAEA) has successfully proposed this novel effort to the Ministry of Education, Culture, Sports, Science and Technology (MEXT) program as the creation of a 'photo-medical industrial valley' base in 2007 fiscal year. In this report, a new laser techniques to drive controlled ion beams is described. It is very important approach to realize a laser-driven ion accelerator. (author)

  13. Real time simulator for material testing reactor

    Takemoto, Noriyuki; Imaizumi, Tomomi; Izumo, Hironobu; Hori, Naohiko; Suzuki, Masahide; Ishitsuka, Tatsuo; Tamura, Kazuo

    2012-01-01

    Japan Atomic Energy Agency (JAEA) is now developing a real time simulator for a material testing reactor based on Japan Materials Testing Reactor (JMTR). The simulator treats reactor core system, primary and secondary cooling system, electricity system and irradiation facility systems. Possible simulations are normal reactor operation, unusual transient operation and accidental operation. The developed simulator also contains tool to revise/add facility in it for the future development. (author)

  14. Establishment of data base files of thermodynamic data developed by OECD/NEA. Part 4. Addition of thermodynamic data for iron, tin and thorium

    Yoshida, Yasushi; Kitamura, Akira

    2014-12-01

    Thermodynamic data for compounds and complexes of elements with auxiliary species specialized in modeling requirements for safety assessments of radioactive waste disposal systems have been developed by the Thermochemical Data Base (TDB) project of the Nuclear Energy Agency in the Organization for Economic Co-operation and Development (OECD/NEA). Recently, thermodynamic data for aqueous complexes, solids and gases of thorium, tin and iron (Part 1) have been published in 2008, 2012 and 2013, respectively. These thermodynamic data have been selected on the basis of NEA’s guidelines which describe peer review and data selection, extrapolation to zero ionic strength, assignment of uncertainty, and temperature correction; therefore the selected data are considered to be reliable. The reliability of selected thermodynamic data of TDB developed by Japan Atomic Energy Agency (JAEA-TDB) has been confirmed by comparing with selected data by the NEA. For this comparison, text files of the selected data on some geochemical calculation programs are required. In the present report, the database files for the NEA’s TDB with addition of selected data for iron, tin and thorium to the previous files have been established for use of PHREEQC, Geochemist’s Workbench and EQ3/6. In addition, as an example of confirmation of quality, dominant species in iron TDB were compared in Eh-pH diagram and differences between JAEA-TDB and NEA-TDB were shown. Data base files established in the present study will be at the Website of thermodynamic, sorption and diffusion database in JAEA (http://migrationdb.jaea.go.jp/). A CD-ROM is attached as an appendix. (J.P.N.)

  15. Japanese FR Deployment Scenario Study after the Fukushima Accident

    Ono, Kiyoshi; Shiotani, Hiroki; Ohtaki, Akira; Mukaida, Kyoko; Abe, Tomoyuki

    2013-01-01

    Conclusion: • The results revealed a need for the implementation of reprocessing and development of FR from the view point of reducing waste, etc. in the medium to long term. • JAEA’s contribution to international cooperation and standardization focusing on the enhancement of safety and reduction of the radioactive waste burden will be increasingly important in current situation. • JAEA intend to continue to build and propose FR deployment scenarios and identify their characteristics

  16. Data of fractures based on the deep borehole investigations in the Horonobe Underground Research Laboratory project. Phase 1

    Kusano, Tomohiro; Ishii, Eiichi

    2016-02-01

    Japan Atomic Energy Agency (JAEA) is performing the Horonobe Underground Research Laboratory Project, which includes a scientific study of the deep geological environment as a basis of research and development for geological disposal of high level radioactive wastes (HLW), in order to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in the sedimentary rock. This report aims at compiling fracture data of drill core obtained from the Horonobe Underground Research Laboratory Project (Phase 1). (author)

  17. Assessment report of research and development activities in FY2006 activity. 'Fast reactor cycle technology development project' (Interim report)

    2007-08-01

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') asked the advisory committee 'evaluation Committee of Research and Development (R and D) Activities for Advanced Nuclear System/Nuclear Fuel Cycle Technology' (hereinafter referred to as 'Committee') to assess the interim report on Fast Reactor Cycle Technology Development Project ' (former 'Feasibility Study on Commercialized Fast Reactor Cycle Systems') in FY2006, in accordance with 'General Guideline for the Evaluation of Government R and D Activities' by Japanese Cabinet Office, 'Guideline for Evaluation of R and D in Ministry of Education, Culture Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to JAEA's request, the Committee assessed the R and D program over five years, the criteria for adoption judgment on innovative technologies at the end of 2010 (Project Review), and the organization structure for R and D. etc. (Management Review). As a result of review, the Committee concluded that this R and D program and its organization structure are almost reasonable. (author)

  18. A study for the safety evaluation of geological disposal of TRU waste and influence on disposal site design by change of amount of TRU waste (Joint research)

    Hasegawa, Makoto; Kondo, Hitoshi; Takahashi, Kuniaki; Funabashi, Hideaki; Kawatsuma, Shinji; Kamei, Gento; Hirano, Fumio; Mihara, Morihiro; Ueda, Hiroyoshi; Ohi, Takao; Hyodo, Hideaki

    2011-02-01

    In the safety evaluation of the geological disposal of the TRU waste, it is extremely important to share the information with the Research and development organization (JAEA: that is also the waste generator) by the waste disposal entrepreneur (NUMO). In 2009, NUMO and JAEA set up a technical commission to investigate the reasonable TRU waste disposal following a cooperation agreement between these two organizations. In this report, the calculation result of radionuclide transport for a TRU waste geological disposal system was described, by using the Tiger code and the GoldSim code at identical terms. Tiger code is developed to calculate a more realistic performance assessment by JAEA. On the other hand, GoldSim code is the general simulation software that is used for the computation modeling of NUMO TRU disposal site. Comparing the calculation result, a big difference was not seen. Therefore, the reliability of both codes was able to be confirmed. Moreover, the influence on the disposal site design (Capacity: 19,000m 3 ) was examined when 10% of the amount of TRU waste increased. As a result, it was confirmed that the influence of the site design was very little based on the concept of the Second Progress Report on Research and Development for TRU Waste Disposal in Japan. (author)

  19. An lesson learned from the consultation activity with community regarding the Mizunami Underground Laboratory project. From a viewpoint of procedural and distributive justice

    Nishio, Kazuhisa; Osawa, Hideaki

    2016-01-01

    Japan Atomic Energy Agency (JAEA) has promoted the Mizunami Underground Research Laboratory (Mizunami URL) as one of generic URL to perform basic research of waste disposal technology for about twenty years. JAEA had carried out consultation activities with local people and community from 1995 when the plan of Mizunami URL opened at the time, because an early approach of JAEA caused a sense of social distrust and concern, which the study area of Mizunami URL would be candidate site of real repository. In this paper, we conducted normative analysis intended for the consultation activities from a viewpoint of procedural justice and distributed justice, used as the social psychological framework in terms of public NIMBY facility. The results show that it is important to develop local partnership, composed of representative local people and organization, at early start in the light of procedural justice and to support deliberation regarding distributive justice and so on by local partnership in the aspect of information and financial administration. (author)

  20. Mizunami Underground Research Laboratory project. Plan for fiscal year 2017

    Ishibashi, Masayuki; Hama, Katsuhiro; Iwatsuki, Teruki; Matsui, Hiroya; Takeuchi, Ryuji; Ikeda, Koki; Mikake, Shinichiro; Iyatomi, Yosuke; Sasao, Eiji; Koide, Kaoru

    2017-10-01

    The Mizunami Underground Research Laboratory (MIU) Project is being pursued by the Japan Atomic Energy Agency (JAEA) to enhance the reliability of geological disposal technologies through investigations of the deep geological environment in the crystalline host rock (granite) at Mizunami, Gifu Prefecture, central Japan. On the occasion of the reform of the entire JAEA organization in 2014, JAEA identified three important issues on the geoscientific research program: 'Development of countermeasure technologies for reducing groundwater inflow', 'Development of modelling technologies for mass transport' and 'Development of drift backfilling technology', based on the latest results of the synthesizing research and development (R and D). The R and D on three remaining important issues has been carrying out on the MIU Project. This report summarizes the R and D activities planned for fiscal year 2017 on the basis of the MIU Master Plan updated in 2015 and Investigation Plan for the Third Medium to Long-term Research Phase. (author)

  1. Annual report of Nuclear Technology and Education Center. April 1, 2007-March 31, 2008

    2009-03-01

    This annual report summarizes the activities of Nuclear Technology and Education Center (NuTEC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2007. This is the third year since the inauguration of JAEA, and NuTEC now flexibly designs and carries out training courses upon request while carrying out the annually scheduled training programs. During this period, the number of trainees completing the domestic training courses was 466, and that for staff technical training was 694. Three prep-examination training courses for '1st class radiation protection supervisor', 'Nuclear fuel protection supervisor' and 'Professional engineer on nuclear and radiation' which were opened only for staff members were newly opened to the public. JAEA continued its cooperative activities with universities; cooperation with graduate school of University of Tokyo, cooperative graduate school program with 14 graduate schools and 1 under-graduate school, and Nuclear HRD Program initiated by MEXT and METI implemented since 2007. Joint course has started networking 3 universities utilizing the Japan Nuclear Education Network, and trial experimental courses for students from newly participating universities were offered. International cooperation was also conducted as scheduled. Joint training course and Instructor training program were carried out bilaterally with Indonesia, Thailand and Vietnam. Human Resources Development Workshop under the Forum for Nuclear Cooperation in Asia was arranged, and Asian Nuclear Training and Education Program to enhance the matching of the needs and available training program of the participating countries were discussed. (author)

  2. Proceedings of the international workshop on mechanistic understanding of radionuclide migration in compacted/intact systems

    Tachi, Yukio; Yui, Mikazu

    2010-03-01

    The international workshop on mechanistic understanding of radionuclide migration in compacted / intact systems was held at ENTRY, JAEA, Tokai on 21st - 23rd January, 2009. This workshop was hosted by Japan Atomic Energy Agency (JAEA) as part of the project on the mechanistic model/database development for radionuclide sorption and diffusion behavior in compacted / intact systems. The overall goal of the project is to develop the mechanistic model / database for a consistent understanding and prediction of migration parameters and its uncertainties for performance assessment of geological disposal of radioactive waste. The objective of the workshop is to integrate the state-of-the-art of mechanistic sorption and diffusion model in compacted / intact systems, especially in bentonite / clay systems, and discuss the JAEA's mechanistic approaches and future challenges, especially the following discussions points; 1) What's the status and difficulties for mechanistic model/database development? 2) What's the status and difficulties for applicability of mechanistic model to the compacted/intact system? 3) What's the status and difficulties for obtaining evidences for mechanistic model? 4) What's the status and difficulties for standardization of experimental methodology for batch sorption and diffusion? 5) What's the uncertainties of transport parameters in radionuclides migration analysis due to a lack of understanding/experimental methodologies, and how do we derive them? This report includes workshop program, overview and materials of each presentation, summary of discussions. (author)

  3. Assessment report of research and development activities. Activity: 'Advanced science research' (Pre-review report)

    2010-11-01

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') consulted an assessment committee, 'Evaluation Committee of Research Activities for Advanced Science Research' (hereinafter referred to as 'Committee') for prior assessment of 'Advanced Science Research,' in accordance with 'General Guideline for the Evaluation of Government Research and Development (R and D) Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to the JAEA's request, the Committee assessed the research program and activities of the Advanced Science Research Center (hereinafter referred to as 'ASRC') for the period of five years from April 2010. The Committee evaluated the management and the research program of the ASRC based on the explanatory documents prepared by the ASRC and the oral presentations with questions-and-answers by the Director and the research group leaders. This report summarizes the result of the assessment by the Committee with the Committee report attached from page 7. (author)

  4. Assessment report on research and development activities. Activity: 'Advanced science research' (Interim report)

    NONE

    2012-11-15

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') consulted an assessment committee, 'Evaluation Committee of Research Activities for Advanced Science Research' (hereinafter referred to as 'Committee') for interim assessment of 'Advanced Science Research,' in accordance with 'General Guideline for the Evaluation of Government Research and Development (R and D) Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to the JAEA's request, the Committee assessed the research programs and activities of the Advanced Science Research Center (hereinafter referred to as 'ASRC') for the period of two years from April 2010. The Committee evaluated the management and the research programs of the ASRC based on the explanatory documents prepared by the ASRC and the oral presentations with questions-and-answers by the Director and the research group leaders. This report summarizes the result of the assessment by the Committee with the Committee report attached from page 7. (author)

  5. Assessment report of research and development activities. Activity: advanced science research' (Interim report)

    2008-08-01

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') consults an assessment committee, 'Evaluation Committee of Research Activities for Advanced Science Research' (hereinafter referred to as 'Committee') for interim assessment of 'Advanced Science Research,' in accordance with General Guideline for the Evaluation of Government Research and Development (R and D) Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to the JAEA's request, the Committee assessed the research program of the Advanced Science Research Center (hereinafter referred to as 'ASRC') during the period of two years from October 2005 to September 2007. The Committee evaluated the management and research activities of the ASRC based on the explanatory documents prepared by the ASRC, the oral presentations with questions-and-answers by the Director and the research group leaders, and interviews from group members through on-site visits by the Committee members. One CD-ROM is attached as an appendix. (J.P.N.)

  6. Development status of data acquisition system for IFMIF/EVEDA accelerator

    Usami, Hiroki; Takahashi, Hiroki; Komukai, Satoshi

    2015-01-01

    EU and JAEA are advancing development of Linear IFMIF Prototype Accelerator (LIPAc) control system jointly, but JAEA keeps developing central control system (CCS) mainly. Data transfer during an equipment control system of CCS and EU is performed through EPICS. JAEA is using PostgreSQL as 1 of development elements in CCS and is advancing development of the system to record the whole EPICS data of LIPAc (the data acquisition system). On the other hand, a data acquisition is performed using BEAUTY (Best Ever Archive Toolset, yet) in an element test of equipment at Europe. Therefore '1 client refers to collected data by more than one server machine' with 'compatibility securement of data with BEAUTY' in case of development of the data acquisition system of CCS, and, it's necessary to consider 'To do a data acquisition and backup work at the same time.' For the moment, former 2 are in progress. And a demonstration of the data acquisition system is being performed simultaneously with commissioning in injector. The data acquisition system is collecting data of injector other ones, and the data reference by a monitor with CSS (Control System Studio) is also possible. We will report on the current state of the development of the data acquisition system by making reference to a result of the test by injector commissioning. (author)

  7. Annual report of Nuclear Emergency Assistance and Training Center. April 1, 2008 - March 31, 2009

    Kanamori, Masashi; Hashimoto, Kazuichiro; Terunuma, Hiroshi; Ikeda, Takeshi; Ohmura, Akiko; Terakado, Naoya; Nagakura, Tomohiro; Fukumoto, Masahiro; Watanabe, Fumitaka; Yamamoto, Kazuya; Abe, Minako; Kikuchi, Masayuki; Sumiya, Akihiro; Matsusaka, Masaru

    2009-09-01

    When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (JAEA) provides technical support to the National government, local governments, police, fire station and license holder etc. They are Designated Public Organizations conforming to the Basic Law on Emergency Preparedness and the Basic Plan for Disaster Countermeasures. The Nuclear Emergency Assistance and Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an Off-Site Center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, provides for the dispatch of specialist as required, supplies emergency equipments and materials to the Joint Council of Nuclear Disaster Countermeasures, which meets at the Off-Site Center. NEAT provide various lectures and training course concerning nuclear disaster prevention for those personnel taking an active part in emergency response organizations at normal time. And NEAT researches on nuclear disaster prevention and also cooperate with international organizations. This annual report summarized the activities of JAEA/NEAT in the fiscal year 2008. (author)

  8. Study of waste acceptance criteria for low-level radioactive waste from medical, industrial, and research facilities (Contract research)

    Koibuchi, Hiroto; Dohi, Terumi; Ishiguro, Hideharu; Hayashi, Masaru; Senda, Masaki

    2008-12-01

    Japan Atomic Energy Agency (JAEA) is supposed to draw up the plan for the disposal program of the very low-level radioactive waste and low-level radioactive waste generated from medical, industrial and research facilities. For instance, there are these facilities in JAEA, universities, private companies, and so on. JAEA has to get to know about the waste and its acceptance of other institutions described above because it is important for us to hold the licenses for the disposal program regarding safety assessment. This report presents the basic data concerning radioactive waste of research institutes etc. except RI waste, domestic and foreign information related to acceptance criteria for disposal of the low-level radioactive waste, the current status of foreign medical waste management, waste acceptance, and such. In this report, Japan's acceptance criteria were summarized on the basis of present regulation. And, the criteria of foreign countries, United States, France, United Kingdom and Spain, were investigated by survey of each reference. In addition, it was reported that the amount of waste from laboratories etc. for near-surface disposal and their characterization in our country. The Subjects of future work: the treatment of hazardous waste, the problem of the double-regulation (the Nuclear Reactor Regulation Law and the Law Concerning Prevention from Radiation Hazards due to Radioisotopes and Others) and the possession of waste were discussed here. (author)

  9. Assessment report of research and development activities. Activity: 'Nuclear science and engineering research' (Interim report)

    2013-11-01

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') consults an assessment committee, 'Evaluation Committee of Research Activities for Nuclear Science and Engineering' (hereinafter referred to as 'Committee') for interim assessment of 'Nuclear Science and Engineering,' in accordance with 'General Guideline for the Evaluation of Government Research and Development (R and D) Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by the JAEA. In response to the JAEA's request, the Committee assessed the research program of the Nuclear Science and Engineering Directorate (hereinafter referred to as 'NSED') and Center for Computational Science and e-Systems (hereinafter referred to as 'CCSE') during the period of about four years from September 2008 to September 2012. The Committee evaluated the management and research activities of the NSED and the CCSE based on explanatory documents prepared by the NSED and the CCSE, and oral presentations with questions-and-answers by unit managers etc. A CD-ROM is attached as an appendix. (J.P.N.)

  10. Development of the environmental data management system

    Tatebe, Kazuaki; Suzuki, Yurina; Shirato, Seiichi; Sato, Yoshinori

    2012-02-01

    The recent society requires business activities with environmental consideration to every enterprise. Also, Japanese laws require those activities. For example, 'Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc, by Facilitating Access to Environmental Information, and Other Measures' (Environmental Consideration Law) mandates publication of a report relating to the activities of environmental consideration to each enterprise above designated size. 'Act on the Rational Use of Energy' mandates the report of the results of energy consumption and the long-term plan of the rational use of energy. Moreover, 'Act on Promotion of Global Warming Countermeasures' mandates the report of the greenhouse gas emissions. In addition to those, 'Water Pollution Control Law', 'Waste Management and Public Cleaning Law' and other environmental laws as well as environmental ordinances require business activities with environmental consideration to all companies. So, it is very important for Japan Atomic Energy Agency (JAEA) to report business activities with environmental consideration in order to build up trustful relations with the nation and communities. The Environmental Data Management System has been developed as the data base of business activities with environmental consideration in JAEA and as the means to promote the activities at every site and office of JAEA. This report summarizes the structure of the Environmental Data Management System, kinds of environmental performance data treated by the system, and gathering methods of the data. (author)

  11. Assessment report of research and development activities in FY2014. Activity: 'Quantum beam science research' (Result evaluation)

    2015-09-01

    Japan Atomic Energy Agency (hereafter referred to as 'JAEA') consulted an assessment committee, 'Evaluation Committee of Research Activities for Quantum Beam Science' (hereafter referred to as 'Committee') for result evaluation of 'Quantum Beam Science', in accordance with 'General Guideline for the Evaluation of Government Research and Development (R and D) Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to the JAEA's request, the Committee assessed the research program of the Quantum Beam Science Center (hereafter referred to as 'QuBS') during the period from April 2010 to September 2014. The Committee evaluated the management and research activities of QuBS based on the explanatory documents and oral presentations. (author)

  12. Assessment report of research and development activities in FY2014. Activity: 'Quantum beam science research' (In-advance evaluation)

    2015-09-01

    Japan Atomic Energy Agency (hereafter referred to as 'JAEA') consulted an assessment committee, 'Evaluation Committee of Research Activities for Quantum Beam Science' (hereafter referred to as 'Committee') for result evaluation of 'Quantum Beam Science', in accordance with 'General Guideline for the Evaluation of Government Research and Development (R and D) Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to the JAEA's request, the Committee assessed the research program of the Quantum Beam Science Center (hereafter referred to as 'QuBS') during the period from April 2015 to March 2022. The Committee evaluated the management and research activities of QuBS based on the explanatory documents and oral presentations. (author)

  13. Assessment report of research and development activities in JFY2008 activity. 'Fast Reactor Cycle Technology Development Project' (Interim report)

    2009-08-01

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') asked the advisory committee 'Evaluation Committee of Research and Development Activities for Advanced Nuclear System/Nuclear Fuel Cycle Technology' (hereinafter referred to as 'Committee') to assess the interim report on 'Fast Reactor Cycle Technology Development Project (FaCT project)' in JFY2008, in accordance with 'General Guideline for the Evaluation of Government R and D Activities' by Japanese Cabinet Office, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response of JAEA's request, the Committee assessed the 2006-2008 R and D results, the 2009-2010 R and D program and its R and D management. The Committee confirmed the progress status of the R and D for the adoption judgment on innovative technologies scheduled in 2010. As a result of the review, the committee has made suggestions for the future R and D plan and the improvements of the R and D organization structure/management. A CD-ROM is attached as an appendix. (J.P.N.)

  14. Report on the 9th workshop on the innovative water reactor for flexible fuel cycle

    Ishikawa, Nobuyuki; Kobayashi, Noboru; Okubo, Tsutomu; Uchikawa, Sadao

    2006-07-01

    The research on Innovative Water Reactor for Flexible Fuel Cycle (FLWR) has been performed in JAEA for the development of future innovative reactor. The workshop on FLWRs has been held every year since 1998 aiming at information exchange with other organizations such as universities, laboratories, utilities and vendors. The 9th workshop was held on March 1, 2006 under the joint auspices of JAEA and North Kanto and Kanto-Koetsu branches of Atomic Energy Society of Japan with 64 participants. The workshop began with presentation entitled 'Activities on Nuclear Science and Engineering Research and Collaboration with Industry in JAEA', followed by presentations entitled 'Progress of Research and Development on FLWR' and 'On Final Report of Feasibility Study (phase 2) on Commercialized FBR Cycle Systems'. Then two lectures followed: 'Core and Fuel Design on Super Light Water Reactor' by Tokyo University and 'Recent trends on the Development of Next Generation Nuclear Reactor' by Institute of Applied Energy. This report summarizes the lectures of the workshop. (author)

  15. Assessment report of research and development on 'the abolition measures of nuclear facilities and associated technology development' and 'radioactive waste treatment and disposal and associated technology development' (result evaluation, in advance evaluation) and 'technology development related to reprocessing of nuclear fuel material' (In advance evaluation)

    2015-07-01

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') consulted the 'Evaluation Committee for Decommissioning and Radioactive Waste Management ' for result evaluation and in advance evaluation of 'The abolition measures of nuclear facilities and associated technology development' project and 'Radioactive waste treatment and disposal and associated technology development' project and 'Technology development related to reprocessing of nuclear fuel material' project in accordance with the 'Guideline for evaluation of government R and D activities', the 'Guideline for evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology (MEXT)' and the 'Operational rule for evaluation of R and D activities' by JAEA. In response to the JAEA's request, the Evaluation Committee for Decommissioning and Radioactive Waste Management, in accordance with the evaluation method as defined in the Committee deliberations and oral report and deliberation of material about the R and D project of three was conducted. This report summarizes the results of the assessment by the Committee with the Committee report. (author)

  16. Annual report of Nuclear Emergency Assistance and Training Center. April 1, 2006 - March 31, 2008

    2008-12-01

    When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (JAEA) provides technical support to the National government, local governments, police, fire station and license holder etc. They are Designated Public Organizations conforming to the Basic Law on Emergency Preparedness and the Basic Plan for Disaster Countermeasures. The Nuclear Emergency Assistance and Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an off-site center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, provides for the dispatch of specialist as required, supplies emergency equipments and materials to the Joint Council of Nuclear Disaster Countermeasures, which meets at the off-site center. NEAT provide various lectures and training course concerning nuclear disaster prevention for those personnel taking an active part in emergency response organizations at normal time. And NEAT researches on nuclear disaster prevention and also cooperate with international organizations. This annual report summarized the activities of JAEA/NEAT in the fiscal year 2006 and 2007. (author)

  17. Assessment report of research and development activities FY2014. Activity: 'Advanced science research' (Final report)

    2015-09-01

    Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') consulted an assessment committee, 'Evaluation Committee of Research Activities for Advanced Science Research' (hereinafter referred to as 'Committee') for final evaluation and prior assessment of 'Advanced Science Research,' in accordance with 'General Guideline for the Evaluation of Government Research and Development (R and D) Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to the JAEA's request, the Committee assessed the research programs and activities of the Advanced Science Research Center (hereinafter referred to as 'ASRC') for the period of five years from April 2010 and the research programs from April 2015. The Committee evaluated the management and the research programs of the ASRC based on the explanatory documents prepared by the ASRC and the oral presentations with questions-and-answers by the Director and the research group leaders. This report summarizes the results of the assessment by the Committee with the Committee report attached. (author)

  18. Research and development of fusion grid infrastructure based on atomic energy grid infrastructure (AEGIS)

    Suzuki, Y.; Nakajima, K.; Kushida, N.; Kino, C.; Aoyagi, T.; Nakajima, N.; Iba, K.; Hayashi, N.; Ozeki, T.; Totsuka, T.; Nakanishi, H.; Nagayama, Y.

    2008-01-01

    In collaboration with the Naka Fusion Institute of Japan Atomic Energy Agency (NFI/JAEA) and the National Institute for Fusion Science of National Institute of Natural Science (NIFS/NINS), Center for Computational Science and E-systems of Japan Atomic Energy Agency (CCSE/JAEA) aims at establishing an integrated framework for experiments and analyses in nuclear fusion research based on the atomic energy grid infrastructure (AEGIS). AEGIS has been being developed by CCSE/JAEA aiming at providing the infrastructure that enables atomic energy researchers in remote locations to carry out R and D efficiently and collaboratively through the Internet. Toward establishing the integrated framework, we have been applying AEGIS to pre-existing three systems: experiment system, remote data acquisition system, and integrated analysis system. For the experiment system, the secure remote experiment system with JT-60 has been successfully accomplished. For the remote data acquisition system, it will be possible to equivalently operate experimental data obtained from LHD data acquisition and management system (LABCOM system) and JT-60 Data System. The integrated analysis system has been extended to the system executable in heterogeneous computers among institutes

  19. Annual report of Nuclear Human Resource Development Center. April 1, 2010 - March 31, 2011

    2012-03-01

    This annual report summarizes the activities of Nuclear Human Resource Development Center (NuHRDeC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2010. In this fiscal year, NuHRDeC flexibly designed and conducted as need training courses upon requests while conducting the annually scheduled training programs, and actively addressed the challenge of human resource development, such as to enhance the collaboration with academia and to expand the number of participating countries for international training. The number of trainees who completed the domestic training courses in 2010 was slightly increased to 340, which is 6 percent more than the previous year. The number of those who completed the staff technical training courses was 879 in 2010, which is 12 percent more than the previous year. As a result, the total number of trainees during this period is about 10 percent more than the previous year. In order to correspond with the needs from outside of JAEA, four temporary courses were held upon the request from Nuclear and Industrial Safety Agency (NISA), Ministry of Economy, Trade and Industry (METI). JAEA continued its cooperative activities with universities; cooperation with graduate school of University of Tokyo, and the cooperative graduate school program was enlarged to cooperate with totally 19 graduate schools, one faculty of undergraduate school, and one technical college, including the newly joined 1 graduate school in 2010. JAEA also continued cooperative activities with Nuclear HRD Program initiated by MEXT and METI in 2007. The joint course has continued networking with six universities through utilizing the remote education system, Japan Nuclear Education Network (JNEN), and special lectures, summer and winter practice were also conducted. In respect of International training, NuHRDeC continuously implemented the Instructor Training Program (ITP) by receiving the annual sponsorship from MEXT. In fiscal year 2010, four countries (Bangladesh

  20. Development and management of the knowledge base for the geological disposal technology. Annual report 2006

    Umeda, Koji; Oyama, Takuya; Kurosawa, Hideki; Semba, Takeshi; Takeuchi, Shinji; Tajikara, Masayoshi; Tsuruta, Tadahiko; Yasue, Ken-ichi; Ohi, Takao; Oda, Chie; Kamei, Gento; Kobayashi, Yasushi; Sasaki, Yasuo; Sawada, Atsushi; Taniguchi, Naoki; Tanai, Kenji; Naito, Morimasa; Nakayama, Masashi; Kuno, Yoshio; Fujita, Tomoo; Honda, Akira; Mihara, Morihiro; Miyahara, Kaname; Osawa, Hideaki; Fujishima, Atsushi; Kuji, Masayoshi; Saito, Haruo; Sanada, Hiroyuki; Niizato, Tadafumi; Funaki, Hironori; Maekawa, Keisuke; Fujiwara, Kenso

    2007-12-01

    To increase technical reliability in geological disposal technology of high-level radioactive waste, JAEA have been conducting R and D activities in the fields in the repository engineering, performance assessment (PA) of the geological disposal system, and geoscientific study. In the field of R and D on the repository engineering, laboratory experimental studies at Tokai Research Center are carried out by engineering-scale and non-radiogenic experiments. The studies on performance assessment include more realistic model development with extensive computer analyses and acquisition of basic data concerning the chemical properties and migration behavior of radionuclides under geological disposal conditions. The information obtained from the Underground Research Laboratories (URLs) is used to provide a realistic condition of geological environments for these studies. The R and D studies are also carried out for TRU waste. A particular JAEA R and D activity is to promote the projects of two Underground Research Laboratories (URLs): one at Mizunami city, in crystalline rock and the other at Horonobe town, in sedimentary rock. In the present stage (2nd R and D phase) of the URL projects, the investigation are being carried out during the excavation of shafts and drifts. Data obtained from the investigations will serve to verify and refine the results from the surface-based investigations and characterize the evolution of the geological environment during drift excavation. The research on natural processes, such as fault and volcanic activities, is also conducted to provide better understanding of long-term stability on the geological environment. JAEA has initiated a project to develop the next generation of novel knowledge management system (KMS) to develop and manage the technical knowledge base for supporting implementers and regulators. This knowledge base includes all technical achievements by the JAEA as well as know-how and experience which have been accumulated

  1. The collaboration of Japan and France on the design of ASTRID sodium fast reactor

    Varaine, Frederic; Rodriguez, Gilles; Hamy, Jean-Marie; Hayafune, Hiroki; Iitsuka, Toru; Mochida, Haruo

    2017-01-01

    Since the beginning (2010), the management of ASTRID project was organized around a strong involvement of industrial partners in the reactor design. The ASTRID project has now entered into its Basic Design phase (duration from year 2016 to 2019) with fourteen industrial partners. Since 2014, a partnership with Japanese nuclear institutes and industries is effective on two main items: ASTRID reactor design studies and R and D in support of Sodium Fast Reactors (SFR). This French-Japanese collaboration on ASTRID Program and Sodium Fast Reactor has been set up in two steps: the signature of a General Arrangement between CEA and the representatives of MEXT and METI on May 5th, 2014; and in a second step, an Implementing Arrangement signed the same year on August 7th by CEA, AREVA NP, JAEA, MHI and MFBR. This collaboration of a significant level is foreseen to run at least up to the end of 2019. At the beginning, the collaborative work (input data, planning and deliverables) was divided in 29 Task Sheets covering ASTRID design (3 Task Sheets) and R and D (26 Tasks Sheets). Since 2016, the contribution of JAEA / MHI-MFBR to the ASTRID reactor engineering studies has significantly raised, passing from 3 to 9 Design Task Sheets. Thus, even if the cooperation is recent, the cooperation between CEA, AREVA NP, JAEA, MHI-MFBR is fruitful and it has been planned by all parties to enlarge Japanese contribution to a process called “Joint Evaluation” to prepare future Joint Design. This paper aims at the overview of the significant involvement of JAEA / MHI-MFBR in the ASTRID design studies through these 9 Task Sheets, covering in particular the design of an active decay heat removal system, and of a passive reactor shutdown system based on a Curie point electromagnet system. MHI / MFBR teams are also implies in fabricability studies of complex component such as the Above Core Structure or the Polar Table. In addition the new Task Sheets are now focusing on thermal

  2. Development of CDE (calculation system for decontamination effect) for the support of decontamination to restore the environment. Software visually depicting the effect of decontamination Work

    Satoh, Daiki

    2012-01-01

    CDE in the title developed by Japan Atomic Energy Agency (JAEA) is explained for its use to support the cleaning work of the environment contaminated by the Fukushima Daiichi Nuclear Power Plant Accident (Mar. 11, 2011). With this CDE software (available at http://nsed.jaea.go.jp/josen, from Nov. 2, 2011), the effect of decontamination schedule/work can be evaluable rapidly and accurately by calculating the ambient dose rates before and after the work. Access number to the CDE site until Jan., 2012, amounts to 402, for the purposes of ambient dose assessment (20%), planning of decontamination (15%), study/investigation (15%), etc. The system software is operable in Microsoft Excel with Graphical User Interface (GUI) described by VBA (Visual Basic for Applications). To be inputted in CDE are the map of the region subjected to decontamination, data of surface contamination density and of decontamination coefficients for the area relief, all of which are available through the internet and actual measurement, which is then followed by output as tables and figures of distribution of the ambient dose rate before and after the work, and of the rate reduction coefficient. Radiation subjected to calculation is from radiocesium ( 134 Cs and 137 Cs). When the software is compared for its accuracy with those by previous software Particle and Heavy Ion Transport Code System (PHITS) and by actual measurement, their results all show a virtually satisfactory agreement, and the time necessary for calculation is over several-ten hours in PHITS, and within about 10 seconds, in CDE. Updated information of CDE is available at the above mentioned site and twitter.com/JAEA_nsed. (T.T.)

  3. Development of the sorption and diffusion database system for safety assessment of geological disposal

    Tachi, Yukio; Tochigi, Yoshikatsu; Suyama, Tadahiro; Saito, Yoshihiko; Yui, Mikazu; Ochs, Michael

    2009-02-01

    Japan Atomic Energy Agency (JAEA) has been developing databases of sorption and diffusion parameters in buffer material (bentonite) and rock, which are key parameters for safety assessment of the geological disposal. These sorption and diffusion databases (SDB/DDB) have been firstly developed as an important basis for the H12 performance assessment (PA) of high-level radioactive waste disposal in Japan, and have been provided through the Web. JAEA has been and is continuing to improve and update the SDB/DDB in view of potential future data needs, focusing on assuring the desired quality level and testing the usefulness of the existing databases for possible applications to parameter-setting for the deep geological environment. The new web-based sorption and diffusion database system (JAEA-SDB/DDB) has been developed to utilize quality assuring procedure and to allow effective application for parameter setting, by adding the following functions to the existing database; - consistency and linkage between sorption and diffusion database - effective utilization of quality assuring (QA) guideline and categolized QA data - additional function for estimating of parameters and graphing of relation between parameters - counting and summarizing function for effective access to respective data for parameter setting. In the present report, practical examples were illustrated regarding the applicability of the database system to the parameter setting by using additional functions such as QA information and data estimation. This database system is expected to make it possible to obtain quick overview of the available data from the database, and to have suitable access to the respective data for parameter-setting for performance assessment and parameter-deriving for mechanistic modeling in traceable and transparent manner. (author)

  4. Risk communication practice after the Fukushima Daiichi Nuclear Power Station Accident. Interactive explanatory meeting on radiation and its health effects in Ibaraki prefecture

    Ayame, Junko; Sugiyama, Kenji; Takashita, Hirofumi; Yamamoto, Ryuuichi

    2016-02-01

    Large amounts of radioactive material were released into the environment during the accident at the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company (hereinafter referred to as Fukushima nuclear accident) in March, 2011. The radiation dose rose in a large area of plural prefectures including Fukushima prefecture, and many people had anxiety about radiation and its health effects on their bodies. In such a situation, Japan Atomic Energy Agency (JAEA) received a lot of inquiries and lecture requests about radiation from local residents in Japan. R and D Institutes/Centers of JAEA had explanatory meetings and lectures on radiation and its health effects in response to those requests. Nuclear Fuel Cycle Engineering Laboratories (hereinafter referred to as NCL) of JAEA has held the explanatory meetings in Ibaraki prefecture since May 2011 in order to transmit factual information and reduce the excessive anxiety about radiation risk, based on our experience of risk communication practice and research activities over 10 years. Applying to our past risk communication process to the explanatory meetings, we built a process of interactivity between participants and our staff for the meetings. We incorporated the participants' needs into the meetings, and, as far as possible, we had interactive two-way communication so that the meetings were not one-way and persuasive but promote mutual understanding. According to the opinions and the results of questionnaire survey that were received from the participants, it became evident that the interactive explanatory meetings were effective in reducing participants' anxiety. This report explains the risk communication process for carrying out the explanatory meeting, and shows the activities of the meetings, questions and opinions from the participants, and questionnaire results that NCL implemented. (author)

  5. Information collection regarding geoscientific monitoring techniques during closure of underground facility in crystalline rock

    Hosoya, Shinichi; Yamashita, Tadashi; Iwatsuki, Teruki; Saegusa, Hiromitsu; Onoe, Hironori; Ishibashi, Masayuki

    2016-01-01

    The Mizunami Underground Research Laboratory (MIU) project is being pursued by the Japan Atomic Energy Agency (JAEA) to enhance the reliability of geological disposal technologies through investigations of the deep geological environment in the crystalline host rock (granite) at Mizunami City in Gifu Prefecture, central Japan. On the occasion of the reform of the entire JAEA organization in 2014, JAEA identified the critical issues on the geoscientific research program: “Development of modelling technologies for mass transport”, “Development of drift backfilling technologies” and “Development of technologies for reducing groundwater inflow”, based on the latest results of the synthesizing R and D. The purposes of the “Development of drift backfilling technologies” are to develop closure methodology and technology, and long-term monitoring technology, and to evaluate resilience of geological environment. In order to achieve the purposes, previous information from the case example of underground facility constructed in crystalline rock in Europe has been collected in this study. In particular, the boundary conditions for the closure, geological characteristics, technical specifications, and method of monitoring have been focused. The information on the international project regarding drift closure test and development of monitoring technologies has also been collected. In addition, interviews were conducted to Finnish and Swedish specialists who have experiences involving planning, construction management, monitoring, and safety assessment for the closure to obtain the technical knowledge. Based on the collected information, concept and point of attention, which are regarding drift closure testing, and planning, execution management and monitoring on the closure of MIU, have been specified. (author)

  6. Disposal project for LLW and VLLW generated from research facilities in Japan: A feasibility study for the near surface disposal of VLLW that includes uranium

    Sakai, Akihiro; Hasegawa, M.; Sakamoto, Y.; Nakatani, T.

    2016-01-01

    Conclusion and future work: • JAEA plans trench disposal of U-bearing waste with less than 100 Bq/g. • Two safety measures of trench disposal of U-bearing waste have been discussed taking into account increasing radioactivity over a long period of time. 1. First is to carry out dose assessment of site use scenario by using a conservatively stylized condition. 2. Second is to control the average concentration of U in the trench facilities based on the concept of the existing exposure situation. • We are continuously developing the method for safety measures of near surface disposal of VLLW including U-bearing waste.

  7. A strategy for the application of steam explosion codes to reactor analysis

    Moriyama, Kiyofumi; Nakamura, Hideo

    2006-01-01

    A technical view on the strategy for the application of steam explosion codes for plant scale analysis is described. It includes assumption of triggering at the time of peak premixed melt mass, tuning of the explosion model on typical alumina steam explosion data, consideration of void and solidification effects as primary mechanism to limit the premixed mass and explosion energetics, choice of simple heat partition models affecting evaporation. The view was developed through experiences in development, verification and application of a steam explosion simulation code, JASMINE, at Japan Atomic Energy Agency (JAEA), as well as participation in OECD SERENA Phase-1 program. (author)

  8. Reactivity Impact of Difference of Nuclear Data Library for PWR Fuel Assembly Calculation by Using AEGIS Code

    Ohoka, Yasunori; Tatsumi, Masahiro; Sugimura, Naoki; Tabuchi, Masato

    2011-01-01

    In 2010, the latest version of the Japanese Evaluated Nuclear Data Library (JENDL-4.0) has been released by JAEA. JENDL-4.0 is major update from JENDL- 3.3, and confirmed to give good accuracy by integral test for fission reactor systems such as fast neutron system and thermal neutron system. In this study, we evaluated the reactivity impact due to difference between ENDF/B-VII.0 and JENDL-4.0 for PWR fuel assembly burnup calculation using AEGIS code which has been developed by Nuclear Engineering, Ltd. in cooperation with Nuclear Fuel Industries, Ltd. and Nagoya University

  9. Development of new irradiation facility for BWR safety research

    Okada, Yuji; Magome, Hirokatsu; Iida, Kazuhiro; Hanawa, Hiroshi; Ohmi, Masao

    2013-01-01

    In JAEA (Japan Atomic Energy Agency), about the irradiation embrittlement of the reactor pressure vessel and the stress corrosion cracking of reactor core composition apparatus concerning the long-term use of the light water reactor (BWR), in order to check the influence of the temperature, pressure, and water quality, etc on BWR condition. The water environmental control facility which performs irradiation assisted stress corrosion-cracking (IASCC) evaluation under BWR irradiation environment was fabricated in JMTR (Japan Materials Testing Reactor). This report is described the outline of manufacture of the water environmental control facility for doing an irradiation test using the saturation temperature capsule after JMTR re-operation. (author)

  10. The review of ISTC/STCU 'On the environmental assessment for long term monitoring and remediation in and around Fukushima'

    Tsuruoka, S.

    2017-01-01

    An international project ISTC/STCU 'On the Environmental Assessment for Long Term Monitoring and Remediation in and Around Fukushima' was conducted for 4 years. The project was involved by ISTC/STCU, DOE in the United State, IAEA/JAEA, Ministry of Education, Culture, Sports, Science and technology Japan, and the other institutions. The objectives were to remedy for radioactive contamination in soil after the Fukushima One nuclear power plant accident in 2011, where the scientific experiences to recover farming and forest area in Chernobyl were applied. This review summarizes the exploration results. (author)

  11. Announced document collection of the 3rd information exchange meeting on radioactive waste disposal research network

    2008-03-01

    The 3rd meeting on 'Radioactive Waste Disposal Research Network' was held at the Ricotti techno community square of JAEA on September 3 and 4, 2007. The 'Radioactive Waste Disposal Research Network' was established in Interorganization Atomic Energy Research Program under academic collaborative agreement between Japan Atomic Energy Agency and the University of Tokyo. The objective is to bring both research infrastructures and human expertise in Japan to an adequate performance level, thereby contributing to the development of the fundamental research area in the field of radioactive waste disposal. This lecture material is a collection of presentations and discussions during the information exchange meeting. (author)

  12. Current situation and future of research reactor in Japan

    Metoki, Naoto

    2011-01-01

    A new style of neutron facilities coexisting high intensity pulse neutron source (J-PARC/MLF) and steady state neutron from research reactor (JRR-3) is proposed. The coexistence of the pulse and reactor source is the world trend which is inevitable for the next generation neutron science. A sophisticated management and comprehensive user program are important for Japanese neutron community, involving high performance instruments with pulse neutron and steady neutron source with widely spread users. JAEA is the most responsible for the future of neutron science, because of the commitment for both type of neutron source, J-PARC/MLF and JRR-3. (author)

  13. Proceedings of the international information exchange meeting on diffusion phenomena in bentonite and rock. Aiming at the safety assessment of the geological disposal

    Sato, Haruo; Hatanaka, Koichiro

    2009-12-01

    The international information exchange meeting on diffusion phenomena in bentonite and rock was held at Horonobe Underground Research Center on 18th July, 2006. This meeting was hosted by Japan Atomic Energy Agency (JAEA) and supported by Hokkaido University and Radioactive Waste Management Funding and Research Center (RWMC). Totally 18 scientists who are specialists of diffusion participated from Finland (VTT) and Japan (7 research organizations) in the meeting. 6 presentations were made on recent research activities and outputs on diffusion phenomena in bentonite and rock. The 6 papers are indexed individually. (J.P.N.)

  14. Present status of JENDL-4

    Shibata, Keiichi

    2009-01-01

    The fourth version of Japanese Evaluated Nuclear Data Library is being developed at the JAEA Nuclear Data Center in cooperation with the Japanese Nuclear Data Committee. As for actinides, we already released JENDL Actinoid File 2008, which contains the evaluated data for 79 nuclei. The high-energy cross sections of FP nuclei have been evaluated by using the CCONE and POD statistical model codes. The nuclear data for structural materials and light nuclei are being revised. The fission product yields were updated on the basis of ENDF/B-VII.0. Ternary fission was included in the yield data. (author)

  15. Developments of CHON-extractants and proliferation-resistant advanced reprocessing: ARTIST, in Japan

    Tachimori, S.; Yaita, T.; Suzuki, S.; Rais, J.

    2008-01-01

    Development of separation processes for the Partitioning and Transmutation (P and T) has been carried out in Japan for more than 30 years. From the Three Group Partitioning (3GP) and 4GP processes to the newest ARTIST processes, the main research results of Partitioning achieved at JAEA (former JAER1) are reviewed. In this report, the emphasis is put on the research works to develop the advanced reprocessing process: ARTIST, in which novel CHON-extractants were tailored to apply to separation of uranium (DO2EBA), transuranics (TODGA), cesium (DOC(4)C6), and Am-Cm from lanthanides (OcTolPTA). (author)

  16. Flow instability research on steam generator with straight double-walled heat transfer tube for FBR. Pressure drop under high pressure condition

    Liu, Wei; Tamai, Hidesada; Yoshida, Hiroyuki; Takase, Kazuyuki; Hayafune, Hiroki; Futagami, Satoshi; Kisohara, Naoyuki

    2008-01-01

    For the Steam Generator (SG) with straight double-walled heat transfer tube that used in sodium cooled Faster Breeder Reactor, flow instability is one of the most important items need researching. As the first step of the research, thermal hydraulics experiments were performed under high pressure condition in JAEA with using a straight tube. Pressure drop, heat transfer coefficients and void fraction data were derived. This paper evaluates the pressure drop data with TRAC-BF1 code. The Pffan's correlation for single phase flow and the Martinelli-Nelson's two-phase flow multiplier are found can be well predicted the present pressure drop data under high pressure condition. (author)

  17. Development of a high current 250 kV photocathode dc gun

    Nishimori, Nobuyuki; Nagai, Ryoji; Sawamura, Masaru; Hajima, Ryoichi

    2016-01-01

    We have developed a high current photocathode dc gun at JAEA for the next generation light sources such as an energy recovery linac and high-repetition rate X-ray free electron laser. The gun is equipped with a multialkali photocathode preparation system. Quantum efficiency of 0.37% at 532 nm was obtained for a Cs_3Sb photocathode. The gun was high voltage conditioned up to 230 kV with a cathode electrode. Beam generation test from the multialkali photocathode will be performed by the end of FY2015. (author)

  18. Annual report of R and D activities in Center for Computational Science and e-Systems from April 1, 2006 to March 31, 2007

    2008-03-01

    This report provides an overview of the research and development activities of the Center for Computational Science and e-Systems (CCSE), JAEA in fiscal year 2006 (April 1, 2006 - March 31, 2007). These research and development activities have been performed by the Simulation Technology Research and Development Office and the Computer Science Research and Development Office. The primary results of the research and development activities are the development of simulation techniques for a virtual earthquake testbed, an intelligent infrastructure for atomic energy research, computational biological disciplines to predict DNA repair function of protein, and material models for a neutron detection device, crack propagation, and gas bubble formation in nuclear fuel. (author)

  19. Determination of boron in ceramic reference materials by prompt gamma activation analysis using focused neutron guided beam of JRR-3M

    Miura, T.; Kuroiwa, T.; Chiba, K.; Matsue, H.

    2008-01-01

    Prompt gamma activation analysis using a focused thermal neutron guided beam at JAEA JRR-3M was applied to the determination of B in ceramic certified reference materials (BAM CRM S-003 Silicon Carbide Powder and NMIJ CRM 8004-a Silicon Nitride Powder). Cl and Si were used as internal standards to obtain linear calibration curves of B. The analytical result of B in BAM CRM S-003 was in good agreement with the certified value. The relative expanded measurement uncertainties (k = 2) were 4.8% for BAM CRM S-003 and 4.9% for NMIJ CRM 8004-a. (author)

  20. Present Status of the JENDL Project (May, 2013). WPEC Meeting, Paris, France, 23-24 May, 2013

    Fukahori, Tokio; Iwamoto, Osamu; Ishikawa, Makoto

    2013-01-01

    This paper briefly presents the present status of the Japanese JENDL Project: organization of Japanese Nuclear Data Committee (JNDC), a research committee for JAEA research activities; Nuclear Data Evaluation (JENDL-4.0 Updated Files and JENDL-4.0 Plus, benchmarking for fission reactor applications (criticality for thermal systems, adjusted library for fast systems), new evaluations, covariances, evaluation tools, fission products decay data file); other activities such as the 2012 Symposium on Nuclear Data at Kyoto University Research Reactor Institute, the initiation of conversation on Covariance Data with users, the celebration of the Golden Jubilee (since 1963) of JNDC

  1. Experience of Integrated Safeguards Approach for Large-scale Hot Cell Laboratory

    Miyaji, N.; Kawakami, Y.; Koizumi, A.; Otsuji, A.; Sasaki, K.

    2010-01-01

    The Japan Atomic Energy Agency (JAEA) has been operating a large-scale hot cell laboratory, the Fuels Monitoring Facility (FMF), located near the experimental fast reactor Joyo at the Oarai Research and Development Center (JNC-2 site). The FMF conducts post irradiation examinations (PIE) of fuel assemblies irradiated in Joyo. The assemblies are disassembled and non-destructive examinations, such as X-ray computed tomography tests, are carried out. Some of the fuel pins are cut into specimens and destructive examinations, such as ceramography and X-ray micro analyses, are performed. Following PIE, the tested material, in the form of a pin or segments, is shipped back to a Joyo spent fuel pond. In some cases, after reassembly of the examined irradiated fuel pins is completed, the fuel assemblies are shipped back to Joyo for further irradiation. For the IAEA to apply the integrated safeguards approach (ISA) to the FMF, a new verification system on material shipping and receiving process between Joyo and the FMF has been established by the IAEA under technical collaboration among the Japan Safeguard Office (JSGO) of MEXT, the Nuclear Material Control Center (NMCC) and the JAEA. The main concept of receipt/shipment verification under the ISA for JNC-2 site is as follows: under the IS, the FMF is treated as a Joyo-associated facility in terms of its safeguards system because it deals with the same spent fuels. Verification of the material shipping and receiving process between Joyo and the FMF can only be applied to the declared transport routes and transport casks. The verification of the nuclear material contained in the cask is performed with the method of gross defect at the time of short notice random interim inspections (RIIs) by measuring the surface neutron dose rate of the cask, filled with water to reduce radiation. The JAEA performed a series of preliminary tests with the IAEA, the JSGO and the NMCC, and confirmed from the standpoint of the operator that this

  2. Executive summary

    2010-01-01

    The special session on Fuel cycle strategies and transition scenarios comprised three invited papers and five oral presentations: INL (USA) was invited to present US activities on fuel cycle transition scenarios; JAEA (Japan) presented the current status of the Japanese nuclear fuel cycle; CEA and EDF (France) gave a presentation on the French fuel cycle strategy and transition scenarios; CEA and INL presented the latest outcomes from the NEA activity on fuel cycle transition scenarios and the European approach; JAEA reported on the results of global scenarios for fast reactor deployment; AECL (Canada) discussed actinide transmutation in Candu reactors, which may efficiently transmute TRU; Materials assessments, which could be used in advanced nuclear fuel cycles from a safeguard perspective, were presented by LANL (USA); The technical session about Impact on P and T on waste management and geological disposal comprised one invited paper and two oral presentations: JAEA presented on the concept of waste management and geological disposal incorporating P and T technology; CIEMAT (Spain) gave a summary of the RED-IMPACT study, which is the study of the impact of P and T on the HLW management programme of the EC; Chalmers University(Sweden) presented an estimation of maximum permissible step losses in P and T processing; The technical session about Progress in transmutation fuels and targets comprised one invited paper and seven oral presentations: The invited talk of the session was given by ITU (EC), on advanced fuel fabrication processes for transmutation; INL presented the development status of transuranic-bearing metal fuels in the USA; CEA summarised European projects on design, development and qualification of advanced fuels for an industrial ADS prototype; The Japanese study of the microstructural evolution and Am migration behaviour in Am-containing MOX fuels at the initial stage of irradiation was presented by JAEA discussed Japanese status on the

  3. Proceedings of the 2009 annual symposium on nuclear data. NDS2009

    Koura, Hiroyuki; Chiba, Satoshi

    2010-12-01

    The annual nuclear data symposium, organized by the Nuclear Data Division of Atomic Energy Society of Japan (AESJ) was held at Ricotti, Tokai, on Nov. 26 and 27, 2009 in cooperation with Advanced Science Research Center of JAEA and under financial support from North-Kanto Branch of AESJ. The symposium was devoted for discussions and presentations of research results in wide variety of fields related to nuclear data, including 3 tutorial talks. Talks as well as posters presented at the symposium aroused lively discussions among approximately 90 participants. This report contains 17 papers submitted from the talkers and poster presenters. (author)

  4. Current status of JRR-3. After the 3.11 earthquake

    Arai, Masaji; Murayama, Yoji; Wada, Shigeru

    2012-01-01

    JRR-3 at Tokai site of JAEA was in its regular maintenance period, when the Great East Japan Earthquake was taken place on 11th March 2011. The reactor building with their solid foundations and the equipment important to safety survived the earthquake without serious damage and no radioactive leakage has been occurred. Recovery work is planned to be completed by the end of this March. At the same time, check and test of the integrity of all components and seismic assessment to show resistance with the 3.11 earthquake have been carried out. JRR-3 will restart its operation after completing above mentioned procedures. (author)

  5. Guide for decontaminating swimming pool at schools

    Matsuhashi, Shimpei; Kurikami, Hiroshi; Yasuda, Ryo; Takano, Takao; Seko, Noriaki; Naganawa, Hirochika; Kuroki, Ryota; Saegusa, Jun

    2012-07-01

    Because of TEPCO Fukushima Dai-ichi Nuclear Power Plant accident due to the Great East Japan Earthquake, a huge amount of radioactive materials was widely dispersed and precipitated into the environment. Swimming pools in Fukushima prefectures were contaminated with the radioactives. We JAEA carried out several demonstration tests to decontaminate the radioactives and discharge the pool water safely. We concluded the results obtained from the tests as 'Guide for decontaminating Swimming Pool at School' and released it quickly. Following this, we also released the guide in English. This manuscript, as an experimental report of the swimming pool water decontamination, is consisted from the guide in Japanese and English prepared. (author)

  6. Conceptual study of 99Mo production in JRR-3

    Hirose, Akira; Komeda, Masao; Kinase, Masami; Sorita, Takami; Wada, Shigeru

    2010-06-01

    We investigated the production process of 99 Mo, which is parent nuclide of 99m Tc, in JRR-3. 99m Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Currently the supplying of 99 Mo is only dependent on imports from foreign countries, so JAEA is aiming at domestic production of a part of 99 Mo in cooperation with the industrial arena. This report presents the technical study for the production process of 99 Mo by using the neutron radiation method of (n, γ) reaction in JRR-3. (author)

  7. Harmonizing the prototypes concerning the fast reactors of 4. generation

    Anon.

    2008-01-01

    In january 2008, an agreement was signed between the Japan Atomic Energy Agency (JAEA), the American Department of Energy (DOE) and the French Atomic Energy Commission, in order to harmonize the projects of the 3 countries for the development of prototypes of sodium-cooled fast reactors. This cooperation concerns the following issues: -) the purpose of the prototypes, -) common set of safety rules, -) technical innovations for reducing construction, operating and maintenance costs, and -) information exchange about the level of power, the type of nuclear fuels and the time schedule of these prototypes. (A.C.)

  8. Benchmarking of the FENDL-3 Neutron Cross-section Data Starter Library for Fusion Applications

    Fischer, U., E-mail: ulrich.fischer@kit.edu [Association KIT-Euratom, Karlsruhe Institute of Technology, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Angelone, M. [Associazione ENEA-Euratom, ENEA Fusion Division, Via E. Fermi 27, I-00044 Frascati (Italy); Bohm, T. [University of Wisconsin-Madison, 1500 Engineering Dr, Madison, WI 53706 (United States); Kondo, K. [Association KIT-Euratom, Karlsruhe Institute of Technology, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Konno, C. [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 (Japan); Sawan, M. [University of Wisconsin-Madison, 1500 Engineering Dr, Madison, WI 53706 (United States); Villari, R. [Associazione ENEA-Euratom, ENEA Fusion Division, Via E. Fermi 27, I-00044 Frascati (Italy); Walker, B. [University of Wisconsin-Madison, 1500 Engineering Dr, Madison, WI 53706 (United States)

    2014-06-15

    This paper summarizes the benchmark analyses performed in a joint effort of ENEA (Italy), JAEA (Japan), KIT (Germany), and the University of Wisconsin (USA) on a computational ITER benchmark and a series of 14 MeV neutron benchmark experiments. The computational benchmark revealed a modest increase of the neutron flux levels in the deep penetration regions and a substantial increase of the gas production in steel components. The comparison to experimental results showed good agreement with no substantial differences between FENDL-3.0 and FENDL-2.1 for most of the responses. In general, FENDL-3 shows an improved performance for fusion neutronics applications.

  9. Status of SCRF cavity and ADS development in Japan

    Yamamoto, Akira

    2011-01-01

    SCRF cavity technology has progressed with high-energy particle accelerator programs in Japan. It was first applied for TRISTAN program at KEK, in early 1980s, and it is expected to be a key technology to realize the next energy-frontier lepton collider such as ILC, and/or intensity-frontier proton accelerators hopefully to be realized in Japan. The JPARC project as a joint program between JAEA and KEK is scoping to realize ADS program with the linac upgrade using a superconducting cavity system, as a future program. The talk will cover an overview of the SCRF cavity development and the ADS development in Japan. (author)

  10. Naval Reactors Prime Contractor Team (NRPCT) Experiences and Considerations With Irradiation Test Performance in an International Environment

    MH Lane

    2006-01-01

    This letter forwards a compilation of knowledge gained regarding international interactions and issues associated with Project Prometheus. The following topics are discussed herein: (1) Assessment of international fast reactor capability and availability; (2) Japanese fast reactor (JOYO) contracting strategy; (3) NRPCT/Program Office international contract follow; (4) Completion of the Japan Atomic Energy Agency (JAEA)/Pacific Northwest National Laboratory (PNNL) contract for manufacture of reactor test components; (5) US/Japanese Departmental interactions and required Treaties and Agreements; and (6) Non-technical details--interactions and considerations

  11. Irradiation technology (1). Development of new in-pile instrumentation at JMTR

    Shibata, Akira; Kimura, Nobuaki; Tanimoto, Masataka; Nakamura, Jinichi; Saito, Takashi; Tsuchiya, Kunihiko

    2012-01-01

    Development of instrumentation which can use under severe accident condition is important issue for the purpose to cope with severe accident at nuclear reactors. And also to improve the quality of irradiation tests data and to increase the reliability of safety management system of reactors, the development of new instrumentation is key issue. JAEA is developing several in-pile instrumentations to conduct irradiation tests at JMTR. This study includes the developments of three new instrumentations and describes the characteristics of the instrumentations. These are ECP sensor, new water level indicator and in-reactor observation system using Cherenkov light. (author)

  12. Diffusivity database (DDB) system for major rocks and buffer materials (Released on 2007/specification)

    Tochigi, Yoshikatsu; Shibata, Masahiro; Sato, Haruo; Kitamura, Akira

    2007-03-01

    The Diffusivity Database (DDB) System developed on early 2006 was upgraded to apply the data of effective diffusion coefficient of the nuclides in the rock matrix for the 'H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan', and the data in the buffer materials from literature survey was newly added. Some functions of data search and selection were reformed to improve the level of convenience. This DDB system (work on MS-Access TM ) is released to the public through Web server managed by JAEA. (author)

  13. Development of intense high-energy noble gas ion beams from in-terminal ion injector of tandem accelerator using an ECR ion source

    Matsuda, M., E-mail: matsuda.makoto@jaea.go.jp [Japan Atomic Energy Agency (JAEA), Tokai Research and Development Center, 2-4 Shirakata-shirane, Tokai, Naka, Ibaraki 319-1195 (Japan); Nakanoya, T.; Hanashima, S.; Takeuchi, S. [Japan Atomic Energy Agency (JAEA), Tokai Research and Development Center, 2-4 Shirakata-shirane, Tokai, Naka, Ibaraki 319-1195 (Japan)

    2011-10-21

    An ECRIS-based heavy ion injector was constructed in the high-voltage terminal of JAEA-Tokai Tandem Accelerator to develop new beam species of highly charged noble gas ions. This work was associated with a lot of development to operate the ion source on the 20UR Pelletron high voltage terminal in high pressure SF{sub 6} gas environment. Highly charged ions of N, O, Ne, Ar, Kr and Xe have been accelerated satisfactorily. Operating data integrated during many years long beam delivery service are summarized.

  14. Peak creation in the energy spectrum of laser-produced protons by phase rotation

    Noda, Akira; Nakamura, Shu; Iwashita, Yoshihisa; Shirai, Toshiyuki; Tongu, Hiromu; Ito, Hiroyuki; Souda, Hikaru; Yamazaki, Atsushi; Tanabe, Mikio; Daido, Hiroyuki; Mori, Michiaki; Kado, Masataka; Sagisaka, Akito; Ogura, Koichi; Nishiuchi, Mamiko; Orimo, Satoshi; Hayashi, Yukio; Yogo, Akifumi; Bulanov, Sergei; Esirkepov, Timur; Nagashima, Akira; Kimura, Toyoaki; Tajima, Toshiki; Fukumi, Atsushi; Li, Zhong

    2007-01-01

    In collaboration between JAEA, Kansai Photon Science Institute and Institute for Chemical Research, Kyoto University, proton generation from a thin foil target (Ti 3 or 5 μm in thickness) with use of 10 TW laser (JLITEX) has been performed. Proton production is optimized by real time proton energy measurement with use of TOF method. Phase rotation with use of an RF electric field phase-synchronized to the pulse laser enabled the creation of peaks with the spread of ∼7% in the energy spectrum of the produced protons, which resulted in the increase of the intensity ∼4 times at peak position. (author)

  15. Contributions to and expectations from the CRP - Argonne National Laboratory (USA)

    Cahalan, J.E.

    2007-01-01

    For us, the chief benefit of the CRP will be validation of multidimensional fluid dynamics capabilities for analysis of outlet plenum temperature distributions. As reactor designers seek new fuel handling features to reduce costs, upper internal structure configurations are becoming more compact, and higher fidelity analysis techniques are required to assess thermal stresses. Argonne currently has 1) a reactor systems analysis code with an experimentally-based model for plenum stratification, 2) the COMMIX code (parent of the JAEA AQUA code), and 3) commercial fluid dynamics analysis codes. It is anticipated that all or some combination of these capabilities will be employed to perform the CRP analysis

  16. Microstructure and elemental distribution of americium containing MOX fuel under the short term irradiation tests

    Tanaka, Kosuke; Hirosawa, Takashi; Obayashi, Hiroshi; Koyama, Shin Ichi; Yoshimochi, Hiroshi; Tanaka, Kenya

    2008-01-01

    In order to investigate the effect of americium addition to MOX fuels on the irradiation behavior, the 'Am-1' program is being conducted in JAEA. The Am-1 program consists of two short term irradiation tests of 10-minute and 24 hour irradiations and a steady-state irradiation test. The short-term irradiation tests were successfully completed and the post irradiation examinations (PIEs) are in progress. The PIEs for Am-containing MOX fuels focused on the microstructural evolution and redistribution behavior of Am at the initial stage of irradiation and the results to date are reported

  17. Application of Cherenkov light observation to reactor measurements (3). Evaluation of spent fuel elements of LWRs with Cherenkov light estimation system

    Yamamoto, Keiichi; Takeuchi, Tomoaki; Tsuchiya, Kunihiko; Hayashi, Takayasu; Kosuge, Fumiaki

    2016-11-01

    Development of the reactor measurement system has been carried out to obtain the real-time in-core nuclear and thermal information, where the quantitative measurement of brightness of Cherenkov light was investigated. The system would be applied as a monitoring system in severe accidents and for the advanced operation management technology in existing LWRs. This report summarized the modification of Cherenkov light estimation system described JAEA-Testing 2015-001 and the result of the burn-up evaluation by Cherenkov light image emitted from spent fuel elements of LWRs with the modified system. (author)

  18. Derivation of Inter-Atomic Force Constants of Cu2O from Diffuse Neutron Scattering Measurement

    T. Makhsun

    2013-04-01

    Full Text Available Neutron scattering intensity from Cu2O compound has been measured at 10 K and 295 K with High Resolution Powder Diffractometer at JRR-3 JAEA. The oscillatory diffuse scattering related to correlations among thermal displacements of atoms was observed at 295 K. The correlation parameters were determined from the observed diffuse scattering intensity at 10 and 295 K. The force constants between the neighboring atoms in Cu2O were estimated from the correlation parameters and compared to those of Ag2O

  19. Post irradiation examinations cooperation and worldwide utilization of facilities

    Karlsson, Mikael

    2009-01-01

    Status of post irradiation examinations in Studsvik's facilities, cooperation and worldwide utilization of facilities, was described. Studsvik cooperate with irradiation facilities, as Halden, CEA and JAEA, as well as other hot cell facilities (examples, PSI, ITU and NFD) universities (example, the Royal Institute of Technology in Sweden) in order to be able to provide everything asked for by the nuclear community. Worldwide cooperation for effective use of expensive and highly specialized facilities is important, and the necessity of cooperation will be more and more recognized in the future. (author)

  20. Environmental performance data in environmental report 2012

    Suzuki, Yurina; Tatebe, Kazuaki; Ohtake, Masaki; Shirato, Seiichi

    2013-03-01

    In September, 2012 Japan Atomic Energy Agency published the Environmental Report 2012 concerning the activities of FY 2011 under 'Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc, by Facilitating Access to Environmental Information, and Other Measures'. This report has been edited to show detailed environmental performance data in FY 2011 as the base of the Environmental Report 2012. This report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA. (author)

  1. Proceedings of information and opinion exchange conference on geoscientific study, 2007

    Nishio, Kazuhisa; Iyatomi, Yosuke; Ogata, Nobuhisa

    2008-05-01

    The Tono Geoscience Center (TGC) of Japan Atomic Energy Agency (JAEA) has been conducting a geoscientific studies in order to establish a scientific and technological basis for the geological disposal of HLW. Information and Opinion Exchange Conference on Geoscientific Study has been held by TGC annually. The conference provides technical information and an opportunity for peer review and exchange of opinions on the geoscientific studies conducted at TGC. Research specialists and engineers from Japanese universities, research organizations and private companies usually participate the conference. This document compiles research presentations, posters of the conference on October 19th, 2007 at Mizunami. (author)

  2. Proceedings of information and opinion exchange conference on geoscientific study, 2006

    Nishio, Kazuhisa; Iyatomi, Yosuke; Ogata, Nobuhisa

    2008-03-01

    The Tono Geoscience Center (TGC) of Japan Atomic Energy Agency (JAEA) has been conducting a geoscientific studies in order to establish a scientific and technological basis for the geological disposal of HLW. Information and Opinion Exchange Conference on Geoscientific Study has been held by TGC annually. The conference provides technical information and an opportunity for peer review and exchange of opinions on the geoscientific studies conducted at TGC. Research specialists and engineers from Japanese universities, research organizations and private companies usually participate the conference. This document collects research presentations, posters of the conference on October 19th to 20th, 2006 at Mizunami. (author)

  3. Proceedings of information and opinion exchange conference on geoscientific study, 2009

    Nishio, Kazuhisa; Iyatomi, Yosuke; Shimada, Akiomi

    2010-02-01

    The Tono Geoscience Center (TGC) of Japan Atomic Energy Agency (JAEA) has been conducting a geoscientific studies in order to establish a scientific and technological basis for the geological disposal of HLW. Information and Opinion Exchange Conference on Geoscientific Study has been held by TGC annually. The conference provides technical information and an opportunity for peer review and exchange of opinions on the geoscientific studies conducted at TGC. Research specialists and engineers from Japanese universities, research organizations and private companies usually participate the conference. This document compiles research presentations, posters of the conference on October 27th, 2009 at Mizunami. (author)

  4. Environmental performance data in environmental report 2009

    Sato, Yoshinori; Noritake, Kazumitsu; Kawasaki, Takanori; Suzuki, Yurina; Nemoto, Asako

    2010-02-01

    In July, 2009 Japan Atomic Energy Agency published the Environmental Report 2009 concerning the activities of FY 2008 under 'Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc, by Facilitating Access to Environmental Information, and Other Measures'. This report has been edited to show detailed environmental performance data in FY 2008 as the base of the Environmental Report 2009. This report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA. (author)

  5. Environmental performance data in environmental report 2013

    Suzuki, Yurina; Ohtake, Masaki; Shirato, Seiichi; Tatebe, Kazuaki

    2014-03-01

    In September, 2013 Japan Atomic Energy Agency published the Environmental Report 2013 concerning the activities of FY 2012 under 'Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc, by Facilitating Access to Environmental Information, and Other Measures'. This report has been edited to show detailed environmental performance data in FY 2012 as the base of the Environmental Report 2013. This report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA. (author)

  6. Guide for decontaminating swimming pool at schools

    Matsuhashi, Shimpei; Kurikami, Hiroshi; Yasuda, Ryo; Takano, Takao; Seko, Noriaki; Naganawa, Hirochika; Kuroki, Ryota; Saegusa, Jun

    2012-07-15

    Because of TEPCO Fukushima Dai-ichi Nuclear Power Plant accident due to the Great East Japan Earthquake, a huge amount of radioactive materials was widely dispersed and precipitated into the environment. Swimming pools in Fukushima prefectures were contaminated with the radioactives. We JAEA carried out several demonstration tests to decontaminate the radioactives and discharge the pool water safely. We concluded the results obtained from the tests as 'Guide for decontaminating Swimming Pool at School' and released it quickly. Following this, we also released the guide in English. This manuscript, as an experimental report of the swimming pool water decontamination, is consisted from the guide in Japanese and English prepared. (author)

  7. 岩石型酸化物燃料要素を用いたペブルベッド型モジュラー高温ガス冷却炉の設計研究

    Ho, Hai Quan; Ho, Hai Quan

    2016-01-01

    Pebble bed reactor (PBR) is claimed to be have excellent passive safety features among the reactors. Rock-like oxide (ROX) fuel was proposed at JAEA with high chemical stability under geological condition. It is of interest that using ROX as fuel in PBRs can improve safety features during normal operation and the final disposal of spent fuel. The purpose of this study was to show the design concept for a small modular pebble bed reactor with ROX fuel that could achieve a high safety feature o...

  8. Status of HTTR and Technology Developments for Near Term Deployment of Nuclear Process Heat Applications in Japan

    Yan, Xing L.

    2017-01-01

    JAEA's High Temperature Engineering Test Reactor: Main features: Thermal power 30 MWt; Fuel SiC TRISO UO2 coated particle fuel, pin in block; Design type Prismatic core; Coolant Helium; Temperature 950 °C (Max.); Pressure 4 MPa. Proven quality of HTTR coated particle fuel - 50-day 950°C operation test in HTTR (2009): • Proved fuel production quality in commercial-scale facility - Fabricated 2 core loads of fuel for HTTR (2 t of U used); - Failure fraction: 2 orders of magnitude < licensed limits • Demonstrated fuel integrity in HTTR operation and extended burnup test: an order of magnitude < licensed limit

  9. Inventory of safeguards software

    Suzuki, Mitsutoshi; Horino, Koichi

    2009-03-01

    The purpose of this survey activity will serve as a basis for determining what needs may exist in this arena for development of next-generation safeguards systems and approaches. 23 software tools are surveyed by JAEA and NMCC. Exchanging information regarding existing software tools for safeguards and discussing about a next R and D program of developing a general-purpose safeguards tool should be beneficial to a safeguards system design and indispensable to evaluate a safeguards system for future nuclear fuel facilities. (author)

  10. Naval Reactors Prime Contractor Team (NRPCT) Experiences and Considerations With Irradiation Test Performance in an International Environment

    MH Lane

    2006-02-15

    This letter forwards a compilation of knowledge gained regarding international interactions and issues associated with Project Prometheus. The following topics are discussed herein: (1) Assessment of international fast reactor capability and availability; (2) Japanese fast reactor (JOYO) contracting strategy; (3) NRPCT/Program Office international contract follow; (4) Completion of the Japan Atomic Energy Agency (JAEA)/Pacific Northwest National Laboratory (PNNL) contract for manufacture of reactor test components; (5) US/Japanese Departmental interactions and required Treaties and Agreements; and (6) Non-technical details--interactions and considerations.

  11. Study on an equivalent continuum model at the Mizunami Underground Research Laboratory

    Tanno, Takeo; Sato, Toshinori; Matsui, Hiroya; Sanada, Hiroyuki; Kumasaka, Hiroo; Tada, Hiroyuki

    2012-01-01

    The Japan Atomic Energy Agency (JAEA) is conducting the MIzunami Underground research laboratory (MIU) Project in order to develop comprehensive geological investigation and engineering techniques for deep underground applications (e.g. geological disposal of HLW). This modelling study has a two-fold objective, to contribute to the evaluation of the mechanical stability of shaft and research drifts, and to plan the future studies. A crack tensor model, a method of an equivalent continuum model, has been studied at the MIU. In this study, the relationship between the estimated crack tensor parameters and the rock mass classification was revealed. (author)

  12. Five Years Progress on Waste Management of Fukushima-Daiichi Nuclear Accident

    Nomura, Shigeo; Katoh, Kazuyuki; Okano, Kenta

    2016-01-01

    Conclusions: • A huge amount of off-site specified waste is planned to be managed by constructing and operating interim storage facilities. However, there still needs a lot of initiatives to recover the 1F nuclear accident. • On-site management of solid waste generated by the accident should be sustained as long-term key activities, such as safe storage, characterization, processing and disposal of various wastes. • Effective collaborations among NDF, TEPCO, IRID, JAEA, other domestic and international organizations and companies are strongly requested to tackle challenging projects on 1F decommissioning.

  13. Post irradiation examination technology exchange

    Sozawa, Shizuo; Ito, Masayasu; Taguchi, Taketoshi; Nakagawa, Tetsuya; Lee, Hyung-Kwon

    2012-01-01

    Under the KAERI and JAEA agreement, in a part of the program 18 (Post Irradiation Examination (PIE) and Evaluation Technique of Irradiated Materials), an eddy current test was proposed as a round robin test, and it has been being progressed in both organizations in order to enhance the post irradiation examination technology. Up to now, several data are obtained by both PIE facilities. In this paper, the round robin test program is shown, and also shown obtained data with discussion from applicability as a nondestructive test in the hot cell. (author)

  14. Annual report of Kansai Research Establishment 2004. April 1, 2004 - March 31, 2005

    Harami, Taikan; Mizuki, Jun'ichiro; Aoki, Katsutoshi; Baba, Yuji; Murakami, Yoichi; Kobayashi, Keisuke; Sakai, Toru; Nagashima, Akira; Yamakawa, Koichi; Nagashima, Keisuke; Daido, Hiroyuki; Koike, Masato; Yamagiwa, Mituru; Bulanov, Sergei V.; Minehara, Eisuke

    2006-01-01

    This report is the sixth issue of the annual report of Kansai Research Establishment, Japan Atomic Energy Research Institute. It covers status report of R and D and results of experiments conducted at the Advanced Photon Research Center and Synchrotron Radiation Research Center during the period from April 1, 2004 to March 31, 2005. The JAERI (Japan Atomic Energy Research Institute) have been unified with JNC (Japan Nuclear Cycle Development Institute) and became JAEA (Japan Atomic Energy Agency) on October 1st, 2005. (author)

  15. 99Mo-99mTc production development by (n, γ) reaction

    Izumo, Hironobu; Nishikata, Kaori; Kimura, Akihiro; Tanimoto, Masataka; Tsuchiya, Kunihiko; Ishihara, Masahiro; Kaminaga, Masanori

    2012-01-01

    The renewed JMTR will be started from the later half of JFY2012, and it is expected to various fields. Supply of 99 Mo in Japan depends only on imports from foreign countries. JAEA has a plan to produce 99 Mo, a parent nuclide of 99m Tc. JMTR will contribute to produce 99 Mo by (n, r) method as one of effective uses of the JMTR. In this paper, outline of the technical study items for production method of 99 Mo- 99m Tc in JMTR will be described. (author)

  16. Proceedings of the international symposium on materials testing reactors

    Ishihara, Masahiro; Kawamura, Hiroshi

    2009-01-01

    This report is the Proceedings of the International Symposium on Materials Testing Reactors hosted by Japan Atomic Energy Agency (JAEA). The symposium was held on July 16 to 17, 2008, at the Oarai Research and Development Center of JAEA. This symposium was also held for the 40th anniversary ceremony of Japan Materials Testing Reactor (JMTR) from achieving its first criticality. The objective of the symposium is to exchange the information on current status, future plan and so on among each testing reactors for the purpose of mutual understanding. There were 138 participants from Argentina, Belgium, France, Indonesia, Kazakhstan, Korea, the Russian Federation, Sweden, the United State, Vietnam and Japan. The symposium was divided into four technical sessions and three topical sessions. Technical sessions addressed the general topics of 'status and future plan of materials testing reactors', 'material development for research and testing reactors', irradiation technology (including PIE technology)' and 'utilization with materials testing reactors', and 21 presentations were made. Also the topical sessions addressed 'establishment of strategic partnership', 'management on re-operation work at reactor trouble' and 'basic technology for neutron irradiation tests in MTRs', and panel discussion was made. The 21 of the presented papers are indexed individually. (J.P.N.)

  17. Water experiments on thermal striping in reactor vessel of advanced sodium-cooled fast reactor. Influence of flow collector of backup CR guide tube

    Kobayashi, Jun; Ezure, Toshiki; Tanaka, Masaaki; Kamide, Hideki

    2016-01-01

    Design study of an advanced large-scale sodium-cooled fast reactor (SFR) has been conducted in JAEA. In the region between the bottom of the Upper Internal Structure (UIS) and the core outlet, the hot sodium from the fuel subassembly mixes with the cold sodium from the neighbor control rod (CR) channel. Therefore, temperature fluctuation due to mixing fluids at different temperatures may cause high cycle thermal fatigue at the bottom of the UIS. In the advanced design, installation of a flow guide structure named Flow-Collector (FC) to the backup control rod (BCR) guide tube is considered to enhance reliable operation of self-actuated shutdown system (SASS) and to ensure reactor shutdown operation. Previously, water experiments without the FC model had been examined in JAEA to investigate effective countermeasures to the significant temperature fluctuation generation at the bottom of the UIS. Since the FC may affect the thermal mixing behavior at the bottom of the UIS, influence of the FC on characteristics of the temperature fluctuation around the BCR channels was investigated using a water experimental facility with structure model of the FC. Through the experiment, small influence of the FC on the temperature fluctuation distribution at the bottom of the UIS was indicated. (author)

  18. Monte Carlo Codes Invited Session

    Trama, J.C.; Malvagi, F.; Brown, F.

    2013-01-01

    This document lists 22 Monte Carlo codes used in radiation transport applications throughout the world. For each code the names of the organization and country and/or place are given. We have the following computer codes. 1) ARCHER, USA, RPI; 2) COG11, USA, LLNL; 3) DIANE, France, CEA/DAM Bruyeres; 4) FLUKA, Italy and CERN, INFN and CERN; 5) GEANT4, International GEANT4 collaboration; 6) KENO and MONACO (SCALE), USA, ORNL; 7) MC21, USA, KAPL and Bettis; 8) MCATK, USA, LANL; 9) MCCARD, South Korea, Seoul National University; 10) MCNP6, USA, LANL; 11) MCU, Russia, Kurchatov Institute; 12) MONK and MCBEND, United Kingdom, AMEC; 13) MORET5, France, IRSN Fontenay-aux-Roses; 14) MVP2, Japan, JAEA; 15) OPENMC, USA, MIT; 16) PENELOPE, Spain, Barcelona University; 17) PHITS, Japan, JAEA; 18) PRIZMA, Russia, VNIITF; 19) RMC, China, Tsinghua University; 20) SERPENT, Finland, VTT; 21) SUPERMONTECARLO, China, CAS INEST FDS Team Hefei; and 22) TRIPOLI-4, France, CEA Saclay

  19. Process of establishing JHP project

    Ishihara, Masayasu

    2013-01-01

    Institute for Nuclear Study, University of Tokyo was a Japanese central research institute as regards to nuclear physics, high energy physics, and cosmic ray physics. After the foundations of National Laboratory for High Energy Physics, KEK, and Institute for Cosmic Ray Research, University of Tokyo, in early 1970s, the nuclear physics community worked out so-called NUMATRON project, which involved building a large heavy-ion synchrotron. It was, however, not successful in competition with TRISTAN project which was proposed by KEK to build a 30 GeV electron-positron collider. Alternative project of the nuclear physics community was so-called JHP (Japanese Hadron Project), to build 1 GeV proton linac in KEK site in collaboration with KEK, which included that the Institute for Nuclear Study should be consolidated to KEK leaving from The University of Tokyo. The reorganized KEK proposed in collaboration with JAEA, Japan Atomic Energy Agency, to build a big proton accelerator facility in JAEA site. This plan was realized as J-PARC, Japanese Proton Accelerator Research Complex, operating 50 GeV proton synchrotron. (author)

  20. Design study on evaluation for power conversion system concepts in high temperature gas cooled reactor with gas turbine

    Minatsuki, Isao; Mizokami, Yorikata

    2007-01-01

    The design studies on High Temperature Gas Cooled Reactor with Gas Turbine (HTGR-GT) have been performed, which were mainly promoted by Japan Atomic Energy Agency (JAEA) and supported by fabricators in Japan. HTGR-GT plant feature is almost determined by selection of power conversion system concepts. Therefore, plant design philosophy is observed characteristically in selection of them. This paper describes the evaluation and analysis of the essential concepts of the HTGR-GT power conversion system through the investigations based on our experiences and engineering knowledge as a fabricator. As a result, the following concepts were evaluated that have advantages against other competitive one, such as the horizontal turbo machine rotor, the turbo machine in an individual vessel, the turbo machine with single shaft, the generator inside the power conversion vessel, and the power conversion system cycle with an intercooler. The results of the study can contribute as reference data when the concepts will be selected. Furthermore, we addressed reasonableness about the concept selection of the Gas Turbine High Temperature Reactor GTHTR300 power conversion system, which has been promoted by JAEA. As a conclusion, we recognized the GTHTR300 would be one of the most promising concepts for commercialization in near future. (author)

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

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

    2014-03-01

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

  2. High power millimeter wave experiment of torus diamond window prototype for ITER EC H and CD system

    Takahashi, K.; Kajiwara, K.; Oda, Y.; Sakamoto, K.; Omori, T.; Henderson, M.

    2013-01-01

    Highlights: ► The diamond window prototype was fabricated based on the reliable and manufacturable design. ► Transmission of 740 kW-100 s on the window prototype was successfully demonstrated. ► tan δ = 7.8 × 10 −6 , which was the lowest value that we had ever obtained at JAEA, was evaluated. ► The window structure promising the high power transmission more than 1 MW was obtained. -- Abstract: The design of the torus diamond window for the ITER electron cyclotron heating and current drive (EC H and CD) system has advanced considering a reliable and manufacturable structure. The diamond window prototype was fabricated based on the design and the high power experiment was carried out to verify the millimeter wave transmission capability. Transmission of 740 kW-100 s was demonstrated and no significant temperature increase of the window structure and no damage on the diamond disk were obtained. The temperature saturation of the cooling water for the window was observed and loss tangent of 7.8 × 10 −6 , which was the lowest value that we had ever obtained at JAEA, was evaluated. This result indicates that the diamond window design is feasible and promising the high power more than 1 MW transmission

  3. Research on advanced technology of performance assessment for geological disposal of high-level radioactive waste (Joint research)

    2006-12-01

    JAEA and RWMC have carried out a joint research program on advanced technologies that could be used to support performance assessments of geological disposal concepts for high-level radioactive waste. The following 5 items were considered in the program: 1) planning of a basic strategy for the development of analysis technologies on nuclide migration over various spatial and temporal scales; 2) development of analysis technologies for vitrified waste scale; 3) development of analysis technologies for repository scale; 4) development of integration technologies for geochemical information; and 5) development of technologies to promote the logical understanding of repository performance and safety. The above items were discussed in the context of technological experiences gained by JAEA and RWMC in previous repository-related studies. According to the results of these discussions, development strategies for each of the technology areas identified above were efficiently formulated by appropriate task allocations. Specific technical subjects requiring further investigation were also identified using this approach, and potential feed-backs from the results of these investigations into the overall research plan and strategy were considered. These specific research and development subjects in the overall strategy defined by this project should be implemented in the future. (author)

  4. Assessment report of research and development on 'geological disposal of high-level radioactive waste' (Interim report)

    Notoya, Shin; Shimizu, Kazuhiko; Ota, Kunio; Sasao, Eiji

    2010-08-01

    Japan Atomic Energy Agency (JAEA) consulted an assessment committee, 'Evaluation Committee of Research and Development (R and D) Activities for Geological Disposal of High-Level Radioactive Waste', for interim assessment of R and D on high-level radioactive waste disposal in accordance with 'General Guideline for Evaluation of Government R and D Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by Japan. In response to JAEA's request, the Committee assessed mainly the progress of the R and D project according to guidelines, which addressed the rationale behind the R and D project, the relevance of the project outcome and the efficiency of the project implementation during the period of the first midterm plan. As a result, the Committee concluded that the progress of the R and D project is satisfactory. In addition, the Committee provided a couple of issues and suggestions to be addressed in the implementation of the project during the period of the second midterm. A CD-ROM is attached as an appendix. (J.P.N.)

  5. Proceedings of the 4th international symposium on material testing reactors

    Ishihara, Masahiro; Suzuki, Masahide [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)

    2012-03-15

    This report is the Proceedings of the fourth International Symposium on Material Testing Reactors hosted by Japan Atomic Energy Agency (JAEA). The first symposium was held on 2008, at the Oarai Research and Development Center of JAEA, the second, 2009, Idaho National Laboratory (INL) of United States and the third 2010, Nuclear Research Institute (NRI) in Czech Republic to exchange information for deep mutual understanding of material testing reactors. The fourth symposium was originally scheduled to be held INVAP in Argentina. However, the aftermath of volcanic explosion at Chili forced the symposium to change place. Total 111 participants attended from Argentina, Belgium, France, Germany, Indonesia, Malasia, Korea, South Africa, Switzerland, the United State and Japan. This symposium addressed the general topics of 'status and future plan of material testing reactors', 'advancement of irradiation technology', 'expansion of industry use(RI)', 'facility, upgrade, aging management', 'new generation MTR', 'advancement of PIE technology', 'development of advanced driver fuel', and 'nuclear human resource development(HRD) for next generation', and 39 presentations were made. Furthermore, three topics, 'Necessity of cooperation for Mo-99 production by (n,gamma) reaction', 'Necessity of standardization of irradiation technology' and 'Conceptual design of next generation materials testing reactor by collaboration', were selected and discussed. (author)

  6. Elemental Technologies for Lead-Bismuth Spallation Target System in J-PARC

    Obayashi, H.; Yamaguchi, K.; Saito, S.; Sugawara, T.; Takei, H.; Sasa, T.

    2015-01-01

    Japan Atomic Energy Agency (JAEA) has been researching and developing an Accelerator-Driven System (ADS) as a dedicated system for the transmutation of long-lived radioactive nuclides. The ADS proposed by JAEA uses the lead-bismuth eutectic (LBE) alloy as a spallation target material and a coolant. In the various R and D for ADS, construction of the Transmutation Experimental Facility (TEF) is planned under the framework of the J-PARC project as a preceding step before the construction of demonstrative ADS. In this R and D, TEF is considered for the experimental investigation of the feasibility of the beam window, the structural materials, and to investigate the operation properties of the target system by using 400 MeV-250 kW proton beam. This target system is consisted of various elements and must be able to operate without troubles during an operation period of TEF facility. Furthermore, in the maintenance period after the operation, because the inside of a hot cell storing a target is exposed to strong radiations, all elements must be designed as remote control devices. In this study, the present conditions of the design and the result of performance test of each important elements were confirmed in the realisation of the LBE target system, such as the monitoring system of flow rate by using the ultrasonic method, the heater system with the metallic heat insulator joined to a flow channel of LBE, and the operability of remote handing. (authors)

  7. Development Of New Chrysanthemum Mutants For Malaysian Floriculture Industry

    Zaiton Ahmad; Affrida Abu Hassan; Shakinah Salleh; Nurul Hidayah Mahmud; Shuhaimi Shamsudin; Mohamed Najli Mohamed Yasin

    2014-01-01

    This five-year project was in collaboration with Japan Atomic Energy Agency (JAEA) under the Bilateral Cooperative Research Program and was partly funded by Ministry of Agriculture and Agro-Based Industry (MOA) under Agriculture R&D Fund. The main objective was to produce new chrysanthemum varieties with good horticultural traits especially for cut flower production. In this project, tissue culture samples of chrysanthemum (red and pink varieties) were sent to JAEA for ion beam irradiations. Plant regeneration and multiplication were carried out at Nuclear Malaysia whilst field screenings for morphological characteristics were done at MARDI Cameron Highlands. Through this project, a number of stable chrysanthemum mutants with various new features have been generated and of these, 8 mutants were selected based on their uniqueness and/or suitability for cut flower production. In preparation for future commercialization process, five of these mutants have been filed for plant variety protection with Department of Agriculture Malaysia and a similar process in Japan is also under consideration. In addition, molecular marker work to fingerprint these mutants has also been initiated and future research may also include development of markers for selected horticultural traits and isolation of unique mutant genes. (author)

  8. Critical power characteristics in 37-rod tight lattice bundles under transient conditions

    Liu, Wei; Kureta, Masatoshi; Tamai, Hidesada; Ohnuki, Akira; Akimoto, Hajime

    2007-01-01

    Critical power characteristics in the postulated abnormal transient processes that may be possibly met in the operation of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) were investigated for the design of the FLWR core. Transient Boiling Transition (BT) tests were carried out using two sets of 37-rod tight lattice rod bundles (rod diameter: 13 mm; rod clearance: 1.3 mm or 1.0 mm) at Japan Atomic Energy Agency (JAEA) under the conditions covering the FLWR operating condition (P ex =7.2 MPa, T in =556 K) for mass velocity G=400-800 kg/(m 2 s). For the postulated power increase and flow decrease transients, no obvious change of the critical power against the steady one was observed. The traditional quasi-steady characteristic was confirmed to be working for the postulated power increase and flow decrease transients. The experiments were analyzed with TRAC-BF1 code, where the JAEA newest critical power correlation for the tight lattice rod bundles was implemented for the BT judgment. The TRAC-BF1 code showed good prediction for the occurrence or the non occurrence of the BT and for the exact BT starting time. The tranditional quasi-steady state prediction of the BT in transient process was confirmed to be applicable for the postulated abnormal transient processes in the tight lattice rod bundles. (author)

  9. Status of the 1 MeV Accelerator Design for ITER NBI

    Kuriyama, M.; Boilson, D.; Hemsworth, R.; Svensson, L.; Graceffa, J.; Schunke, B.; Decamps, H.; Tanaka, M.; Bonicelli, T.; Masiello, A.; Bigi, M.; Chitarin, G.; Luchetta, A.; Marcuzzi, D.; Pasqualotto, R.; Pomaro, N.; Serianni, G.; Sonato, P.; Toigo, V.; Zaccaria, P.; Kraus, W.; Franzen, P.; Heinemann, B.; Inoue, T.; Watanabe, K.; Kashiwagi, M.; Taniguchi, M.; Tobari, H.; De Esch, H.

    2011-09-01

    The beam source of neutral beam heating/current drive system for ITER is needed to accelerate the negative ion beam of 40A with D- at 1 MeV for 3600 sec. In order to realize the beam source, design and R&D works are being developed in many institutions under the coordination of ITER organization. The development of the key issues of the ion source including source plasma uniformity, suppression of co-extracted electron in D beam operation and also after the long beam duration time of over a few 100 sec, is progressed mainly in IPP with the facilities of BATMAN, MANITU and RADI. In the near future, ELISE, that will be tested the half size of the ITER ion source, will start the operation in 2011, and then SPIDER, which demonstrates negative ion production and extraction with the same size and same structure as the ITER ion source, will start the operation in 2014 as part of the NBTF. The development of the accelerator is progressed mainly in JAEA with the MeV test facility, and also the computer simulation of beam optics also developed in JAEA, CEA and RFX. The full ITER heating and current drive beam performance will be demonstrated in MITICA, which will start operation in 2016 as part of the NBTF.

  10. Development of simplified decommissioning cost estimation code for nuclear facilities

    Tachibana, Mitsuo; Shiraishi, Kunio; Ishigami, Tsutomu

    2010-01-01

    The simplified decommissioning cost estimation code for nuclear facilities (DECOST code) was developed in consideration of features and structures of nuclear facilities and similarity of dismantling methods. The DECOST code could calculate 8 evaluation items of decommissioning cost. Actual dismantling in the Japan Atomic Energy Agency (JAEA) was evaluated; unit conversion factors used to calculate the manpower of dismantling activities were evaluated. Consequently, unit conversion factors of general components could be classified into three kinds. Weights of components and structures of the facility were necessary for calculation of manpower. Methods for evaluating weights of components and structures of the facility were studied. Consequently, the weight of components in the facility was proportional to the weight of structures of the facility. The weight of structures of the facility was proportional to the total area of floors in the facility. Decommissioning costs of 7 nuclear facilities in the JAEA were calculated by using the DECOST code. To verify the calculated results, the calculated manpower was compared with the manpower gained from actual dismantling. Consequently, the calculated manpower and actual manpower were almost equal. The outline of the DECOST code, evaluation results of unit conversion factors, the evaluation method of the weights of components and structures of the facility are described in this report. (author)

  11. Assessment report on research and development activities. Activity: 'Advanced science research' (Interim report)

    2012-11-01

    Japan Atomic Energy Agency (hereinafter referred to as “JAEA”) consulted an assessment committee, “Evaluation Committee of Research Activities for Advanced Science Research” (hereinafter referred to as “Committee”) for interim assessment of “Advanced Science Research,” in accordance with “General Guideline for the Evaluation of Government Research and Development (R and D) Activities” by Cabinet Office, Government of Japan, “Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology” and “Regulation on Conduct for Evaluation of R and D Activities” by JAEA. In response to the JAEA's request, the Committee assessed the research programs and activities of the Advanced Science Research Center (hereinafter referred to as “ASRC”) for the period of two years from April 2010. The Committee evaluated the management and the research programs of the ASRC based on the explanatory documents prepared by the ASRC and the oral presentations with questions-and-answers by the Director and the research group leaders. This report summarizes the result of the assessment by the Committee with the Committee report attached from page 7. (author)

  12. In situ test plan for concrete materials using low alkaline cement at Horonobe URL

    Kobayashi, Yasushi; Yamada, Tsutomu; Nakayama, Masashi; Matsui, Hiroya; Matsuda, Takeshi; Konishi, Kazuhiro; Iriya, Keishiro; Noda, Masaru

    2007-03-01

    HLW (high-level radioactive waste) repository is to be constructed at depths of over three hundred meters below the surface. Shotcrete and lining will be used for safety under construction and operational period. Concrete is a kind of composite material which is constituted by aggregate, cement and additives. Low alkaline cement has been developed from the viewpoint of long term stability of the barrier systems which would be influenced by high alkaline arising from cement material. HFSC (Highly Fly-ash contained Silica-fume Cement) is one of a low alkaline cement, which contains silica fume and coal ash. It has been developed in Japan Atomic Energy Agency (JAEA). JAEA are now implementing the construction of the under ground research laboratory (URL) at Horonobe for the purpose of research in deep geological science and repository engineering technology. This report shows the in situ test plan for shotcrete using HFSC at Horonobe URL with identifying requirements for cement materials to be used in HLW repository, and also reviews major literatures of low alkaline cement. This in situ test plan is aiming to assess the performance of HFSC shotcrete in terms of mechanics, workability, durability, and so on. (author)

  13. Crack formation in cementitious materials used for an engineering barrier system and their impact on hydraulic conductivity from the viewpoint of performance assessment of a TRU waste disposal system

    Hirano, Fumio; Mihara, Morihiro; Honda, Akira; Otani, Yoshiteru; Kyokawa, Hiroyuki; Shimizu, Hiroyuki

    2016-01-01

    The mechanical analysis code MACBECE2014 has been developed at the Japan Atomic Energy Agency (JAEA) to make realistic simulations of the physical integrity of the near field for performance assessment of the geological disposal of TRU waste in Japan. The MACBECE2014 code can be used to evaluate long-term changes in the mechanical behavior of the near field and any subsequent changes in the permeability of engineering barrier components, including crack formation in cementitious materials caused by expansion due to metal corrosion. Cracks in cementitious materials are likely to channel the flow of groundwater and so the represent preferred flow paths of any released radionuclides. Mechanical analysis was conducted using the MACBECE2014 code to investigate the concept of the TRU waste disposal system described in JAEA's Second Progress TRU Report. Simulated results of a disposal system with a bentonite buffer demonstrated that the low permeability of the engineering barrier system could be maintained for long time periods because the physical integrity of the bentonite buffer remained intact even if cracks in the cementitious components had formed locally. Simulated results of the disposal system with a concrete backfill instead of a bentonite buffer showed that crack formation leads to a significant increase in the permeability of the engineering barrier system. (author)

  14. A Small Modular Reactor Design for Multiple Energy Applications: HTR50S

    Yan, X.; Tachibana, Y.; Ohashi, H.; Sato, H.; Tazawa, Y.; Kunitomi, K. [Japan Atomic Energy Agency, Ibaraki (Japan)

    2013-06-15

    HTR50S is a small modular reactor system based on HTGR. It is designed for a triad of applications to be implemented in successive stages. In the first stage, a base plant for heat and power is constructed of the fuel proven in JAEA's 950 .deg. C, 30MWt test reactor HTTR and a conventional steam turbine to minimize development risk. While the outlet temperature is lowered to 750 .deg. C for the steam turbine, thermal power is raised to 50MWt by enabling 40% greater power density in 20% taller core than the HTTR. However the fuel temperature limit and reactor pressure vessel diameter are kept. In second stage, a new fuel that is currently under development at JAEA will allow the core outlet temperature to be raised to 900 .deg. C for the purpose of demonstrating more efficient gas turbine power generation and high temperature heat supply. The third stage adds a demonstration of nuclear-heated hydrogen production by a thermochemical process. A licensing approach to coupling high temperature industrial process to nuclear reactor will be developed. The low initial risk and the high longer-term potential for performance expansion attract development of the HTR50S as a multipurpose industrial or distributed energy source.

  15. Status of the 1 MeV Accelerator Design for ITER NBI

    Kuriyama, M.; Boilson, D.; Hemsworth, R.; Svensson, L.; Graceffa, J.; Schunke, B.; Decamps, H.; Tanaka, M.; Bonicelli, T.; Masiello, A.; Bigi, M.; Chitarin, G.; Luchetta, A.; Marcuzzi, D.; Pasqualotto, R.; Pomaro, N.; Serianni, G.; Sonato, P.; Toigo, V.; Zaccaria, P.

    2011-01-01

    The beam source of neutral beam heating/current drive system for ITER is needed to accelerate the negative ion beam of 40A with D - at 1 MeV for 3600 sec. In order to realize the beam source, design and R and D works are being developed in many institutions under the coordination of ITER organization. The development of the key issues of the ion source including source plasma uniformity, suppression of co-extracted electron in D beam operation and also after the long beam duration time of over a few 100 sec, is progressed mainly in IPP with the facilities of BATMAN, MANITU and RADI. In the near future, ELISE, that will be tested the half size of the ITER ion source, will start the operation in 2011, and then SPIDER, which demonstrates negative ion production and extraction with the same size and same structure as the ITER ion source, will start the operation in 2014 as part of the NBTF. The development of the accelerator is progressed mainly in JAEA with the MeV test facility, and also the computer simulation of beam optics also developed in JAEA, CEA and RFX. The full ITER heating and current drive beam performance will be demonstrated in MITICA, which will start operation in 2016 as part of the NBTF.

  16. Risk communication with Fukushima residents affected by the Fukushima Daiichi accident at whole-body counting

    Gunji, I.; Furuno, A.; Yonezawa, R.; Sugiyama, K. [Risk Communication Study Office, Japan Atomic Energy Agency 4-33 Muramatsu, Tokai-mura, Ibaraki, 319-1194 (Japan)

    2013-07-01

    After the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi nuclear power plant accident, the Tokai Research and Development Center of the Japan Atomic Energy Agency (JAEA) have had direct dialogue as risk communication with Fukushima residents who underwent whole-body counting examination (WBC). The purpose of the risk communication was to exchange information and opinions about radiation in order to mitigate Fukushima residents' anxiety and stress. Two kinds of opinion surveys were performed: one survey evaluated residents' views of the nuclear accident itself and the second survey evaluated the management of WBC examination as well as the quality of JAEA's communication skills on risks. It appears that most Fukushima residents seem to have reduced their anxiety level after the direct dialogue. The results of the surveys show that Fukushima residents have the deepest anxiety and concern about their long-term health issues and that they harbor anger toward the government and TEPCO. On the other hand, many WBC patients and patients' relatives have expressed gratitude for help in reducing their feelings of anxiety.

  17. Proceedings of the 4th international symposium on material testing reactors

    Ishihara, Masahiro; Suzuki, Masahide

    2012-03-01

    This report is the Proceedings of the fourth International Symposium on Material Testing Reactors hosted by Japan Atomic Energy Agency (JAEA). The first symposium was held on 2008, at the Oarai Research and Development Center of JAEA, the second, 2009, Idaho National Laboratory (INL) of United States and the third 2010, Nuclear Research Institute (NRI) in Czech Republic to exchange information for deep mutual understanding of material testing reactors. The fourth symposium was originally scheduled to be held INVAP in Argentina. However, the aftermath of volcanic explosion at Chili forced the symposium to change place. Total 111 participants attended from Argentina, Belgium, France, Germany, Indonesia, Malasia, Korea, South Africa, Switzerland, the United State and Japan. This symposium addressed the general topics of 'status and future plan of material testing reactors', 'advancement of irradiation technology', 'expansion of industry use(RI)', 'facility, upgrade, aging management', 'new generation MTR', 'advancement of PIE technology', 'development of advanced driver fuel', and 'nuclear human resource development(HRD) for next generation', and 39 presentations were made. Furthermore, three topics, 'Necessity of cooperation for Mo-99 production by (n,gamma) reaction', 'Necessity of standardization of irradiation technology' and 'Conceptual design of next generation materials testing reactor by collaboration', were selected and discussed. (author)

  18. User's manual and analysis methodology of probabilistic fracture mechanics analysis code PASCAL Ver.2 for reactor pressure vessel (Contract research)

    Osakabe, Kazuya; Onizawa, Kunio; Shibata, Katsuyuki; Kato, Daisuke

    2006-09-01

    As a part of the aging structural integrity research for LWR components, the probabilistic fracture mechanics (PFM) analysis code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed in JAEA. This code evaluates the conditional probabilities of crack initiation and fracture of a reactor pressure vessel (RPV) under transient conditions such as pressurized thermal shock (PTS). The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the recent development in the fracture mechanics and computer performance. PASCAL Ver.1 has functions of optimized sampling in the stratified Monte Carlo simulation, elastic-plastic fracture criterion of the R6 method, crack growth analysis models for a semi-elliptical crack, recovery of fracture toughness due to thermal annealing and so on. Since then, under the contract between the Ministry of Economy, Trading and Industry of Japan and JAEA, we have continued to develop and introduce new functions into PASCAL Ver.2 such as the evaluation method for an embedded crack, K I database for a semi-elliptical crack considering stress discontinuity at the base/cladding interface, PTS transient database, and others. A generalized analysis method is proposed on the basis of the development of PASCAL Ver.2 and results of sensitivity analyses. Graphical user interface (GUI) including a generalized method as default values has been also developed for PASCAL Ver.2. This report provides the user's manual and theoretical background of PASCAL Ver.2. (author)

  19. Materials for the information security education

    Yashiro, Shigeo; Aoki, Kazuhisa; Sato, Tomohiko; Tanji, Kazuhiro

    2014-01-01

    With the rapid progress of the utilization of Information Technology (IT), IT infrastructure (network environment and information system) became crucial as a lifeline for promoting business. At the same time, changes in the circumstances surrounding the IT infrastructure globalize the threat of cyber attacks and increase the risk of the information security such as unlawful access to an information system, viral infection, an alteration of a website, disclosure of subtlety information, destruction of an information system and so on. Information security measure is an important issue in Japan Atomic Energy Agency (JAEA). In order to protect the information property of JAEA from the threat, Center for Computational Science and e-Systems (CCSE) has been taking triadic measures for information security: (1) to lay down a set of information security rules, (2) to introduce security equipments to backbone network and (3) to provide information security education. This report is a summary of the contents of the information security education by e-learning. (author)

  20. Horonobe Underground Research Laboratory project. Investigation report for the 2007 fiscal year

    Nakayama, Masashi; Sanada, Hiroyuki; Sugita, Yutaka

    2008-09-01

    The Horonobe Underground Research Laboratory Project is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction Phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the results of the investigations for the 2007 fiscal year (2007/2008), the 3rd year of the Phase 2 investigations. The investigations, which are composed of 'Geoscientific research' and 'R and D on the geological disposal of high-level radioactive waste (HLW)', were carried out according to 'Horonobe Underground Research Laboratory Project Investigation Program for the 2007 Fiscal Year'. The results of these investigations, along with the results which were obtained in other departments of Japan Atomic Energy Agency (JAEA), are properly offered to the implementations and the safety regulations. JAEA proceeded with the project in collaboration with experts from domestic and overseas research organisation. (author)

  1. Network computing infrastructure to share tools and data in global nuclear energy partnership

    Kim, Guehee; Suzuki, Yoshio; Teshima, Naoya

    2010-01-01

    CCSE/JAEA (Center for Computational Science and e-Systems/Japan Atomic Energy Agency) integrated a prototype system of a network computing infrastructure for sharing tools and data to support the U.S. and Japan collaboration in GNEP (Global Nuclear Energy Partnership). We focused on three technical issues to apply our information process infrastructure, which are accessibility, security, and usability. In designing the prototype system, we integrated and improved both network and Web technologies. For the accessibility issue, we adopted SSL-VPN (Security Socket Layer - Virtual Private Network) technology for the access beyond firewalls. For the security issue, we developed an authentication gateway based on the PKI (Public Key Infrastructure) authentication mechanism to strengthen the security. Also, we set fine access control policy to shared tools and data and used shared key based encryption method to protect tools and data against leakage to third parties. For the usability issue, we chose Web browsers as user interface and developed Web application to provide functions to support sharing tools and data. By using WebDAV (Web-based Distributed Authoring and Versioning) function, users can manipulate shared tools and data through the Windows-like folder environment. We implemented the prototype system in Grid infrastructure for atomic energy research: AEGIS (Atomic Energy Grid Infrastructure) developed by CCSE/JAEA. The prototype system was applied for the trial use in the first period of GNEP. (author)

  2. Development of a vacuum leak test method for large-scale superconducting magnet test facilities

    Kawano, Katsumi; Hamada, Kazuya; Okuno, Kiyoshi; Kato, Takashi

    2006-01-01

    Japan Atomic Energy Agency (JAEA) has developed leak detection technology for liquid helium temperature experiments in large-scale superconducting magnet test facilities. In JAEA, a cryosorption pump that uses an absorbent cooled by liquid nitrogen with a conventional helium leak detector, is used to detect helium gas that is leaking from pressurized welded joints of pipes and valves in a vacuum chamber. The cryosorption pump plays the role of decreasing aerial components, such as water, nitrogen and oxygen, to increase the sensitivity of helium leak detection. The established detection sensitivity for helium leak testing is 10 -10 to 10 -9 Pam 3 /s. A total of 850 welded and mechanical joints inside the cryogenic test facility for the ITER Central Solenoid Model Coil (CSMC) experiments have been tested. In the test facility, 73 units of glass fiber-reinforced plastic (GFRP) insulation break are used. The amount of helium permeation through the GFRP was recorded during helium leak testing. To distinguish helium leaks from insulation-break permeation, the helium permeation characteristic of the GFRP part was measured as a function of the time of helium charging. Helium permeation was absorbed at 6 h after helium charging, and the detected permeation is around 10 -7 Pam 3 /s. Using the helium leak test method developed, CSMC experiments have been successfully completed. (author)

  3. Evaluation of high temperature gas reactor for demanding cogeneration load follow

    Yan, Xing L.; Sato, Hiroyuki; Tachibana, Yukio; Kunitomi, Kazuhiko; Hino, Ryutaro

    2012-01-01

    Modular nuclear reactor systems are being developed around the world for new missions among which is cogeneration for industries and remote areas. Like existing fossil energy counterpart in these markets, a nuclear plant would need to demonstrate the feasibility of load follow including (1) the reliability to generate power and heat simultaneously and alone and (2) the flexibility to vary cogeneration rates concurrent to demand changes. This article reports the results of JAEA's evaluation on the high temperature gas reactor (HTGR) to perform these duties. The evaluation results in a plant design based on the materials and design codes developed with JAEA's operating test reactor and from additional equipment validation programs. The 600 MWt-HTGR plant generates electricity efficiently by gas turbine and 900degC heat by a topping heater. The heater couples via a heat transport loop to industrial facility that consumes the high temperature heat to yield heat product such as hydrogen fuel, steel, or chemical. Original control methods are proposed to automate transition between the load duties. Equipment challenges are addressed for severe operation conditions. Performance limits of cogeneration load following are quantified from the plant system simulation to a range of bounding events including a loss of either load and a rapid peaking of electricity. (author)

  4. Dose conversion coefficients calculated using a series of adult Japanese voxel phantoms against external photon exposure

    Sato, Kaoru; Endo, Akira; Saito, Kimiaki

    2008-10-01

    This report presents a complete set of conversion coefficients of organ doses and effective doses calculated for external photon exposure using five Japanese adult voxel phantoms developed at the Japan Atomic Energy Agency (JAEA). At the JAEA, high-resolution Japanese voxel phantoms have been developed to clarify the variation of organ doses due to the anatomical characteristics of Japanese, and three male phantoms (JM, JM2 and Otoko) and two female phantoms (JF and Onago) have been constructed up to now. The conversion coefficients of organ doses and effective doses for the five voxel phantoms have been calculated for six kinds of idealized irradiation geometries from monoenergetic photons ranging from 0.01 to 10 MeV using EGS4, a Monte Carlo code for the simulation of coupled electron-photon transport. The dose conversion coefficients are given as absorbed dose and effective dose per unit air-kerma free-in-air, and are presented in tables and figures. The calculated dose conversion coefficients are compared with those of voxel phantoms based on the Caucasian and the recommended values in ICRP74 in order to discuss (1) variation of organ dose due to the body size and individual anatomy, such as position and shape of organs, and (2) effect of posture on organ doses. The present report provides valuable data to study the influence of the body characteristics of Japanese upon the organ doses and to discuss developing reference Japanese and Asian phantoms. (author)

  5. An update of the sorption database. Correction and addition of published literature data

    Saito, Yoshihiko; Suyama, Tadahiro; Kitamura, Akira; Shibata, Masahiro; Sasamoto, Hiroshi; Ochs, Michael

    2007-07-01

    Japan Nuclear Cycle Development Institute (JNC) had developed the sorption database (JNC-SDB) which includes distribution coefficient (K d ) data of important radioactive elements for bentonite and rocks in order to define a dataset to evaluate the safety function of retardation by natural barrier and engineered barrier in the H12 report. Then, JNC added to the database the sorption data from 1998 to 2003 collected by literature survey. In this report, Japan Atomic Energy Agency (JAEA) has updated the sorption database: (1) JAEA has widely collected the sorption data in order to extend the sorption database. The JNC-SDB has been added the published data which are not registered in the sorption database so far. (2) For the convenience of users the JNC-SDB was partially improved such as the automatic graph function. (3) Moreover, errors during data input in the part of the JNC-SDB were corrected on the basis of reviewing data in the database according to the guideline; 'evaluating and categorizing the reliability of distribution coefficient values in the sorption database'. In this updated JNC-SDB, 3,205 sorption data for 23 elements, which are important for performance assessment were included. The frequency of K d for some elements was clearly shown by addition of the sorption data. (author)

  6. Helium leak and chemical impurities control technology in HTTR

    Tochio, Daisuke; Shimizu, Atsushi; Hamamoto, Shimpei; Sakaba, Nariaki

    2014-01-01

    Japan Atomic Energy Agency (JAEA) has designed and developed high-temperature gas-cooled reactor (HTGR) hydrogen cogeneration system named gas turbine high-temperature reactor (GTHTR300C) as a commercial HTGR. Helium gas is used as the primary coolant in HTGR. Helium gas is easy to leak, and the primary helium leakage should be controlled tightly from the viewpoint of preventing the release of radioactive materials to the environment. Moreover from the viewpoint of preventing the oxidization of graphite and metallic material, the helium coolant chemistry should be controlled tightly. The primary helium leakage and the helium coolant chemistry during the operation is the major factor in the HTGR for commercialization of HTGR system. This paper shows the design concept and the obtained operational experience on the primary helium leakage control and primary helium impurity control in the high-temperature engineering test reactor (HTTR) of JAEA. Moreover, the future plan to obtain operational experience of these controls for commercialization of HTGR system is shown. (author)

  7. Progress of nuclear safety research - 2005

    Anoda, Yoshinari; Amaya, Masaki; Saito, Junichi; Sato, Atsushi; Sono, Hiroki; Tamaki, Hitoshi; Tonoike, Kotaro; Nemoto, Yoshiyuki; Motoki, Yasuo; Moriyama, Kiyofumi; Yamaguchi, Tetsuji; Araya, Fumimasa

    2006-03-01

    The Japan Atomic Energy Research Institute (JAERI), one of the predecessors of the Japan Atomic Energy Agency (JAEA), had conducted nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Five-Years Program for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI were the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI had conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI had taken a responsible role by providing experts in assistance to conducting accident investigations or emergency responses by the government or local government. These nuclear safety research and technical assistance to the government have been taken over as an important role by JAEA. This report summarizes the nuclear safety research activities of JAERI from April 2003 through September 2005 and utilized facilities. (author)

  8. Risk communication with Fukushima residents affected by the Fukushima Daiichi accident at whole-body counting

    Gunji, I.; Furuno, A.; Yonezawa, R.; Sugiyama, K.

    2013-01-01

    After the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi nuclear power plant accident, the Tokai Research and Development Center of the Japan Atomic Energy Agency (JAEA) have had direct dialogue as risk communication with Fukushima residents who underwent whole-body counting examination (WBC). The purpose of the risk communication was to exchange information and opinions about radiation in order to mitigate Fukushima residents' anxiety and stress. Two kinds of opinion surveys were performed: one survey evaluated residents' views of the nuclear accident itself and the second survey evaluated the management of WBC examination as well as the quality of JAEA's communication skills on risks. It appears that most Fukushima residents seem to have reduced their anxiety level after the direct dialogue. The results of the surveys show that Fukushima residents have the deepest anxiety and concern about their long-term health issues and that they harbor anger toward the government and TEPCO. On the other hand, many WBC patients and patients' relatives have expressed gratitude for help in reducing their feelings of anxiety

  9. R and D status on Water Cooled Ceramic Breeder Blanket Technology

    Enoeda, Mikio, E-mail: enoeda.mikio@jaea.go.jp; Tanigawa, Hisashi; Hirose, Takanori; Nakajima, Motoki; Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara; Kawamura, Yoshinori; Hayashi, Takumi; Yamanishi, Toshihiko; Hoshino, Tsuyoshi; Nakamichi, Masaru; Tanigawa, Hiroyasu; Nishi, Hiroshi; Suzuki, Satoshi; Ezato, Koichiro; Seki, Yohji; Yokoyama, Kenji

    2014-10-15

    Japan Atomic Energy Agency (JAEA) is performing the development of a Water Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) as one of the most important steps toward DEMO blanket. Regarding the blanket module fabrication technology development using F82H, the fabrication of a real scale mockup of the back wall of TBM was completed. In the design activity of the TBM, electromagnetic analysis under plasma disruption events and thermo-mechanical analysis under steady state and transient state of tokamak operation have been performed and showed bright prospect toward design justification. Regarding the development of advanced breeder and multiplier pebbles for DEMO blanket, fabrication technology development of Li rich Li{sub 2}TiO{sub 3} pebble and BeTi pebble was performed. Regarding the research activity on the evaluation of tritium generation performance, the evaluation of tritium production and recovery test using D-T neutron in the Fusion Neutronics Source (FNS) facility has been performed. This paper overviews the recent achievements of the development of the WCCB Blanket in JAEA.

  10. Current state of research base improvement relating to decommissioning

    Kawamura, Hiroshi

    2015-01-01

    'Nuclear Damage Compensation and Decommissioning Facilitation Corporation (NDF)' is responsible for the strategic planning and research and development planning for the important issues such as fuel debris removal and waste management, and for support for the progress management of important issues. The research and development are conducted by 'International Research Institute for Decommissioning (IRID)' and 'Japan Atomic Energy Agency (JAEA).' In the medium- and long-term roadmap, it is described that 'as for the facilities JAEA is improving, application to the decommissioning of Fukushima Daiichi Nuclear Power Station is the first choice, but depending on necessity, the linkage with Fukushima Innovation Coast plan is put into consideration.' In consideration of other backgrounds and with a focus on the contribution to regional industry creation, the research centers that can play the following functions are being developed. (1) Performance of bridging function as a 'place' to promote mutually beneficial university-industry collaborative creation, while sharing a wide variety of users and goals, (2) bridge between basic infrastructure research and social implementation as the demonstration test base, (3) bridge between the research and development of Japan and foreign countries using the world network of the research base, and (4) intensive promotion of demonstration experiments that are difficult for private agencies, and the formulation of robot testing standards. (A.O.)

  11. Operation, test, research and development of the high temperature engineering test reactor (HTTR). (FY2005)

    2007-03-01

    The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan, which is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. The full power operation of 30 MW was attained in December, 2001, and then JAERI (JAEA) received the commissioning license for the HTTR in March, 2002. Since 2002, we have been carrying out rated power operation, safety demonstration tests and several R and Ds, etc., and conducted the high-temperature test operation of 950degC in April, 2004. In fiscal 2005 year, periodical inspection and overhaul of reactivity control system were conducted, and safety demonstration tests were promoted. This report summarizes activities and test results on HTTR operation and maintenance as well as safety demonstration tests and several R and Ds, which were carried out in the fiscal year of 2005. (author)

  12. Study to paraphrase nuclear technical terms with clear and brief explanations

    Shobu, Nobuhiro; Takashita, Hirofumi; Horikoshi, Hidehiko; Osawa, Yukiko

    2010-01-01

    This report summarizes the review work to paraphrase nuclear technical terms with clear and brief explanations. Explanation with nuclear technical terms was not very acceptable to the public in a variety of contexts. The objective of this study is not to paraphrase with the expert's ideas but to paraphrase from the public point of view. Japan Atomic Energy Agency (hereafter abbreviated as 'JAEA') has conducted a survey on public attitudes toward fifty-nine nuclear technical terms by using an online questionnaire. Most of them were frequently used in the brochures of Nuclear fuel Cycle Engineering Laboratories of JAEA. The survey clarified the public awareness and comprehension of each term. Thirty-two terms, which was subject to paraphrase on a priority basis, were selected from fifty-nine nuclear technical terms based on our importance rating. At the work to paraphrase thirty-two terms, emphasis was placed more on clearness and briefness than on scientific/technical accuracy. They are reviewed through focus group interviews. This study brought results on recognizable style and thirty-two well-polished paraphrases. (author)

  13. Communication activity for residents to understand radiation after the accident of Fukushima Daiichi Nuclear Power Station

    Itabashi, Kiyoshi; Tagawa, Akihiro; Sugiyama, Kenji; Yamamoto, Tomoyo

    2015-01-01

    'Question-and-Answer Session on Radiation and Health' ('Kotaeru-kai' in Japanese) has started in July 2011 in Fukushima Prefecture, which was influenced by the accident of Fukushima Daiichi Nuclear Power Station following the Great East Japan Earthquake and Tsunami on 11 March 2011. The purpose of the Session is to have mainly parents and teachers (kindergartens, schools etc.) understand correctly about radiation and its influence on health. At the requests of the teachers in Fukushima Prefecture, about 4 staff members made a team, and visited Fukushima. The members of the team were selected from 500 JAEA staffs nominated beforehand. The members explained about radiation and its influence on health by using illustrations and metaphors. After the lecture, they answered the questions asked in advance at schools. Also they answered the questions asked in the Session. In the Session, the members placed much value on the communication with participants. Until the end of December 2014, the Question-and-Answer Sessions on Radiation and Health have been held 241 times for about twenty thousand participants. According to 7,613 participants' questionnaires, which were collected from July 2011 to the end of 2012, it seems that participants were able to understand well about radiation and its influence on health. Besides parents and teachers, some of the junior high schools requested to explain for students. JAEA will continue this communication activity in order to meet these expectations and requirements. (author)

  14. Practical application of the KMS: 2) site characterisation - 16355

    Semba, Takeshi; Osawa, Hideaki; Hioki, Kazumasa; Tachibana, Shoko; Takase, Hiroyasu; McKinley, Ian

    2009-01-01

    The characterisation of potential repository sites will produce huge volumes of information, which must be correlated, quality assured, integrated, analysed, documented and archived in a rigorous and efficient manner. While some of this work involves rather routine data handling that may be easily automated, much of it requires input of tacit knowledge which involves the experience of expert staff. To provide support for the Japanese implementer and also the regulator, a JAEA team is attempting to capture both Japanese and international geo-synthesis experience within a Knowledge Management System (KMS) framework, which is termed ISIS. This is a hybrid system that combines 'smart' software with human experts, although an aim is to capture tacit knowledge within expert systems to the maximum extent practicable. Initial tests, based mainly on field work carried out by JAEA at the sites of the Mizunami and Horonobe underground research laboratories, have utilised expert systems as modules in a 'blackboard system' approach to planning or implementing the processing of field data. Examples are presented of sub-systems where this approach has already been demonstrated and perspectives for more extensive application to integrated geo-synthesis management are discussed. (authors)

  15. Animal study on biological responses by radon inhalation making use of waste rock which contains feeble activity of uranium (2) (Joint research)

    Ishimori, Yuu; Sakoda, Akihiro; Tanaka, Hiroshi; Mitsunobu, Fumihiro; Yamaoka, Kiyonori; Kataoka, Takahiro; Etani, Reo

    2016-03-01

    Okayama University and the Japan Atomic Energy Agency (JAEA) have carried out the collaborative study of physiological effects of inhaled radon for the low-dose range. Main assignments were as follows. Based on the clinical knowledge, Misasa Medical Center (Okayama University Hospital) clarified the issues that should be addressed. Graduate School of Health Sciences (Okayama University) supervised the research and studied the biological responses. The JAEA made the development and control of a facility for radon inhalation experiments and the investigation of biokinetics and exposure doses of radon. From 2009 to 2013, the following results were obtained. (1) Literature on drinking effects of radon hot spring water was surveyed to determine the present tasks. (2) Under the present experimental conditions, drinking of hot spring water into which radon was intentionally introduced using the equipment in the facility did not have significant effects on mice. (3) Inhibitory effects of antioxidant pre-supplements (Vitamins C and E) and radon pre-inhalation on hepatic or renal oxidative damage were examined to make the comparison. (4) In order to discuss biological responses quantitatively following radon inhalation, the biokinetics of inhaled radon were studied. (5) Some exposure routes due to inhalation of radon or its progeny were modeled to calculate organ doses in mice. (author)

  16. Animal study on biological responses by radon inhalation making use of waste rock which contains feeble activity of uranium (Joint research)

    Ishimori, Yuu; Sakoda, Akihiro; Tanaka, Hiroshi; Mitsunobu, Fumihiro; Yamaoka, Kiyonori; Kataoka, Takahiro; Yamato, Keiko; Nishiyama, Yuichi

    2013-06-01

    Okayama University and the Japan Atomic Energy Agency (JAEA) have carried out the collaborative study of physiological effects of inhaled radon for the low-dose range. Main assignments were as follows. Based on the clinical knowledge, Misasa Medical Center (Okayama University Hospital) clarified the issues that should be addressed. Graduate School of Health Sciences (Okayama University) supervised the research and studied the biological responses. The JAEA made the development and control of a facility for radon inhalation experiments and the investigation of biokinetics and absorbed doses of radon. From 2007 to 2011, the following results were obtained. (1) Literature on effects of radon for the low-dose range was surveyed to determine the present tasks. (2) The first Japanese large-scale facility was developed for radon inhalation experiments with small animals. (3) Relationships between radon concentration and inhalation time were widely examined to understand the change in antioxidative functions due to radon, which are the most basic parameters. (4) Inhibitory effects of radon on oxidative damages were observed using model mice with reactive oxygen- or free radical-related diseases like alcohol-induced oxidative damages and type I diabetes. (5) In order to discuss biological responses quantitatively following radon inhalation, the biokinetics of inhaled radon was examined and the model for calculation of absorbed doses for organs and tissues was obtained. (author)

  17. Presumption of the distribution of the geological structure based on the geological survey and the topographic data in and around the Horonobe area

    Sakai, Toshihiro; Matsuoka, Toshiyuki

    2015-06-01

    The Horonobe Underground Research Laboratory (URL) Project, a comprehensive research project investigating the deep underground environment in sedimentary rock, is being pursued by the Japan Atomic Energy Agency (JAEA) at Horonobe-cho in Northern Hokkaido, Japan. One of the main goals of the URL project is to establish techniques for investigation, analysis and assessment of the deep geological environment. JAEA constructed the geologic map and the database of geological mapping in Horonobe-cho in 2005 based on the existing literatures and 1/200,000 geologic maps published by Geological Survey of Japan, and then updated the geologic map in 2007 based on the results of various investigations which were conducted around the URL as the surface based investigation phase of the URL project. On the other hand, there are many geological survey data which are derived from natural resources (petroleum, natural gas and coal, etc.) exploration in and around Horonobe-cho. In this report, we update the geologic map and the database of the geological mapping based on these geological survey and topographical analysis data in and around the Horonobe area, and construct a digital geologic map and a digital database of geological mapping as GIS. These data can be expected to improve the precision of modeling and analyzing of geological environment including its long-term evaluation. The digital data is attached on CD-ROM. (J.P.N.)

  18. Technological study about a disposal measures of low-level radioactive waste including uranium and long-half-life radionuclides

    Sugaya, Toshikatsu; Nakatani, Takayoshi; Sakai, Akihiro; Sakamoto, Yoshiaki; Sasaki, Toshihisa; Nakamura, Yasuo

    2017-02-01

    Japan Atomic Energy Agency (JAEA) performed the technical studies contributed for the disposal measures of uranium-bearing waste with low concentration and intermediate depth disposal-based waste occurring from the process of the nuclear fuel cycle. (1) Study of the trench disposal of uranium-bearing waste. As a part of the study of disposal measures of the uranium-bearing waste, we carried out the safety assessment (exposure dose assessment) and derived the upper limit of radioactivity concentration of uranium which was allowed to be included in radioactive waste for trench disposal. (2) Preliminary study for the expansion of material applied to clearance in uranium-bearing waste. Currently, the clearance level of uranium handling facilities was derived from the radioactivity concentration of uranium corresponding to dose criterion about the exposure pathways of the reuse and recycle of metal. Therefore, we preliminarily evaluated whether metal and concrete were able to be applied to clearance by the method of the undergrounding disposal. (3) Study of the concentration limitation scenarios for the intermediate depth disposal-based waste. We carried out dose assessment of intermediate depth disposal of radioactive waste generated from JAEA about radioactive concentration limitation scenarios of which the concept was shown by the study team in Nuclear Regulation Authority. Based on the results, we discussed whether the waste was applied to radioactive waste conforming to concept of intermediate depth disposal. (author)

  19. Decommissioning program and future plan for research hot laboratory (2)

    Koya, Toshio; Nozawa, Yukio; Hanada, Yasushi; Ono, Katsuto; Kanazawa, Hiroyuki; Nihei, Yasuo; Owada, Isao

    2010-01-01

    The Research Hot Laboratory (RHL) in Japan Atomic Energy Agency (JAEA) was constructed in 1961, as the first one in JAPAN, to perform the examinations of irradiated fuels and materials. RHL consists of 10 heavy concrete cells and 38 lead cells, which had been contributed to research and development program in or out of JAEA for the investigation of irradiation behavior for fuels and nuclear materials. However, RHL is the one of target as the rationalization program for decrepit facilities in former Tokai institute. Therefore the decommissioning works of RHL have been started on April 2003. The decommissioning work will be progressing, dismantling the lead cells and decontamination of concrete caves then release in the regulation of controlled area. The 18 lead cells (including semi-hot cell and junior-cell) had been dismantled. Removal of the applause from the cells, survey of the contamination revel in the lead cells and prediction of radio active waste have been finished as the preparing work for dismantling of the remained 20 lead cells. The future plan of decommissioning work has been prepared to incarnate the basic vision and dismantling procedure. (author)

  20. Clearance of concrete debris generated from modification work of JRR-3

    Satoyama, Tomonori; Nanri, Tomohiro; Kishimoto, Katsumi

    2014-01-01

    The Japan Atomic Energy Agency (JAEA) planned to apply the clearance system to slightly contaminated concrete debris with radionuclides, which was generated from the modification of the Japan Research Reactor No. 3 (JRR-3) in the Nuclear Science Research Institute (NSRI) of JAEA. The modification work was conducted from 1985 to 1990 and the generated concrete debris has been stored as radioactive waste in interim storage facilities in the NSRI. This is the Japanese first approved of clearance system to concrete debris and stored waste. We established procedures for measuring and evaluating the radioactivity concentration of scored concrete debris. In 2008, the authority approved these procedures for clearance. Since 2009, we have been measuring and evaluating the radioactivity concentration of concrete debris, using the approved procedures. By the end of 2012, the authority had confirmed the correctness of our measurement and evaluation results on about 2,600 tons of concrete debris. About 1,800 tons of those cleared concrete were recycled to flat surface subsidence in the NSRI caused by the Great East Japan Earthquake, and also used as base material to construct new buildings and parking lots in the NSRI. (author)

  1. Thermal mixing in T-junction piping system concerned with high-cycle thermal fatigue in structure

    Tanaka, Masaaki; Ohshima, Hiroyuki; Monji, Hideaki

    2008-01-01

    In Japan Atomic Energy Agency (JAEA), a numerical simulation code 'MUGTHES' has been developed to investigate thermal striping phenomena caused by turbulence mixing of fluids in different temperature and to provide transient data for an evaluation method of high-cycle thermal fatigue. MUGTHES adopts Large Eddy Simulation (LES) approach to predict unsteady phenomena in thermal mixing and employs boundary fitted coordinate system to be applied to complex geometry in a power reactor. Numerical simulation of thermal striping phenomena in a T-junction piping system (T-pipe) is conducted. Boundary condition for the simulation is chosen from an existing water experiment in JAEA, named as WATLON experiment. In the numerical simulation, standard Smagorinsky model is employed as eddy viscosity model with the model coefficient of 0.14 (=Cs). Numerical results of MUGTHES are verified by the comparisons with experimental results of velocity and temperature. Through the numerical simulation in the T-pipe, applicability of MUGTHES to the thermal striping phenomena is confirmed and the characteristic large-scale eddy structure which dominates thermal mixing and may cause high-cycle thermal fatigue is revealed. (author)

  2. Activities of the interactive public meetings on radiation and its health effect after the TEPCO Fukushima Daiichi Nuclear Power Station accident in the case of Nuclear Fuel Cycle Engineering Laboratories

    Sugiyama, Kenji; Ayame, Junko; Takashita, Hirofumi; Yamamoto, Ryuuichi

    2016-02-01

    Radioactive materials were widely released into the environment during the TEPCO Fukushima Daiichi Nuclear Power Station accident (hereinafter referred to as the Fukushima nuclear accident), which increased residents' fear of radiation and its health effects on their bodies. Japan Atomic Energy Agency (JAEA) has held public meetings on radiation and its health effects mainly for parents of students in kindergartens, elementary schools, and junior high schools in Fukushima prefecture after the Fukushima nuclear accident. These meetings are held based on our experience of practicing risk communication activities for a decade in JAEA with local residents. Questionnaires were collected after the meetings. The contents of the questionnaire are degree of understanding about the contents of the meetings, anxiety or worry items, opportunity of obtaining radiation and nuclear information before the accident, and some opinions and requests. By analyzing questionnaires, we confirmed that interactive communication is effective in increasing participants' understanding and in decreasing their anxiety. Risk communication study office supported the staff members of the meetings providing information such as participants' questions in the past meetings. To provide information, we made a homepage and held the orientation for the staff members. Questionnaires of the staff members were also collected and analyzed after the public meetings. (author)

  3. Geological disposal of high-level radioactive waste and the role of rock engineering

    Sugihara, Kozo

    2008-01-01

    Japan Atomic Energy Agency (JAEA) and its predecessors have been conducting an extensive geoscientific research program since the 1970's in order to contribute to the formation of a firm scientific and technological basis for the geological disposal of high level radioactive waste in Japan. As a part of this program, in situ experiments have been performed at the Tono Mine in soft sedimentary rocks and at the Kamaishi Mine in hard crystalline rocks. An experiment on excavation disturbance has been one of these experiments and has revealed the extent and properties of the excavation disturbed zone (EDZ) and the applicability of available measurement methods. It is suggested that mechanical excavation and controlled excavation have reduced excavation damage of the rock mass around a drift, although some improvements in the currently available methods for measuring and simulating the EDZ are essential to understand excavation disturbance in more detail. JAEA is now promoting two underground research laboratory projects in Japan; the Mizunami Underground Research Laboratory (MIU) project for crystalline rocks and the Horonobe Underground Research Laboratory (Horonobe URL) project for sedimentary rocks. From a rock mechanical point of view, the major interest in these projects will be paid to failure phenomenon deep underground, rock stress estimation at larger scales and long-term physical stability of underground structure. These projects are open for international collaboration. (author)

  4. Development of design technology on thermal-hydraulic performance in tight-lattice rod bundle. 4. Large paralleled simulation by the advanced two-fluid model code

    Misawa, Takeharu; Yoshida, Hiroyuki; Akimoto, Hajime

    2008-01-01

    In Japan Atomic Energy Agency (JAEA), the Innovative Water Reactor for Flexible Fuel Cycle (FLWR) has been developed. For thermal design of FLWR, it is necessary to develop analytical method to predict boiling transition of FLWR. Japan Atomic Energy Agency (JAEA) has been developing three-dimensional two-fluid model analysis code ACE-3D, which adopts boundary fitted coordinate system to simulate complex shape channel flow. In this paper, as a part of development of ACE-3D to apply to rod bundle analysis, introduction of parallelization to ACE-3D and assessments of ACE-3D are shown. In analysis of large-scale domain such as a rod bundle, even two-fluid model requires large number of computational cost, which exceeds upper limit of memory amount of 1 CPU. Therefore, parallelization was introduced to ACE-3D to divide data amount for analysis of large-scale domain among large number of CPUs, and it is confirmed that analysis of large-scale domain such as a rod bundle can be performed by parallel computation with keeping parallel computation performance even using large number of CPUs. ACE-3D adopts two-phase flow models, some of which are dependent upon channel geometry. Therefore, analyses in the domains, which simulate individual subchannel and 37 rod bundle, are performed, and compared with experiments. It is confirmed that the results obtained by both analyses using ACE-3D show agreement with past experimental result qualitatively. (author)

  5. The Japanese PR and PP program

    Senzaki, Masao; Inoue, Naoko; Kuno, Yusuke

    2008-01-01

    Japan has established the commercial nuclear fuel cycle with LWR as a non-weapon state, and now has been developing RF fuel cycle as the next generation technology. Japanese studies on proliferation resistance have started in 1990's by JNC, predecessor concern of JAEA. The early study was focused on the intrinsic features of Pu and safeguards technologies. Based on TOPS report, JNC has developed a quantitative assessment methodology and modified it by JNC designers. JNC and JAEA intends to play the role as a hub that contributes international collaborative study such as GEN IV PR and PP Experts Group and INPRO based on Japanese experiences of safeguards and nonproliferation efforts, and feedback to domestic experts. These efforts include not only the contribution into those programs, but also introduce these activities to Japanese domestic experts, holding international workshops, symposiums as a 'Hub' of domestic and international experts. This paper will introduce the Japanese Proliferation Resistance studies including, the early studies, international workshops/symposiums, the study in FaCT, international collaboration studies, and the future direction identified for the nuclear fuel cycle systems. (author)

  6. A development strategy for the business plan of Mitsubishi Small-sized High Temperature Gas-cooled Modular Reactor (MHR-50/100is)

    Minatsuki, Isao; Otani, Tomomi; Shimizu, Katsusuke; Mizokami, Yorikata; Oyama, Sunao; Tsukamoto, Hiroki

    2014-01-01

    A business plan and a new concept of Mitsubishi Small-sized High Temperature Gas-cooled Modular Reactor (MHR-50/100is) has been investigated toward a commercialization in near future by Mitsubishi Heavy Industries cooperated with Japan Atomic Energy Agency (JAEA) in Japan. The potential market of small sized reactor is expected to increase from the points of view of smaller investment, industrial use of the nuclear heat and IPP (Independent Power Producer). Especially minimization of construction unit cost including R and D and plant construction period are important issues in order to realize a business plan for them. The study includes four pertinent subject areas of (1) a market analysis, (2) a conceptual design, (3) improvement of safety design and (4) plant dynamics. In summary, the MHR-50/100 is designed to target a short construction period, competitive cost, and an inherent safety feature while applying only the verified technology of the High Temperature Engineering Test Reactor (HTTR) of JAEA or conventional technologies

  7. Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the Monju Reactor Vessel. Final Report of a Coordinated Research Project 2008-2012

    2014-11-01

    The IAEA supports Member States in the area of advanced fast reactor technology development by providing a major fulcrum for information exchange and collaborative research programmes. The IAEA’s activities in this field are mainly carried out within the framework of the Technical Working Group on Fast Reactors (TWG-FR), which assists in the implementation of corresponding IAEA support, and ensures that all technical activities are in line with expressed needs of Member States. Among this broad range, the IAEA proposes and establishes coordinated research projects (CRPs), aimed at improving Member State capability in fast reactor design and analysis. An important opportunity to perform collaborative research activities was provided by the system startup tests carried out by the Japan Atomic Energy Agency (JAEA) in the prototype loop type sodium cooled fast reactor Monju, in particular a turbine trip test performed in December 1995. As the JAEA opened the experimental dataset to international collaboration in 2008, the IAEA launched the CRP on Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the Monju Reactor Vessel. The CRP, together with eight institutes from seven States, has contributed to improving capabilities in sodium cooled fast reactors simulation through code verification and validation, with particular emphasis on thermal stratification and natural circulation phenomena

  8. A development strategy for the business plan of Mitsubishi Small-sized High Temperature Gas-cooled Modular Reactor (MHR-50/100is)

    Minatsuki, Isao, E-mail: isao_minatsuki@mhi.co.jp [Mitsubishi Heavy Industries, Ltd., 16-5, Konan 2-Chome, Minato-ku, Tokyo (Japan); Otani, Tomomi; Shimizu, Katsusuke [Mitsubishi Heavy Industries, Ltd., 16-5, Konan 2-Chome, Minato-ku, Tokyo (Japan); Mizokami, Yorikata; Oyama, Sunao; Tsukamoto, Hiroki [Mitsubishi Heavy Industries, Ltd., 1-1 Wadasaki-cho 1-Chome, Hyogo-ku, Kobe (Japan)

    2014-05-01

    A business plan and a new concept of Mitsubishi Small-sized High Temperature Gas-cooled Modular Reactor (MHR-50/100is) has been investigated toward a commercialization in near future by Mitsubishi Heavy Industries cooperated with Japan Atomic Energy Agency (JAEA) in Japan. The potential market of small sized reactor is expected to increase from the points of view of smaller investment, industrial use of the nuclear heat and IPP (Independent Power Producer). Especially minimization of construction unit cost including R and D and plant construction period are important issues in order to realize a business plan for them. The study includes four pertinent subject areas of (1) a market analysis, (2) a conceptual design, (3) improvement of safety design and (4) plant dynamics. In summary, the MHR-50/100 is designed to target a short construction period, competitive cost, and an inherent safety feature while applying only the verified technology of the High Temperature Engineering Test Reactor (HTTR) of JAEA or conventional technologies.

  9. Full scale trials for qualification of the manufacture of the ITER TF coils in Japan

    Matsui, Kunihiro, E-mail: matsui.kunihiro@jaea.go.jp; Hemmi, Tsutomu; Kajitani, Hideki; Yamane, Minoru; Mizutani, Takumi; Nakano, Toshihide; Takano, Katsutoshi; Ando, Shinji; Koizumi, Norikiyo

    2016-11-01

    Highlights: • High accuracy conductor winding of 0.1% was achieved in TF coil fabrication. • Conductor elongation due to heat treatment satisfied with the expected value of 0.06% ± 0.02%. • Commissioning of a transfer tooling without adding strain to conductor was completed. • Commissioning of a conductor insulation and CP welding was successfully completed. - Abstract: JAEA performed full-scale trials to qualify and optimize manufacturing procedure of TF coil fabrication prior to series production. In the full-scale trials, conductor winding, heat treatment, conductor transfer, conductor insulation and cover plate (CP) welding trials were performed to resolve some technical issues and to demonstrate the fabrication procedure. The followings are major achievement. (1) High accuracy conductor winding of 0.01%, (2) the evaluation of 0.06% conductor elongation due to heat treatment, (3) conductor transfer in a radial plate (RP) groove with addition strain under 0.1%, (4) conductor insulation without breakage of the insulation tape and (5) flatness of 2 mm of the double pancake (DP) by CP welding. Then JAEA started the 1st TF coil fabrication from March 2014, and has already completed ten conductor windings and heat treatment of nine windings.

  10. Development of radiation resistant structural materials utilizing fission research reactors in Japan (Role of research reactors)

    Shikama, T.; Tanigawa, H.; Nozawa, T.; Muroga, T.; Aoyama, T.; Kawamura, H.; Ishihara, M.; Ito, C.; Kaneda, S.; Mimura, S.

    2009-01-01

    Structural materials for next-generation nuclear power systems should have a good radiation resistance, where the expected accumulation dose will largely exceed 10 dpa. Among several candidate materials, materials of five categories, 1. Austenitic steels, including high nickel alloys, 2. Low activation ferritic martensitic steels, 3. ODS steels (austenitic and ferritic), 4. Vanadium based alloys, 5. Silicon carbide composites (SiC/SiCf). All have been most extensively studied in Japan, in collaboration among industries, national institutes such as Japan Atomic Energy Agency (JAEA), National Institute for Fusion Science (NIFS) and National Institute for Materials Science (NIMS), and universities. The high nickel base alloys were studied for their low swelling behaviors mainly by the NIMS and the austenitic steels are studied for their reliable engineering data base and their reliable performance in irradiation environments mainly by the JAEA, mainly for their application in the near-term projects such as the ITER and the Sodium Cooled Fast Reactors. The most extensive studies are now concentrated on the Low Activation Ferritic Marsensitic steels and ODS steels, for their application in a demonstration fusion reactor and prototype sodium cooled fast reactors. Fundamental studies on radiation effects are carried out, mainly utilizing Japan Materials Testing Rector (JMTR) with its flexible irradiation ability, up to a few dpa. For higher dpa irradiation, a fast test reactor, JOYO is utilized up to several 10s dpa. Some international collaborations such as Japan/USA and Japan/France are effective to utilize reactors abroad, such as High Flux Isotope Reactor (HFIR) of Oak Ridge National Laboratory, and sodium cooled high flux fast reactors in France. Silicon carbide based composites are extensively studied by university groups led by Kyoto University and the JAEA. For their performance in heavy irradiation environments, the Japan/USA collaboration plays an important role

  11. Japan Sea expeditions for studies on water circulation and transport processes of radionuclides

    Togawa, Orihiko; Ito, Toshimichi; Kobayashi, Takuya; Otosaka, Shigeyoshi; Suzuki, Takashi

    2006-02-01

    The Japan Sea expeditions at the Japan Atomic Energy Agency (JAEA from October 1, 2005, former JAERI: Japan Atomic Energy Research Institute until September 30, 2005) were started on its participation in the first and second Japanese-Korean-Russian joint expeditions in 1994 and 1995 to investigate the situation on marine pollution due to radioactive wastes dumped in the Japan Sea and other seas around Japan. After the joint expeditions, JAEA continued to conduct the Japan Sea expeditions not only to monitor the impacts of radioactive wastes dumped in the Japan Sea, but also to investigate water circulation and the migration behavior of radionuclides in the Japan Sea. Taking account of some difficulties and constraints due to the political boundaries in the Japan Sea, the expeditions were carried out, separating the sea into two regions; one is the Japanese exclusive economical zone (EEZ) and the other is the Russian EEZ. The data of observations and measurements obtained in the two regions were analyzed together. The program of the Japan Sea expeditions included large-volume seawater sampling at different depths and seabed sediment sampling for measurements of representative anthropogenic radionuclides. To investigate the migration behavior of the radionuclides more in detail, associated oceanographic observations were also implemented; CTD/MBS (conductivity-temperature-depth meter with multi-bottle sampler) casts, analysis of dissolved oxygen and nutrients, deployment and recovery of mooring systems with current meters and sediment traps, and so on. Additional seawater samples were taken with CTD/MBS for further analysis on land. This report summarizes the results of the Japan Sea expeditions (Phase 1) conducted and/or jointed by JAEA from 1994 to 2002. First the report explains oceanographic features of the Japan Sea, main expeditions in the past and the summarized results of the Japanese-Korean-Russian joint expeditions. Then the report gives an outline of the

  12. Annual report of Nuclear Human Resource Development Center. April 1, 2011 - March 31, 2012

    2013-11-01

    This annual report summarizes the activities of Nuclear Human Resource Development Center (NuHRDeC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2011. In this fiscal year, we flexibly designed and conducted training courses corresponding with the needs from outside, while conducting the annually scheduled training programs, and also actively addressed the challenge of human resource development, such as to enhance the collaboration with academia and to organize international training for Asian countries. The number of trainees who completed the domestic training courses in 2011 was increased to 387, which is 14 percent more than the previous year. And also, in order to respond to the Tokyo Electric Power Company (TEPCO)'s Fukushima No.1 nuclear power plant accident, we also newly designed and organized the special training courses on radiation survey for the subcontracting companies working with TEPCO, and the training courses on decontamination work for the construction companies in Fukushima prefecture. The total number of attendees in these special courses was 3,800 persons. JAEA continued its cooperative activities with universities. In respect of the cooperation with graduate school of University of Tokyo, we accepted 17 students and cooperatively conducted practical exercises for nuclear major. Furthermore, we also actively continued cooperation on practical exercises for students of universities which were signed in Nuclear HRD Program. In terms of the collaboration network with universities, the joint course was held with six universities through utilizing the remote education system. Furthermore, the intensive course at Okayama University and practical exercise at Nuclear Fuel Cycle Engineering Laboratories of JAEA were also conducted. In respect of International training, NuHRDeC continuously implemented the Instructor Training Program (ITP) by receiving the annual sponsorship from MEXT. In fiscal year 2011, seven countries (i.e. Bangladesh

  13. Annual report of Nuclear Human Resource Development Center. April 1, 2013 - March 31, 2014

    2015-07-01

    This annual report summarizes the activities of Nuclear Human Resource Development Center (NuHRDeC) of Japan Atomic Energy Agency (JAEA) in the FY2013. In FY2013, we flexibly designed special training courses corresponding with the outside training needs, while organizing the annually scheduled regular training programs. We also actively addressed the challenging issues on human resource development, such as to enhance the collaboration with academia and to organize international training for Asian countries. The number of trainees who participated in the domestic regular training courses in 2013 was more than 300 persons. Besides these regular courses, we also organized the special training courses based on the outside needs, e.g. the training courses on radiation survey and decontamination work in Fukushima prefecture for the subcontracting companies of the Tokyo Electric Power Company (TEPCO) working to respond to the TEPCO's Fukushima Daiichi nuclear power station accident. JAEA continued its cooperative activities with universities. In respect of the cooperation with graduate school of University of Tokyo, we accepted nuclear major students and cooperatively conducted lectures and practical exercises for one year. In terms of the collaboration network with universities, the joint course was successfully held with six universities through utilizing the remote education system. Furthermore, the intensive course at Okayama University, University of Fukui, and practical exercise at Nuclear Fuel Cycle Engineering Laboratories of JAEA were also conducted. In respect of International training, we continuously implemented the Instructor Training Program (ITP) by receiving the annual sponsorship from Ministry of Education, Culture, Sports, Science and Technology. In fiscal year 2013, eight countries (i.e. Bangladesh, Indonesia, Kazakhstan, Malaysia, Mongolia, Philippines, Thailand, Vietnam) joined this Instructor training courses. Furthermore, we organized nuclear

  14. Annual report of Nuclear Human Resource Development Center. April 1, 2014 - March 31, 2015

    2017-06-01

    This annual report summarizes the activities of Nuclear Human Resource Development Center (NuHRDeC) of Japan Atomic Energy Agency (JAEA) in the fiscal year (FY) 2014. In FY 2014, we flexibly designed special training courses corresponding with the outside training needs, while organizing the annually scheduled regular training programs. We also actively addressed the challenging issues on human resource development, such as to enhance the collaboration with academia and to organize international training for Asian countries. Besides these regular courses, we also organized the special training courses based on the outside needs, e.g. Nuclear Regulatory Authority or the people in Naraha town in Fukushima Prefecture. JAEA continued its cooperative activities with universities. In respect of the cooperation with graduate school of The University of Tokyo, we accepted nuclear major students and cooperatively conducted lectures and practical exercises for one year. In terms of the collaboration network with universities, the joint course was successfully held with six universities through utilizing the remote education system. Besides, the intensive summer course and practical exercise at Nuclear Fuel Cycle Engineering Laboratories were also conducted. Furthermore, JAEA had re-signed the agreement “Japan Nuclear Education Network” with 7 Universities in Feb. 2015 for the new participation of Nagoya University from FY 2015. Concerning International training, we continuously implemented the Instructor Training Program (ITP) by receiving the annual sponsorship from Ministry of Education, Culture, Sports, Science and Technology. In FY 2014, eight countries (i.e. Bangladesh, Indonesia, Kazakhstan, Malaysia, Mongolia, Philippines, Thailand and Vietnam) joined this Instructor training courses such as “Reactor Engineering Course”. Furthermore, we organized nuclear technology seminar courses, e.g. “Basic Radiation Knowledge for School Education”. In respect of

  15. Annual report of Nuclear Human Resource Development Center. April 1, 2012 - March 31, 2013

    2014-03-01

    This annual report summarizes the activities of Nuclear Human Resource Development Center (NuHRDeC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2012. In this fiscal year, we flexibly designed training courses corresponding with the needs from outside, while organizing the annually scheduled training programs, and also actively addressed the challenging issues on human resource development, such as to enhance the collaboration with academia and to organize international training for Asian countries. The number of trainees who completed the domestic training courses in 2012 was increased to 525, which is 30 percent more than the previous year. And also, in order to respond to the Tokyo Electric Power Company (TEPCO)'s Fukushima No.1 nuclear power plant accident, we also organized the special training courses on radiation survey for the subcontracting companies working with TEPCO, and the training courses on decontamination work for the construction companies in Fukushima prefecture. The total number of attendees in these special courses was more than 4,000 persons. JAEA continued its cooperative activities with universities. In respect of the cooperation with graduate school of University of Tokyo, we accepted 14 students and cooperatively conducted practical exercises for nuclear major. Furthermore, we also actively continued cooperation on practical exercises for students of universities which were signed in Nuclear HRD Program. In terms of the collaboration network with universities, the joint course was held with six universities through utilizing the remote education system. Furthermore, the intensive course at Okayama University, Fukui University, and practical exercise at Nuclear Fuel Cycle Engineering Laboratories of JAEA were also conducted. In respect of International training, NuHRDeC continuously implemented the Instructor Training Program (ITP) by receiving the annual sponsorship from MEXT. In fiscal year 2012, eight countries (i

  16. Whole-body counting of Fukushima residents after the TEPCO Fukushima Daiichi Nuclear Power Station accident

    Momose, Takumaro; Takada, Chie; Nakagawa, Takahiro; Nakai, Katsuta; Kurihara, Osamu; Tsujimura, Norio; Furuta, Sadaaki [Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, Tokai, Ibaraki (Japan); Ohi, Yoshihiro; Murayama, Takashi; Suzuki, Takashi [Japan Atomic Energy Agency, Nuclear Science Research Institute, Tokai, Ibaraki (Japan); Uezu, Yasuhiro [Japan Atomic Energy Agency, Fukushima Environmental Safety Center, Fukushima, Fukushima (Japan)

    2012-11-15

    At the request of the Fukushima government, the Japan Atomic Energy Agency (JAEA) started whole-body counting of residents on July 11, 2011, to assess radiation exposure after the TEPCO Fukushima Daiichi Nuclear Power Station accident. JAEA has examined residents in Iitate, Kawamata, Namie, and eight other local communities. The measurement capacity of the whole-body counting device is approximately 100 persons per day, and the total number of people to measure reached 9,927 by the end of January 2012. Two types of whole-body counter (WBC), each of which has two large-sized NaI(Tl) detectors, were used to perform the measurements. Physical phantoms (a Canberra RMC-II transfer phantom or a water-filled block phantom developed by JAEA) were used to perform the efficiency calibration of the WBCs, and results of this calibration were verified by comparing them with different-sized BOttle Mannequin ABsorber (BOMAB) phantoms imitating an adult male, a 10-year-old child, and a 4-year-old child. Short half-life radionuclides (e.g., {sup 131}I) originating from the accident were not detected in the present work, because the measurements were made starting four months after the accident. These measurements showed that about 80% of the residents were below a minimum detectable amount (MDA) of the measured radionuclides in the whole-body content. No artificial nuclides other than {sup 134}Cs and {sup 137}Cs were detected in the present whole-body counting. The maximum whole-body content of radiocesium ({sup 134}Cs and {sup 137}Cs in total) was 2.7 kBq for children (< 8 years old) and 14 kBq for adults. The radioactivity ratio ({sup 137}Cs/{sup 134}Cs) was estimated to be from 1.12 to 1.26. An acute intake scenario via inhalation of radiocesium was assumed in the present dose estimation for all the residents who were measured by the end of January 2012. The committed effective dose (CED) to 99.8% of the residents was found to be below 1 mSv. There were only 25 subjects with a

  17. Conceptual design of multipurpose compact research reactor

    Nagata, Hiroshi; Kusunoki, Tsuyoshi; Hori, Naohiko; Kaminaga, Masanori

    2012-01-01

    Conceptual design of the high-performance and low-cost multipurpose compact research reactor which will be expected to construct in the nuclear power plant introduction countries, started from 2010 in JAEA and nuclear-related companies in Japan. The aims of this conceptual design are to achieve highly safe reactor, economical design, high availability factor and advanced irradiation utilization. One of the basic reactor concept was determined as swimming pool type, thermal power of 10MW and water cooled and moderated reactor with plate type fuel element same as the JMTR. It is expected that the research reactors are used for human resource development, progress of the science and technology, expansion of industry use, lifetime extension of LWRs and so on. (author)

  18. Development of a groundwater monitoring system at Horonobe Underground Research Center

    Nanjo, Isao; Amano, Yuki; Iwatsuki, Teruki; Murakami, Hiroaki; Kunimaru, Takanori; Morikawa, Keita; Hosoya, Shinichi

    2012-03-01

    Japan Atomic Energy Agency (JAEA) develops basic investigation techniques for deep geological environment around Underground Research Laboratory (URL) at Horonobe area, Japan. The observation technique of hydrochemical condition in low permeable sedimentary rock around the facility is one of R and D subjects. We report, 1) development of hydrochemical monitoring system to observe water pressure, pH, electric conductivity, dissolved oxygen, redox potential and temperature, 2) hydrochemical observation results around URL under construction. The applicability of the hydrochemical monitoring system is evaluated for low permeable sedimentary rock bearing abundant dissolved gases. The hydrochemical observation during facility construction demonstrates that pH and redox potential of groundwater almost did not changed even at hydraulic disturbed zone (water pressure decreased zone). A CD-ROM is attached as an appendix. (J.P.N.)

  19. Design of auxiliary shield for remote controlled metallographic microscope

    Matsui, Hiroki; Okamoto, Hisato

    2014-06-01

    The remote controlled optical microscope installed in the lead cell at the Reactor Fuel Examination Facility (RFEF) in Japan Atomic Energy Agency (JAEA) has been upgraded to a higher performance unit to study the effect of the microstructural evolution in clad material on the high burn-up fuel behavior under the accident condition. The optical pass of the new microscope requires a new through hole in the shielding lead wall of the cell. To meet safety regulations, auxiliary lead shieldings were designed to cover the lost shielding function of the cell wall. Particle and Heavy Ion Transport Code System (PHITS) was used to calculate and determine the shape and setting positions of the shielding unit. Seismic assessments of the unit were also performed. (author)

  20. Manual for environmental radiological surveillance

    Sumiya, Shuichi; Matsuura, Kenichi; Nakano, Masanao; Takeyasu, Masanori; Morisawa, Masato; Onuma, Toshimitsu; Fujita, Hiroki; Mizutani, Tomoko; Watanabe, Hajime; Sugai, Masamitsu

    2010-03-01

    Environmental radiation monitoring around the Tokai Reprocessing Plant has been conducted by the Nuclear Fuel Cycle Engineering Laboratories, based on 'Safety Regulations for the Reprocessing Plant of JAEA, Chapter IV - Environmental monitoring' and Environmental Radiation Monitoring Program decided by the Ibaraki prefectural government. The radiation monitoring installations and equipments were also prepared for emergency. This manual describes; (1) the installations of radiological measurement, (2) the installations of meteorological observation, and (3) environmental data processing system for executing the terrestrial environmental monitoring by Environmental Protection Section, Radiation Protection Department. The environmental monitoring has been operated through the manual published in 1993 (PNC TN8520 93-001). Then the whole articles were revised because the partially of installations and equipments having been updated in recent years. (author)

  1. Introduction of a backup system for data and servers of main IT infrastructure services

    Hirayama, Takashi; Kannari, Masaaki

    2013-06-01

    The optimization of the JAEA network system has been promoted in accordance with the optimization plan which has the fundamental principles of ensuring its dependability, information security and usability. In respect to ensuring the dependability, we addressed to a) the reduction of both trouble probability and recovery time, and b) an execution of the business continuity plan in time of large-scale earthquake. For the latter, we installed an e-mail backup server and an alternate connection to the internet in Kansai Photon Science Institute (Kizu-area) based on lesson learned from the experience of the Great East Japan Earthquake on March 11, 2011. In addition, we introduced a backup system for data and servers of other main IT infrastructure services. This report documents the configuration and operation of the backup system. (author)

  2. First successful ionization of Lr (Z = 103) by a surface-ionization technique

    Sato, Tetsuya K., E-mail: sato.tetsuya@jaea.go.jp; Sato, Nozomi; Asai, Masato; Tsukada, Kazuaki; Toyoshima, Atsushi; Ooe, Kazuhiro; Miyashita, Sunao; Schädel, Matthias [Advanced Science Research Center, Japan Atomic Energy Agency (JAEA), 2-4 Shirakata-shirane, Tokai-mura, Ibaraki 319-1195 (Japan); Kaneya, Yusuke; Nagame, Yuichiro [Advanced Science Research Center, Japan Atomic Energy Agency (JAEA), 2-4 Shirakata-shirane, Tokai-mura, Ibaraki 319-1195 (Japan); Graduate School of Science and Engineering, Ibaraki University, 2-1-1, Bunkyo, Mito, Ibaraki 310-8512 (Japan); Osa, Akihiko [Department of Research Reactor and Tandem Accelerator, Japan Atomic Energy Agency (JAEA), 2-4 Shirakata shirane, Tokai-mura, Ibaraki 319-1195 (Japan); Ichikawa, Shin-ichi [Advanced Science Research Center, Japan Atomic Energy Agency (JAEA), 2-4 Shirakata-shirane, Tokai-mura, Ibaraki 319-1195 (Japan); Nishina Center for Accelerator-Based Science, RIKEN, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Stora, Thierry [ISOLDE, CERN, CH-1211 Geneva 23 (Switzerland); Kratz, Jens Volker [Institut für Kernchemie, Universität Mainz, D-55099 Mainz (Germany)

    2013-02-15

    We have developed a surface ionization ion-source as part of the JAEA-ISOL (Isotope Separator On-Line) setup, which is coupled to a He/CdI{sub 2} gas-jet transport system to determine the first ionization potential of the heaviest actinide lawrencium (Lr, Z = 103). The new ion-source is an improved version of the previous source that provided good ionization efficiencies for lanthanides. An additional filament was newly installed to give better control over its operation. We report, here, on the development of the new gas-jet coupled surface ion-source and on the first successful ionization and mass separation of 27-s {sup 256}Lr produced in the {sup 249}Cf + {sup 11}B reaction.

  3. Detailed benchmark test of JENDL-4.0 iron data for fusion applications

    Konno, Chikara, E-mail: konno.chikara@jaea.go.jp [Japan Atomic Energy Agency, Tokai-Mura, Ibaraki-ken, 319-1195 (Japan); Wada, Masayuki [Japan Computer System, Mito, 310-0805 (Japan); Kondo, Keitaro; Ohnishi, Seiki; Takakura, Kosuke; Ochiai, Kentaro; Sato, Satoshi [Japan Atomic Energy Agency, Tokai-Mura, Ibaraki-ken, 319-1195 (Japan)

    2011-10-15

    The major revised version of Japanese Evaluated Nuclear Data Library (JENDL), JENDL-4.0, was released in May, 2010. As one of benchmark tests, we have carried out a benchmark test of JENDL-4.0 iron data, which are very important for radiation shielding in fusion reactors, by analyzing the iron fusion neutronics integral experiments (in situ and Time-of-Flight (TOF) experiments) at JAEA/FNS. It is demonstrated that the problems of the iron data in the previous version of JENDL, JENDL-3.3, are solved in JENDL-4.0; the first inelastic scattering cross section data of {sup 57}Fe and the angular distribution of the elastic scattering of {sup 56}Fe. The iron data in JENDL-4.0 are comparable to or are partly better than those in ENDF/B-VII.0 and JEFF-3.1.

  4. Real-time multi-function entry / exit management system

    Hiyama, Kazuhisa; Kurosawa, Akihiko; Asano, Norikazu; Onoue, Ryuji; Eguchi, Shohei; Hanawa, Nobuhiro; Hori, Naohiko; Ueda, Hisao; Kanda, Hiroaki

    2012-01-01

    In order to prevent radiation accident and its expansion, more integrated management system is required to safety management for radiation workers in the nuclear facilities. Therefore, JAEA (Japan Atomic Energy Agency) and HAM (Hitachi Aloka Medical, Ltd) have developed innovative real-time multi-function entry/exit management system which managed worker's exposed dose and position under the joint developed patent. This system is sharing worker's data among workers and server manager who is inside of or outside of building, such as worker's positing, health condition and exposed dose. It consists of mobile equipments, receivers, LAN, and servers system. This report summarizes the system to be installed in the JMTR. (author)

  5. Design study of the compact ERL

    Hajima, Ryoichi; Nakamura, Norio; Sakanaka, Shogo; Kobayashi, Yukinori

    2008-02-01

    Energy-recovery linac (ERL) is a promising device for future X-ray light sources, which can produce coherent X-rays and femto-second X-ray pulses. In Japan, we have organized a collaboration team, consisting of the members of KEK, JAEA, ISSP and other laboratories, toward realization of future ERL light sources, and started R and D efforts to establish accelerator technologies relevant to the ERL light source. In order to demonstrate all the accelerator technologies working together, we have decided to build a small facility, the Compact ERL. This report presents a design study of the Compact ERL, which includes R and D issues for each accelerator component, studies on the beam dynamics, performance of the Compact ERL as a light source of THz and X-ray. (author)

  6. Research and development of grid computing technology in center for computational science and e-systems of Japan Atomic Energy Agency

    Suzuki, Yoshio

    2007-01-01

    Center for Computational Science and E-systems of the Japan Atomic Energy Agency (CCSE/JAEA) has carried out R and D of grid computing technology. Since 1995, R and D to realize computational assistance for researchers called Seamless Thinking Aid (STA) and then to share intellectual resources called Information Technology Based Laboratory (ITBL) have been conducted, leading to construct an intelligent infrastructure for the atomic energy research called Atomic Energy Grid InfraStructure (AEGIS) under the Japanese national project 'Development and Applications of Advanced High-Performance Supercomputer'. It aims to enable synchronization of three themes: 1) Computer-Aided Research and Development (CARD) to realize and environment for STA, 2) Computer-Aided Engineering (CAEN) to establish Multi Experimental Tools (MEXT), and 3) Computer Aided Science (CASC) to promote the Atomic Energy Research and Investigation (AERI). This article reviewed achievements in R and D of grid computing technology so far obtained. (T. Tanaka)

  7. Preparation and evaluation of reference materials for accountancy analysis. (1) Preparation and evaluation method

    Takamatsu, Mai; Kacchi, Tomokazu; Murakami, Toshiki; Ai, Hironobu; Sumi, Mika; Abe, Katsuo; Kageyama, Tomio; Nakazawa, Hiroaki

    2009-01-01

    Isotope dilution mass spectrometry method used for the accountancy analysis at nuclear fuel facilities requires the standard materials called LSD (Large Size Dried) spike. Generally, LSD spikes are prepared from certified reference materials (CRMs) which supplied from foreign laboratories. However, the difficulty of Pu CRM importation is increasing. It is important for safeguards to attain and continue high reliable accountancy analysis and stable securing of LSD spike is essential. Therefore, in order to conserve CRMs, several types of LSD spike were prepared under collaboration work between JAEA and JNFL, such as the amount of nuclear material in one LSD spike is decreased and others. Practical test with actual samples were performed at JNFL Rokkasho reprocessing plant, and those results were compared with the results obtained by using LSD spike which supplied from foreign laboratory. Preparation and verification analysis of LSD spikes and evaluation of uncertainty based on ISO-GUM will be presented. (author)

  8. Status of material development for lifetime expansion of beryllium reflector

    Dorn, C [Materion Brush Beryllium and Composites, California (United States); Tsuchiya, Kunihiko; Kawamura, Hiroshi [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan); Hatano, Y [Univ. of Toyama, Toyama (Japan); Chakrov, P [INP-KNNC, Almaty (Kazakhstan); Kodama, M [Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki (Japan)

    2012-03-15

    Beryllium has been used as the reflector element material in the reactor, specifically S-200F structural grade beryllium manufactured by Materion Brush Beryllium and Composites (former, Brush Wellman Inc.). As a part of the reactor upgrade, the Japan Atomic Energy Agency (JAEA) also has carried out the cooperation experiments to extend the operating lifetime of the beryllium reflector elements. It will first be necessary to determine which of the material's physical, mechanical and chemical properties will be the most influential on that choice. The irradiation testing plans to evaluate the various beryllium grades are also briefly considered and prepared. In this paper, material selection, irradiation test plan and PEI development for lifetime expansion of beryllium are described for material testing reactors. (author)

  9. Conceptual design of next generation MTR

    Nagata, Hiroshi; Yamaura, Takayuki; Naka, Michihiro; Kawamata, Kazuo; Izumo, Hironobu; Hori, Naohiko; Nagao, Yoshiharu; Kusunoki, Tsuyoshi; Kaminaga, Masanori; Komori, Yoshihiro; Suzuki, Masahide; Kawamura, Hiroshi [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan); Mine, M [Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki (Japan); Yamazaki, S [Kawasaki Heavy Industries, Ltd., Kobe, Hyogo (Japan); Ishikawa, S [NGK Insulators, Ltd., Nagoya, Aichi (Japan); Miura, K [Sukegawa Electric Co., Ltd., Takahagi, Ibaraki (Japan); Nakashima, S [Fuji Electric Co., Ltd., Tokyo (Japan); Yamaguchi, K [Chiyoda Technol Corp., Tokyo (Japan)

    2012-03-15

    Conceptual design of the high-performance and low-cost next generation materials testing reactor (MTR) which will be expected to construct in the nuclear power plant introduction countries, started from 2010 in JAEA and nuclear-related companies in Japan. The aims of this conceptual design are to achieve highly safe reactor, economical design, high availability factor and advanced irradiation utilization. One of the basic reactor concept was determined as swimming pool type, thermal power of 10MW and water cooled and moderated reactor with plate type fuel element same as the JMTR. It is expected that the research reactors are used for human resource development, progress of the science and technology, expansion of industry use, lifetime extension of LWRs and so on. (author)

  10. Sludge behavior in centrifugal contactor operation for nuclear fuel reprocessing

    Sakamoto, Atsushi; Sano, Yuichi; Takeuchi, Masayuki; Okamura, Nobuo; Koizumi, Kenji

    2015-01-01

    The Japan Atomic Energy Agency (JAEA) has been developing the centrifugal contactor for spent fuel reprocessing. In this study, we investigated the sludge behavior in centrifugal contactors at three different scales. The operational conditions (the flow rate and rotor speed) were varied. Most insoluble particles such as sludge remained in the rotor via centrifugal force. The capture ratio of sludge in the contactor was measured as a function of particle size at various flow rates, rotor speeds, and contactor scales. The sludge adhered and accumulated inside the rotor as the operational time increased, and the operational conditions influenced the capture ratio of the sludge; a lower flow rate and higher rotor speed increased the capture ratio. The results confirmed that Stokes' law can be applied to estimate the experimental result on the behavior of the capture ratio for centrifugal contactors with different scales. (author)

  11. Preliminary results of consequence assessment of a hypothetical severe accident using Thai meteorological data

    Silva, K.; Lawawirojwong, S.; Promping, J.

    2017-06-01

    Consequence assessment of a hypothetical severe accident is one of the important elements of the risk assessment of a nuclear power plant. It is widely known that the meteorological conditions can significantly influence the outcomes of such assessment, since it determines the results of the calculation of the radionuclide environmental transport. This study aims to assess the impacts of the meteorological conditions to the results of the consequence assessment. The consequence assessment code, OSCAAR, of Japan Atomic Energy Agency (JAEA) is used for the assessment. The results of the consequence assessment using Thai meteorological data are compared with those using Japanese meteorological data. The Thai case has following characteristics. Low wind speed made the radionuclides concentrate at the center comparing to the Japanese case. The squalls induced the peaks in the ground concentration distribution. The evacuated land is larger than the Japanese case though the relocated land is smaller, which is attributed to the concentration of the radionuclides near the release point.

  12. Evaluating methods to improve safeguards training courses of ISCN

    Okumura, Yukiko; Nakamura, Yo; Kawata, Norio

    2014-01-01

    Although questionnaires were used to receive feedbacks from participants at the end of each training course, Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of Japan Atomic Energy Agency (JAEA) did not establish a structured evaluation method. To this end, ISCN has started to study on methods to accurately evaluate the courses since April and started to introduce the evaluation method on trial, according to the Donald Kirkpatrick's Four-Level Training Evaluation Model, so as to better develop and conduct more effective courses. This paper will focus on how ISCN has modified the Kirkpatrick's Four-level to adapt to its safeguards training courses. This will then be followed by two particular cases of how the evaluation method functioned for the Additional Protocol training courses held in Malaysia in 2014, and the feedbacks received to improve future training courses. (author)

  13. Design concept of a knowledge management system of geological disposal technology

    Osawa, Hideaki; Umeki, Hiroyuki; Makino, Hitoshi; Takase, H.; Mckinley, I.G.; Okubo, H.

    2008-01-01

    JAEA is developing a 'Knowledge Management System' for vast quantities of data or information arising from various sources relevant to the geological disposal programs in Japan. The geological disposal project is taking a stepwise approach to selecting a disposal site and, to the approval and licensing, construction, operation and closure of a repository. It is a long-term project required approximately 100 years. In this paper, in order to structuralize, as knowledge, the results of R and D on geological disposal technologies of high-level radioactive wastes, the knowledge management approach was first reviewed. The paper is followed by descriptions of the technical characteristics, procedure to carry out a plan, and education of geological disposal technologies such as knowledge management etc. The structuring of the knowledge base and the knowledge management system including the construction of safety case were described. (S. Ohno)

  14. Human resource development for the new nuclear power plant unit in Armenia

    Gevorgyan, A.; Galstyan, A.; Donovan, M.

    2008-01-01

    This paper presents a discussion of a study to define the programs for development of the human resource infrastructure needed for a new nuclear power plant unit in the Republic of Armenia. While Armenia has a workforce experienced in operation and regulation of a nuclear power plant (NPP), a significant portion of the current Armenia Nuclear Power Plant (ANPP) workforce is approaching retirement age and will not be available for the new plant. The Government of Armenia is performing a human resource infrastructure study in cooperation with the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), sponsored by the JAEA. The study of Human Resource Development for Armenia uses the INPRO methodology for assessment of human resources. The results of this study will provide the basis for decisions on human resource development programs for nuclear power in Armenia and provide a model for countries with the limited resources that are working to develop nuclear energy in the future. (authors)

  15. Research on the state-of-the-art of probabilistic safety assessment for non-reactor nuclear facilities (1)

    Yoshida, Kazuo; Abe, Hitoshi; Yamane, Yuichi; Tashiro, Sinsuke; Muramatsu, Ken

    2007-02-01

    Japan Atomic Energy Agency (JAEA) entrusted with research on the state-of-the-art of probabilistic safety assessment (PSA) for non-reactor nuclear facilities (NRNF) to the Atomic Energy Society of Japan (AESJ). The objectives of this research is to obtain the basic useful information related for establishing the quantitative performance requirement and for risk-informed regulation through qualifying issues needed to be resolved for applying PSA to NRNF. A special committee of 'research on the analysis methods for accident consequence in NFRF' was organized in the AESJ. The research activities of the committee were mainly focused on the analysis method for upper bounding consequences of accidents such as events of criticality, explosion, fire and solvent boiling postulated in NRNF resulting in release of radio active material to the environment. (author)

  16. Large-scale visualization system for grid environment

    Suzuki, Yoshio

    2007-01-01

    Center for Computational Science and E-systems of Japan Atomic Energy Agency (CCSE/JAEA) has been conducting R and Ds of distributed computing (grid computing) environments: Seamless Thinking Aid (STA), Information Technology Based Laboratory (ITBL) and Atomic Energy Grid InfraStructure (AEGIS). In these R and Ds, we have developed the visualization technology suitable for the distributed computing environment. As one of the visualization tools, we have developed the Parallel Support Toolkit (PST) which can execute the visualization process parallely on a computer. Now, we improve PST to be executable simultaneously on multiple heterogeneous computers using Seamless Thinking Aid Message Passing Interface (STAMPI). STAMPI, we have developed in these R and Ds, is the MPI library executable on a heterogeneous computing environment. The improvement realizes the visualization of extremely large-scale data and enables more efficient visualization processes in a distributed computing environment. (author)

  17. Ni-rich precipitates in a lead bismuth eutectic loop

    Kikuchi, K.; Saito, S.; Hamaguchi, D.; Tezuka, M.

    2010-01-01

    Solidified LBE was sampled from the specimens, electro-magnetic pump, filter, drain valve and oxygen sensor at the JAEA Lead Bismuth Loop-1 (JLBL-1) where the structural material was made of SS316. The concentration of Ni, Fe and Cr in LBE were analyzed by the Inductive Coupled Plasma atomic emission spectrometer. It was concluded that the solution of Ni into LBE was not saturated although the concentration of Fe and Cr almost achieved to the values in the literature. A needle-type structure appeared on the surface of solidified LBE inside the tube specimens. It was found to be Ni-rich precipitates by X-ray analyses (Field Emission Scanning Electron Microscope, FE-SEM). LBE samples collected from a circulating loop after discharging did not show the amount of impurities equivalent to the LBE bulk property.

  18. Ni-rich precipitates in a lead bismuth eutectic loop

    Kikuchi, K., E-mail: kikuchik@mx.ibaraki.ac.j [Ibaraki University, IQBRC, Tokai, Ibaraki 319-1106 (Japan); Saito, S.; Hamaguchi, D.; Tezuka, M. [J-PARC Center, JAEA, Tokai, Ibaraki 319-1195 (Japan)

    2010-03-15

    Solidified LBE was sampled from the specimens, electro-magnetic pump, filter, drain valve and oxygen sensor at the JAEA Lead Bismuth Loop-1 (JLBL-1) where the structural material was made of SS316. The concentration of Ni, Fe and Cr in LBE were analyzed by the Inductive Coupled Plasma atomic emission spectrometer. It was concluded that the solution of Ni into LBE was not saturated although the concentration of Fe and Cr almost achieved to the values in the literature. A needle-type structure appeared on the surface of solidified LBE inside the tube specimens. It was found to be Ni-rich precipitates by X-ray analyses (Field Emission Scanning Electron Microscope, FE-SEM). LBE samples collected from a circulating loop after discharging did not show the amount of impurities equivalent to the LBE bulk property.

  19. Ni-rich precipitates in a lead bismuth eutectic loop

    Kikuchi, K.; Saito, S.; Hamaguchi, D.; Tezuka, M.

    2010-03-01

    Solidified LBE was sampled from the specimens, electro-magnetic pump, filter, drain valve and oxygen sensor at the JAEA Lead Bismuth Loop-1 (JLBL-1) where the structural material was made of SS316. The concentration of Ni, Fe and Cr in LBE were analyzed by the Inductive Coupled Plasma atomic emission spectrometer. It was concluded that the solution of Ni into LBE was not saturated although the concentration of Fe and Cr almost achieved to the values in the literature. A needle-type structure appeared on the surface of solidified LBE inside the tube specimens. It was found to be Ni-rich precipitates by X-ray analyses (Field Emission Scanning Electron Microscope, FE-SEM). LBE samples collected from a circulating loop after discharging did not show the amount of impurities equivalent to the LBE bulk property.

  20. Applications of CR-39 solid state nuclear track detector to ion beam diagnosis

    Kanasaki, Masato; Hattori, Atsuto; Oda, Keiji; Yamauchi, Tomoya; Fukuda, Yuji; Sakaki, Hironao; Nishiuchi, Mamiko; Kondo, Kiminori; Kurashima, Satoshi; Kamiya, Tomihiro

    2012-01-01

    CR-39 solid state nuclear track detector, which was developed for optical lens, has been applied for various field such as radon surveys, measurement of galactic cosmic ray, cell irradiation experiment and so on. The CR-39 detectors have the great advantages of being insensitive to high energy photons and electrons and capable of detecting only ions in the mixed fields such as laser driven relativistic plasmas. Though there are some analytical methods of CR-39 to diagnose ion beam, unfortunately, only few researchers in the field of plasma know the methods. This article looks at how to use CR-39 detectors and introduce the accomplishment of the joint study JAEA and Kobe Univ. for application of CR-39 detectors to ion beam diagnosis. (author)

  1. Annual report of R and D activities in Center for Computational Science and e-Systems from April 1, 2009 to March 31, 2010

    2011-10-01

    This report overviews the activity of research and development (R and D) in Center for Computational Science and e-Systems (CCSE) of the Japan Atomic Energy Agency (JAEA), during the fiscal year 2009 (April 1, 2009 - March 31, 2010). The work has been accomplished by the Simulation Technology R and D Office and Computer Science R and D Office in CCSE. The activity includes researches of secure computational infrastructure for the use in atomic energy research, which is based on the grid technology, a seismic response analysis for the structure of nuclear power plants, materials science, and quantum bioinformatics. The materials science research includes large scale atomic and subatomic simulations of nuclear fuels and materials for safety assessment, large scale quantum simulations of superconductor for the design of new devices and fundamental understanding of superconductivity. The quantum bioinformatics research focuses on the development of technology for large scale atomic simulations of proteins. (author)

  2. Evaluation of sorption distribution coefficient of Cs onto granite using sorption data collected in sorption database and sorption model

    Nagasaki, S.

    2013-01-01

    Based on the sorption distribution coefficients (K d ) of Cs onto granite collected from the JAERI Sorption Database (SDB), the parameters for a two-site model without the triple-layer structure were optimized. Comparing the experimentally measured K d values of Cs onto Mizunami granite carried out by JAEA with the K d values predicted by the model, the effect of the ionic strength on the K d values of Cs onto granite was evaluated. It was found that K d values could be determined using the content of biotite in granite at a sodium concentration ([Na]) of 1 x 10 -2 to 5 x 10 -1 mol/dm 3 . It was suggested that in high ionic strength solutions, the sorption of Cs onto other minerals such as microcline should also be taken into account. (author)

  3. Evaluation of sorption distribution coefficient of Cs onto granite using sorption data collected in sorption database and sorption model

    Nagasaki, S., E-mail: nagasas@mcmaster.ca [McMaster Univ., Hamilton, Ontario (Canada)

    2013-07-01

    Based on the sorption distribution coefficients (K{sub d}) of Cs onto granite collected from the JAERI Sorption Database (SDB), the parameters for a two-site model without the triple-layer structure were optimized. Comparing the experimentally measured K{sub d} values of Cs onto Mizunami granite carried out by JAEA with the K{sub d} values predicted by the model, the effect of the ionic strength on the K{sub d} values of Cs onto granite was evaluated. It was found that K{sub d} values could be determined using the content of biotite in granite at a sodium concentration ([Na]) of 1 x 10{sup -2} to 5 x 10{sup -1} mol/dm{sup 3} . It was suggested that in high ionic strength solutions, the sorption of Cs onto other minerals such as microcline should also be taken into account. (author)

  4. Investigation for calculation methods used in analyzing the physics characteristics of nuclear power reactor

    Nguyen Tuan Khai; Hoang Van Khanh; Phan Quoc Vuong; Tran Viet Phu; Tran Vinh Thanh; Nguyen Thi Mai Huong; Nguyen Thi Dung; Le Tran Chung; Nguyen Minh Tuan; Tran Quoc Duong

    2014-01-01

    The project aims at nuclear human resource development and enhancement in research capability in reactor physics and kinetics at Nuclear Energy Center (Institute for Nuclear Science and Technology) and Nuclear Reactor Center (Nuclear Research Institute, Dalat). The main research items of the project can be summarized as follows: i) Considering possibility on using modern calculation techniques and methods in investigating neutronic characteristics and neutronics-thermal hydraulics coupling. This item is proposed to carry out based on international collaboration with Prof. Le Trong Thuy, San Jose University, US; ii) Carrying out the collaborative activities in research and training between Nuclear Energy Center (Institute for Nuclear Science and Technology) and Nuclear Reactor Center (Nuclear Research Institute, Dalat); iii) Opening two-week training course on nuclear reactor engineering (25 Nov - 12 Dec 2013) in collaboration with Japan Atomic Energy Agency (JAEA). (author)

  5. Atmospheric models in the numerical simulation system (SPEEDI-MP) for environmental studies

    Nagai, Haruyasu; Terada, Hiroaki

    2007-01-01

    As a nuclear emergency response system, numerical models to predict the atmospheric dispersion of radionuclides have been developed at Japan Atomic Energy Agency (JAEA). Evolving these models by incorporating new schemes for physical processes and up-to-date computational technologies, a numerical simulation system, which consists of dynamical models and material transport models for the atmospheric, terrestrial, and oceanic environments, has been constructed to apply for various environmental studies. In this system, the combination of a non-hydrostatic atmospheric dynamic model and Lagrangian particle dispersion model is used for the emergency response system. The utilization of detailed meteorological field by the atmospheric model improves the model performance for diffusion and deposition calculations. It also calculates a large area domain with coarse resolution and local area domain with high resolution simultaneously. The performance of new model system was evaluated using measurements of surface deposition of 137 Cs over Europe during the Chernobyl accident. (author)

  6. Microstructural evolution and Am migration behaviour in Am-containing fuels at the initial stage of irradiation

    Tanaka, Kosuke; Miwa, Shuhei; Sato, Isamu; Osaka, Masahiko; Hirosawa, Takashi; Obayashi, Hiroshi; Koyama, Shin-ichi; Yoshimochi, Hiroshi; Tanaka, Kenya

    2010-01-01

    In order to investigate the effect of americium addition to MOX fuels on the irradiation behaviour, the 'Am-1' programme is being conducted in JAEA. The Am-1 programme consists of two short-term irradiation tests of 10-minute and 24-hour irradiations and a steady-state irradiation test. The short-term irradiation tests were successfully completed and the post-irradiation examinations (PIE) are in progress. The PIE for Am-containing MOX fuels focused on the microstructural evolution and redistribution behaviour of Am at the initial stage of irradiation and the results to date are reported. The successful development of fabrication technology with remote handling and the evaluation of thermo-chemical properties based on the out-of-pile experiments are described with an emphasis on the effects of Am addition on the MOX fuel properties. (authors)

  7. Decommissioning engineering systems for nuclear facilities and knowledge inheritance for decommissioning of nuclear facilities

    Tachibana, Mitsuo

    2016-01-01

    Information on construction, operation and maintenance of a nuclear facility is essential in order to plan and implement the decommissioning of the nuclear facility. A decommissioning engineering system collects these information efficiently, retrieves necessary information rapidly, and support to plan the reasonable decommissioning as well as the systematic implementation of dismantling activities. Then, knowledge of workers involved facility operation and dismantling activities is important because decommissioning of nuclear facility will be carried out for a long period. Knowledge inheritance for decommissioning has been carried out in various organizations. This report describes an outline of and experiences in applying decommissioning engineering systems in JAEA and activities related to knowledge inheritance for decommissioning in some organizations. (author)

  8. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2009

    2014-02-01

    JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment in the nuclear reactor training, Practice of Reactor operation, Irradiation for activation analyses, RI productions, fission tracks, etc. In the fiscal year 2009, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 6 cycles (daily operation : 24 days). The volume contains 138 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, prompt gamma-ray analyses, neutron activation analyses, RI productions, and others submitted by the users in JAEA and from other organizations. (author)

  9. Development of advanced loop-type fast reactor in Japan (4): An advanced design of the fuel handling system for the enhanced economic competitiveness

    Usui, S.; Mihara, T.; Obata, H.; Kotake, S.

    2008-01-01

    Refueling operation of sodium fast reactor (SFR) is one of major technical issue due to the chemical activities and opaqueness of sodium coolant properties in comparison with that of LWR. In the Japan Atomic Energy Agency (JAEA) sodium cooled Fast Reactor (JSFR) design study, the further reliable and rational fuel handling system (FHS) has been developing based on the experience of safe and reliable fuel handling operation in the existent SFR plants. Some of advanced concepts for the FHS have being studied in order to increase economic competitiveness further by attempting reduction of the amount of the material and the refueling time, and are scheduled to execute elemental tests and/or mock-up tests to confirm their feasibilities. (authors)

  10. After Action Report - CUP-2 Comparative Sample Analysis Meeting - Kazakhstan September 2016

    Kips, Ruth [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lindvall, Rachel [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Eppich, Gary [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Oujo, Kaitlin [National Nuclear Security Administration (NNSA), Washington, DC (United States); Geist, William [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-01

    Representatives from the U.S. Department of Energy’s Office of Nuclear Smuggling Detection and Deterrence (NSDD) visited the Kazakhstan Institute of Nuclear Physics (INP) to discuss the results and conclusions of a joint sample analysis (CUP-2 uranium ore concentrate) between LLNL, INP and the Japan Atomic Energy Agency (JAEA) (Fig. 1). The U.S. delegation also met with the newly-appointed Director-General of the INP (S. Sakhiyev) who expressed his continued support for this collaboration. On the last day of the visit, the delegation toured the new medical isotope production facilities (which is expected to begin operation in a few months), as well as INP’s Nuclear Security Training Center (co-funded by DOE, the Defense Threat Reduction Initiative (DTRA) and the Kazakhstan government). Construction of the Nuclear Security Training Center is expected to be completed by the end of 2016.

  11. Application of micro-PIXE and imaging technology to life science (Joint research)

    Satoh, Takahiro; Ishii, Keizo

    2011-03-01

    The joint research on 'Application of micro-PIXE and imaging technology to life science' supported by the Inter-organizational Atomic Energy Research Program, had been performed for three years, from 2006FY to 2009FY. Aiming to apply in-air micro-PIXE analytical system to life science, the research was consisting of 7 collaborative themes related to beam engineering for micro-PIXE and applied technology of element mapping in biological/medical fields. The system, so-called micro-PIXE camera, to acquire spatial element mapping in living cells was originally developed by collaborative research between the JAEA and the department of engineering of Tohoku University. This review covers these research results. (author)

  12. Activities of special committee on 'quality assurance of accountancy analysis for safeguards'

    2010-01-01

    For the long-term stable operation of nuclear fuel cycle facilities, it is essential to satisfy the requirements of IAEA safeguards agreement. It could be attained by precise implementation of accountancy analysis of nuclear materials and application of Destructive Analysis (DA) which enables highly precise measurement is necessary. The requirements to maintain and improve the precision of DA are supposed to grow along with nuclear fuel cycle fully in progress and Pu handling amount increases. In order to maintain long-term stability of quality level of accountancy analysis for safeguards, a special committee on 'Quality Assurance (QA) for Accountancy /Safeguards analysis' was established at Atomic Energy Society Japan supported by INNM-Japan Chapter. Experts of safeguards analysis, reference materials, statistics and QA were gathered and drafted the committee standard document for isotope dilution mass spectrometry, the major accountancy analysis technique for Pu and U, supported Pu standard preparation at JAEA and summarized the items needed for QA of DA. (author)

  13. In-Pile Tests for IASCC Growth Behavior of Irradiated 316L Stainless Steel under Simulated BWR Condition in JMTR

    Chimi, Yasuhiro; Kasahara, Shigeki; Ise, Hideo; Kawaguchi, Yoshihiko; Nakano, Junichi; Nishiyama, Yutaka

    The Japan Atomic Energy Agency (JAEA) has an in-pile irradiation test plan to evaluate in-situ effects of neutron/γ-ray irradiation on stress corrosion crack (SCC) growth of irradiated stainless steels using the Japan Materials Testing Reactor (JMTR). SCC growth rate and its dependence on electrochemical corrosion potential (ECP) are different between in-pile test and post irradiation examination (PIE). These differences are not fully understood because of a lack of in-pile data. This paper presents a systematic review on SCC growth data of irradiated stainless steels, an in-pile test plan for crack growth of irradiated SUS316L stainless steel under simulated BWR conditions in the JMTR, and the development of the in-pile test techniques.

  14. Introduction

    Lanaro, Flavio

    2008-01-01

    This chapter illustrates the role of JAEA in conducting Research and Development on deep geological disposal of nuclear waste, on the reliability of the disposal technology and on safety assessment methods. Within this frame, the present study seeks a better understanding of the influence of the in-situ conditions on the sampling process through the analysis of sample damage. The correlation between sample damage and in-situ stress conditions provides a tool for correction of the laboratory test results and for predicting stresses and in-situ mechanical properties of the Toki granite at the MIU Construction Site (Mizunami, Gifu Pref., Japan). This study of the literature, sample conditions, available laboratory results and numerical models will lead to the proposal of a statistical method based on fractal geometry for quantifying cracking and fracturing in brittle rocks and describing its dependence on the level of stress. (author)

  15. Core Calculation of 1 MWatt PUSPATI TRIGA Reactor (RTP) using Monte Carlo MVP Code System

    Karim, Julia Abdul

    2008-05-01

    The Monte Carlo MVP code system was adopted for the Reaktor TRIGA PUSAPTI (RTP) core calculation. The code was developed by a group of researcher of Japan Atomic Energy Agency (JAEA) first in 1994. MVP is a general multi-purpose Monte Carlo code for neutron and photon transport calculation and able to estimate an accurate simulation problems. The code calculation is based on the continuous energy method. This code is capable of adopting an accurate physics model, geometry description and variance reduction technique faster than conventional method as compared to the conventional scalar method. This code could achieve higher computational speed by several factors on the vector super-computer. In this calculation, RTP core was modeled as close as possible to the real core and results of keff flux, fission densities and others were obtained.

  16. Core Calculation of 1 MWatt PUSPATI TRIGA Reactor (RTP) using Monte Carlo MVP Code System

    Karim, Julia Abdul

    2008-01-01

    The Monte Carlo MVP code system was adopted for the Reaktor TRIGA PUSAPTI (RTP) core calculation. The code was developed by a group of researcher of Japan Atomic Energy Agency (JAEA) first in 1994. MVP is a general multi-purpose Monte Carlo code for neutron and photon transport calculation and able to estimate an accurate simulation problems. The code calculation is based on the continuous energy method. This code is capable of adopting an accurate physics model, geometry description and variance reduction technique faster than conventional method as compared to the conventional scalar method. This code could achieve higher computational speed by several factors on the vector super-computer. In this calculation, RTP core was modeled as close as possible to the real core and results of keff flux, fission densities and others were obtained

  17. Sulfur-Iodine Integrated Lab Scale Experiment Development

    Russ, Ben

    2011-05-27

    The sulfur-iodine (SI) cycle was deermined to be the best cycle for coupling to a high temperature reactor (HTR) because of its high efficiency and potential for further improvement. The Japanese Atomic Energy Agency (JAEA) has also selected the SI process for further development and has successfully completed bench-scale demonstrations of the SI process at atmospheric pressure. JEA also plans to proceed with pilot-scale demonstrations of the SI process and eventually plans to couple an SI demonstration plant to its High Temperature Test Reactor (HHTR). As part of an international NERI project, GA, SNL, and the Frech Commissariat L'Energie Atomique performed laboratory-scale demonstrations of the SI process at prototypical temperatures and pressures. This demonstration was performed at GA in San Diego, CA and concluded in April 2009.

  18. Annual report of R and D activities in Center for Computational Science and e-Systems from April 1, 2007 to March 31, 2009

    2010-01-01

    This report provides an overview of research and development activities in Center for Computational Science and e-Systems (CCSE), JAEA, during the fiscal years 2007 and 2008 (Apr 1, 2007 - March 31, 2009). These research and development activities have been performed by the Simulation Technology R and D Office and Computer Science R and D Office. These activities include development of secure computational infrastructure for atomic energy research based on the grid technology, large scale seismic analysis of an entire nuclear reactor structure, large scale fluid dynamics simulation of J-PARC mercury target, large scale plasma simulation for nuclear fusion reactor, large scale atomic and subatomic simulations of nuclear fuels and materials for safety assessment, large scale quantum simulations of superconductor for the design of new devices and fundamental understanding of superconductivity, development of protein database for the identification of radiation-resistance gene, and large scale atomic simulation of proteins. (author)

  19. Implementation of the DIAC control system

    Chang, Dae-Sik; Jang, Doh-Yun; Jin, Jeong-Tae; Oh, Byung-Hoon [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    DIAC (Daejeon Ion Accelerator Complex) system was developed, and operated at JAEA of Japan by KEK team with a name of TRIAC (Tokai Radioactive Ion Accelerator Complex) during 2004 to 2010. The TRIAC control system was based on LabView and had two independent control units for ion source and accelerator. To be an efficient system, it is necessary to have an integrated control capability. And the control software, which had implemented by using LabView at TRIAC, will be changed with EPICS in order to give an effective beam service to the users. In this presentation, the old TRIAC control system is described, and a new control system for DIAC is discussed. The control system of DIAC is based on TRIAC. But it is gradually improved performance using EPICS toolkits and changing some digital interface hardware of it. Details of the control system will be demonstrated during the conference.

  20. Practical application of the KMS: 1) total system performance assessment - 16349

    Makino, Hitoshi; Hioki, Kazumasa; Umeki, Hiroyuki; Yang, Hongzhi; Takase, Hiroyasu; McKinley, Ian

    2009-01-01

    Comprehensive total system performance assessment (PA) is a key component of the safety case. Within this PA there are a number of tasks that reuse specific models and datasets, together with associated knowledge base for the disposal system considered. These are tasks where recent developments in the Knowledge Management System by Japan Atomic Energy Agency (JAEA KMS) can lead to optimisation of procedures. This paper will outline the reformulation of PA as a Knowledge Management (KM) task, discuss application of KM technologies to PA tasks, and illustrate how these can be handled electronically in a 'Performance assessment All-In-one Report System (PAIRS)' utilising hyper-links and embedded tools to minimise duplication of material, ease Quality Assurance (QA) and facilitate the regular updating required in the Japanese programme. (authors)

  1. Mutation induction of orchids by ion beams

    Affrida Abu Hassan; Zaiton Ahmad; Sakinah Ariffin; Oono, Yutaka; Hase, Yoshihiro; Shikazono; Naoya; Narumi, Issay; Tanaka, Atsushi

    2010-01-01

    Mutation induction using ionizing radiation provides an effective alternative means for improvement of orchids. In this study, ion beams were used because they have much higher linear energy transfer (LET) than X-rays or gamma rays, and subsequently lead to higher mutation frequency and broad mutation spectrum. The proto corm-like bodies (PLBs) of three orchid species (Dendrobium crumenatum, Dendrobium mirbellianum) were irradiated at various doses with 320 MeV 12 C 6+ ions accelerated by Azimuthally Varying Field (AVF) cyclotron at JAEAs Takasaki Ion Accelerators for Advanced Radiation Application (TIARA). The optimum irradiation condition and the effect of irradiation on each species were studied, particularly on flower colour and morphology, flowering habit and insect resistance. Dose effects on plantlet regeneration for each species were also obtained. Some morphological changes were observed in flowers of Dendrobium crumenatum, whilst one insect resistant mutant was obtained in Dendrobium mirbellianum. (author)

  2. Review of the international forum on peaceful use of nuclear energy and nuclear security. Taking the lessons learned from Fukushima Daiichi Nuclear Power Plant accident to the 2012 Seoul nuclear security summit

    Tazaki, Makiko; Suda, Kazunori; Suzuki, Mitsutoshi; Kuno, Yusuke; Mochiji, Toshiro

    2012-06-01

    The Japan Atomic Energy Agency (JAEA) held '2011 International Forum on the Peaceful Use of Nuclear Energy and Nuclear Security - Taking the lessons learned from Fukushima Daiichi Nuclear Power Plant Accident to the 2012 Seoul Nuclear Security Summit-' on 8 and 9 December, 2011. It intended to articulate effective strategies and measures for strengthening nuclear security using lessons learned from the Fukushima Nuclear Accident. Moreover, it was expected to explore comprehensive approaches which could contribute to enhancing both nuclear safety and security in order to support sustainable and appropriate development of the peaceful use of nuclear energy. This report includes abstracts of keynote speeches, summary of panel discussions and materials of the presentations in the forum. The editors take full responsibility for the wording and content of this report, excepts presentation materials. (author)

  3. Annual report for research on geosphere stability for long-term isolation of radioactive waste in fiscal years 2012

    Yasue, Ken-ichi; Asamori, Koichi; Niwa, Masakazu; Hanamuro, Takahiro; Saito-Kokubu, Yoko; Sueoka, Shigeru; Makuuchi, Ayumu; Ikuta, Masafumi; Matsubara, Akihiro; Tamura, Hajimu; Kobori, Kazuo; Ishimaru, Tsuneari; Umeda, Koji

    2014-03-01

    This annual report documents the progress of R and D in the 3rd fiscal year during the JAEA 2nd Midterm Plan (FY 2010 - 2014) to provide the scientific base for assessing geosphere stability for long-term isolation of the high-level radioactive waste. The planned framework is structured into the following categories: 1) development and systematization of investigation techniques for selecting suitable sites in geosphere stability, 2) development, application and verification of prediction models for evaluating the changes of geological environment in thermal, hydraulic, mechanical and geochemical conditions for a long period of time, and 3) development of new dating techniques for providing information about geologic history and the timing of geologic events. In this report, the current status of R and D activities with previous scientific and technological progress is summarized. (author)

  4. Present status of research reactor and future prospects

    Nakajima, Ken

    2013-01-01

    Research reactors have been playing an important role in the research and development of the various fields, such as physics, chemistry, biology, engineering, agriculture, medicine, etc. as well as human resource development. However, the most of them are older than 40 years, and the ageing management is an important issue. In Japan, only two research reactors are operational after the Great East Japan Earthquake in 2011. JAEA's reactors suffered from the quake and they are under inspections. Kyoto University Research Reactor, one of the operational reactors, has been widely used for research and human resource development, and the additional safety measures against the station blackout were installed. Besides the affect of the quake, the disposal or treatment of spent fuel becomes an inevitable problem for research reactors. The way of spent fuel disposal or treatment should be determined with the nation-wide and/or international coalition. (author)

  5. Development of a single-shot-imaging thin film for an online Thomson parabola spectrometer

    Sakaki, H.; Fukuda, Y.; Nishiuchi, M.; Hori, T.; Yogo, A.; Jinno, S.; Kanasaki, M.; Niita, K.

    2013-01-01

    A single-shot-imaging thin scintillator film was developed for an online Thomson parabola (TP) spectrometer and the first analysis of laser accelerated ions, using the online TP spectrometer, was demonstrated at the JAEA-Kansai Advanced Relativistic Engineering Laser System (J-KAREN). An energy spectrum of ∼4.0 MeV protons is obtained using only this imaging film without the need of a microchannel plate that is typically utilized in online ion analyses. A general-purpose Monte Carlo particle and heavy ion-transport code system, which consists of various quantum dynamics models, was used for the prediction of the luminescent properties of the scintillator. The simulation can reasonably predict not only the ion trajectories detected by the spectrometer, but also luminescence properties.

  6. Conceptual study of nuclear power generation facilities life-cycle support versatile engineering database. Procedure of development and consideration of fundamental functions

    Endo, Hidetoshi

    2009-05-01

    International Atomic Energy Agency (IAEA) stands out the activity of the knowledge management of nuclear safety and the movement to introduce the idea of the life cycle management into the quality control of maintenance of the nuclear power generation facilities to assure the knowledge preservation and to succeed the technology of facilities. Japan Atomic Energy Agency (JAEA) also has such activities as the knowledge preservation of research and development, and related information. The facilities' performance reliability can be easily checked with the technology of data processing in the general industry and the results of the knowledge repository, transmitting technology and knowledge management by referring to the information and knowledge if the information and knowledge at each step of the life-cycle of facilities can be built. This report shows the strategy of the construction of the engineering database to support the life cycle of facilities and the basic function of the management system. (author)

  7. Improvement in oil seal performance of gas compressor in HTTR

    Oyama, Sunao; Hamamoto, Shimpei; Nemoto, Takahiro; Sekita, Kenji; Isozaki, Minoru; Emori, Kouichi; Ohta, Yukimaru; Mizushima, Toshihiko; Kaneshiro, Noriyuki; Ito, Yoshiteru; Yamamoto, Hideo

    2007-08-01

    High-Temperature engineering Test Reactor (HTTR) built by Japan Atomic Energy Agency (JAEA) has reciprocating compressor commonly used to extract and discharge helium gas into primary/secondary coolant helium loop from helium purification system. Piston rod seal of the compressor consist of several components to prevent coolant leak. However, rod seal system has weak reliability during long term operation due to repeated leakage of seal oil in operation. As a result of investigations, leakage's root is found in that seal were used in a range beyond limit sliding properties of seal material. For this reason, a lip of the seal was worn and transformed itself and was not able to sustain a seal function. Therefore, through tests using facility actual equipment for endurance of candidate materials, one seal material were chosen for long term operation. (author)

  8. Development of virtual private network for JT-60SA CAD integration

    Oshima, Takayuki; Fujita, Takaaki; Seki, Masami; Kawashima, Hisato; Hoshino, Katsumichi; Shibanuma, Kiyoshi; Verrecchia, M.; Teuchner, B.

    2010-01-01

    The CAD models will be exchanged and integrated at Naka for JT-60SA, a common computer network efficiently connected between Naka site and the Garching site is needed to be established. Virtual Private Network (VPN) was introduced with LAN on computer network physically-separated from JAEA intranet area and firewall. In July 2009, a new VPN connection between the Naka and Garching sites has been successfully demonstrated using IPSec-VPN technology with a commercial and cost-effective firewall/router for security. It was found that the introduction of the Wide Area File Service (WAFS) could solve the issue of the data transmission time and enhance the usability of the VPN for design integration in JT-60SA. (author)

  9. Evaluating and categorizing the reliability of distribution coefficient values in the sorption database

    Ochs, Michael; Saito, Yoshihiko; Kitamura, Akira; Shibata, Masahiro; Sasamoto, Hiroshi; Yui, Mikazu

    2007-03-01

    Japan Atomic Energy Agency (JAEA) has developed the sorption database (JNC-SDB) for bentonite and rocks in order to assess the retardation property of important radioactive elements in natural and engineered barriers in the H12 report. The database includes distribution coefficient (K d ) of important radionuclides. The K d values in the SDB are about 20,000 data. The SDB includes a great variety of K d and additional key information from many different literatures. Accordingly, the classification guideline and classification system were developed in order to evaluate the reliability of each K d value (Th, Pa, U, Np, Pu, Am, Cm, Cs, Ra, Se, Tc on bentonite). The reliability of 3740 K d values are evaluated and categorized. (author)

  10. Test plan using the HTTR for commercialization of GTHTR300C

    Tachibana, Yukio; Sakaba, Nariaki; Ohashi, Hirofumi; Sato, Hiroyuki; Ueta, Shohei; Aihara, Jun; Goto, Minoru; Sumita, Junya; Shibata, Taiju; Takamatsu, Kuniyoshi; Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; Nishihara, Tetsuo; Hamamoto, Shimpei; Iyoku, Tatsuo

    2010-02-01

    The High Temperature Engineering Test Reactor (HTTR) is the first High Temperature Gas-cooled Reactor (HTGR) built at the Oarai Research and Development Center of JAEA with thermal power of 30 MW and the maximum reactor outlet coolant temperature of 950degC. The HTTR achieved the first criticality in 1998, the reactor outlet coolant temperature of 950degC in 2004, and 30 days continuous operation in 2007. Since 2002, safety demonstration tests including reactivity insertion tests and coolant flow reduction tests have been conducted to show inherent safety features of the HTGRs by using the HTTR. This report describes full scope of the future feasible test plan mainly using the HTTR. The test items cover fuel performance and radionuclide transport, core physics, reactor thermal hydraulics and plant dynamics, and reactor operations, maintenance, control, etc. The test results will be utilized for realization of Japan's commercial Very High Temperature Reactor (VHTR) system, GTHTR300C. (author)

  11. Development and verification of remote research environment based on 'Fusion research grid'

    Iba, Katsuyuki; Ozeki, Takahisa; Totsuka, Toshiyuki; Suzuki, Yoshio; Oshima, Takayuki; Sakata, Shinya; Sato, Minoru; Suzuki, Mitsuhiro; Hamamatsu, Kiyotaka; Kiyono, Kimihiro

    2008-01-01

    'Fusion research grid' is a concept that unites scientists and let them collaborate effectively against their difference in time zone and location in a nuclear fusion research. Fundamental technologies of 'Fusion research grid' have been developed at JAEA in the VizGrid project under the e-Japan project at the Ministry of Education, Culture, Sports, Science and Technology (MEXT). We are conscious of needs to create new systems that assist researchers with their research activities because remote collaborations have been increasing in international projects. Therefore we have developed prototype remote research environments for experiments, diagnostics, analyses and communications based on 'Fusion research grid'. All users can access these environments from anywhere because 'Fusion research grid' does not require a closed network like Super SINET to maintain security. The prototype systems were verified in experiments at JT-60U and their availability was confirmed

  12. Generation of laser Compton gamma-rays using Compact ERL

    Shizuma, Toshiyuki; Hajima, Ryoichi; Nagai, Ryoji; Hayakawa, Takehito; Mori, Michiaki; Seya, Michio

    2015-01-01

    Nondestructive isotope-specific assay system using nuclear resonance fluorescence has been developed at JAEA. In this system, intense, mono-energetic laser Compton scattering (LCS) gamma-rays are generated by combining an energy recovery linac (ERL) and laser enhancement cavity. As technical development for such an intense gamma-ray source, we demonstrated generation of LCS gamma-rays using Compact ERL (supported by the Ministry of Education, Culture, Sports, Science and Technology) developed in collaboration with KEK. We also measured X-ray fluorescence for elements near iron region by using mono-energetic LCS gamma-rays. In this presentation, we will show results of the experiment and future plan. (author)

  13. Customer Acceptance Survey On Chrysanthemum Mutant Developed By Nuclear Malaysia

    Shakinah Salleh; Zaiton Ahmad; Affrida Hassan; Shuhaimi Shamsudin; Nurul Hidayah Mahmud; Salim Othman; Mohamed Najli Mohamed Yasin

    2014-01-01

    Chrysanthemum morifolium is an important temperate cut flower for Malaysian floriculture industry and the lack of new local-owned varieties has led to this mutation breeding research. The project was started in 2008 under bilateral cooperation between Nuclear Malaysia and JAEA (Japan Atomic Energy Agency). Through this project, 8 new varieties of chrysanthemum were successfully developed, in which 4 varieties were from red cultivar and another 4 from pink cultivar. A preliminary survey on public perception and acceptance of these mutants was conducted on 7 January 2014 at Agrotechnology and Biosciences Division, Malaysian Nuclear Agency. The main objective of this survey was to gather information from the public on overall appearance of these new varieties and their potential for commercialization. Approximately 60 participants were involved in this survey, which include staff of Nuclear Malaysia, university students, plant growers/collectors and hobbyists. (author)

  14. Proceedings of the workshop on 'anomalous electronic states and physical properties in high-temperature superconductors'

    Arai, Masatoshi; Kajimoto, Ryoichi

    2007-03-01

    A workshop entitled 'Anomalous Electronic States and Physical Properties in High-Temperature Superconductors' was held on November 7-8, 2006 at Institute for Materials Research, Tohoku University. In the workshop, leading scientists in the field of high-T c superconductivity, both experimentalists and theorists, gathered in a hall to report the recent progress of the study, clarify the problems to be solved, and discuss the future prospects. The workshop was jointly organized by Specially Promoted Research of MEXT, Development of the 4D Spaces Access Neutron Spectrometer and Elucidation of the Mechanism of Oxide High-T c Superconductivity' (repr. by M. Arai, JAEA) and by the Inter-university Cooperative Research Program of the Institute for Materials Research, Tohoku University, 'Anomalous Electronic States and Physical Properties in High-Temperature Superconductors' (repr. by T. Tohyama, Kyoto Univ.). This report includes abstracts and materials of the presentations in the workshop. (author)

  15. Activities of the nuclear emergency assistance and training center. Strengthening co-operation with parties in normal circumstances

    Watanabe, Fumitaka; Matsui, Tomoaki; Nomura, Tamotsu

    2005-01-01

    The Japan Nuclear Cycle Development Institute (JNC) and the Japan Atomic Energy Research Institute (JAERI) established the Nuclear Emergency Assistance and Training Center (NEAT) in March 2002. The center aims to provide various support nuclear safety regulatory bodies, local governments and nuclear facility licenses as specialists about nuclear and radiological issues according to the role shown in the Basic Disaster Management Plan. Upon a nuclear and/or radiological disaster occurring in Japan, NEAT will send specialists to the disaster scene, and offer the use of special equipments. NEAT maintains frequent contact with related organizations in normal circumstance. NEAT also participates in nuclear emergency exercises instructed by the parties concerned, which has contributed to the brewing of mutual trust with related organizations. In October 2005, JNC and JAERI merged into a new organization named the Japan Atomic Energy Agency (JAEA). NEAT, as a section of the organization, continuously deals with nuclear emergencies. (author)

  16. Recalibration of indium foil for personnel screening in criticality accidents.

    Takada, C; Tsujimura, N; Mikami, S

    2011-03-01

    At the Nuclear Fuel Cycle Engineering Laboratories of the Japan Atomic Energy Agency (JAEA), small pieces of indium foil incorporated into personal dosemeters have been used for personnel screening in criticality accidents. Irradiation tests of the badges were performed using the SILENE reactor to verify the calibration of the indium activation that had been made in the 1980s and to recalibrate them for simulated criticalities that would be the most likely to occur in the solution process line. In addition, Monte Carlo calculations of the indium activation using the badge model were also made to complement the spectral dependence. The results lead to a screening level of 15 kcpm being determined that corresponds to a total dose of 0.25 Gy, which is also applicable in posterior-anterior exposure. The recalibration based on the latest study will provide a sounder basis for the screening procedure in the event of a criticality accident.

  17. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2005

    2007-03-01

    In the fiscal year 2005, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 37 cycles (daily operation : 137 days). JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography. Irradiation for activation analyses, radioisotope (RI) productions, fission tracks. Irradiation test of reactor materials etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT). Prompt gamma-ray analyses. Sensitivity measurement of radiation detectors. Experiment in the nuclear reactor training. Practice of Reactor operation. Irradiation for activation analyses, RI productions, fission tracks etc. The volume contains 100 activity reports, which are categorized into the fields of neutron scattering (9 subcategories), neutron radiography, neutron activation analyses, RI productions, prompt gamma-ray analyses, and others submitted by the users in JAEA and from other organizations. (author)

  18. A proposal for safety design philosophy of HTGR for coupling hydrogen production plant

    Sato, Hiroyuki; Ohashi, Hirofumi; Tazawa, Yujiro; Imai, Yoshiyuki; Nakagawa, Shigeaki; Tachibana, Yukio; Kunitomi, Kazuhiko

    2013-06-01

    Japan Atomic Energy Agency (JAEA) has been conducting research and development for hydrogen production utilizing heat from High Temperature Gas-cooled Reactors (HTGRs). Towards the realization of nuclear hydrogen production, coupled hydrogen production plants should not be treated as an extension of a nuclear plant in order to open the door for the entry of non-nuclear industries as well as assuring reactor safety against postulated abnormal events initiated in the hydrogen production plants. Since hydrogen production plant utilizing nuclear heat has never been built in the world, little attention has been given to the establishment of a safety design for such system including the High Temperature engineering Test Reactor (HTTR). In the present study, requirements in order to design, construct and operate hydrogen production plants under conventional chemical plant standards are identified. In addition, design considerations for safety design of nuclear facility are suggested. Furthermore, feasibility of proposed safety design and design considerations are evaluated. (author)

  19. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2007

    2012-03-01

    In the fiscal year 2007, the research reactor JRR-3 was operated for 7 cycles (cycle operation : 26days/cycle) and the JRR-4 was operated for 92 days. JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment and practice in the nuclear reactor training, Irradiation for activation analyses, RI productions, fission tracks, etc. The volume contains 262 activity reports, which are categorized into the fields of neutron scattering (10 subcategories), neutron radiography, neutron activation analyses, prompt gamma-ray analyses, and others submitted by the users in JAEA and other Organizations. (author)

  20. Research plan on geosphere stability for long-term isolation of radioactive waste. Scientific programme for fiscal years 2011

    Yasue, Ken-ichi; Asamori, Koichi; Kusano, Tomohiro; Saito-Kokubu, Yoko; Tanikawa, Shin-ichi; Niwa, Masakazu; Hanamuro, Takahiro; Yamasaki, Seiko; Yamada, Kunimi; Ishimaru, Tsuneari; Umeda, Koji

    2011-07-01

    The concept of geological disposal of HLW in Japan is based on a multi-barrier system which combines a stable geological environment with a robust barrier system. Potential geological host formations and their surroundings are chosen, in particular, for their long-term stability, taking into account the fact that Japan is located in a tectonically active zone. This report is a plan of research and development (R and D) on geosphere stability for long-term isolation of HLW in JAEA, in fiscal year 2011. The objectives and contents in fiscal year 2011 are described in detail based on the outline of 5 years plan (fiscal years 2010-2014). In addition, the planed framework is structured into the following categories: (1) Development and systematization of investigation techniques, (2) Development of models for long-term estimation and effective assessment, (3) Development of dating techniques. (author)

  1. Research plan on geosphere stability for long-term isolation of radioactive waste. Scientific programme for fiscal years 2012

    Asamori, Koichi; Niwa, Masakazu; Hanamuro, Takahiro; Yamada, Kunimi; Kusano, Tomohiro; Makuuchi, Ayumu; Takatori, Ryoichi; Saito-Kokubu, Yoko; Ishimaru, Tsuneari; Umeda, Koji

    2012-07-01

    The concept of geological disposal of HLW in Japan is based on a multi-barrier system which combines a stable geological environment with a robust barrier system. Potential geological host formations and their surroundings are chosen, in particular, for their long-term stability, taking into account the fact that Japan is located in a tectonically active zone. This report is a plan of research and development (R and D) on geosphere stability for long-term isolation of HLW in JAEA, in fiscal year 2012. The objectives and contents in fiscal year 2012 are described in detail based on the outline of 5 years plan (fiscal years 2010-2014). In addition, the planned framework is structured into the following categories: (1) Development and systematization of investigation techniques, (2) Development of models for long-term estimation and effective assessment, (3) Development of dating techniques. (author)

  2. Study of parameters for safety assessment of sub-surface disposal. Tunnel-excavating speed and thickness of additional soil in residential land development by filling

    Ishitoya, Kimihide; Sugaya, Toshikatsu; Funabashi, Hideyuki

    2012-02-01

    Japan Atomic Energy Agency (JAEA) is making preparations for the sub-surface disposal of own low level radioactive wastes. In order to carry out the disposal, it is necessary to confirm the safety of the disposal. Nuclear Safety Commission of Japan (NSC) issued 'Policy of the Safety Assessment of Sub-surface Disposal after the Period for Active Control' (April 1, 2010). Then, we investigated the parameters for dose assessment in tunnel excavation scenario and large-scale land use scenario which were described in the 'Policy of the Safety Assessment', in order to perform the assessment based on actual conditions. To be concrete, we investigated the tunnel excavating speeds in Japan for the former scenario, and investigated technical standards of the filling for the latter scenario. We studied the realistic parameters for the dose assessment with the results of those investigations. (author)

  3. Research plan on geosphere stability for long-term isolation of radioactive waste. Scientific programme for fiscal years 2010

    Yasue, Ken-ichi; Asamori, Koichi; Yamada, Kunimi; Saito-Kokubu, Yoko; Yamasaki, Seiko; Kurosawa, Hideki; Tanikawa, Shin-ichi; Negi, Tateyuki; Kusano, Tomohiro; Hanamuro, Takahiro; Ishimaru, Tsuneari; Umeda, Koji

    2010-09-01

    The concept of geological disposal of HLW in Japan is based on a multibarrier system which combines a stable geological environment with an engineered barrier system. Potential geological host formations and their surroundings are chosen, in particular, for their long-term stability, taking into account the fact that Japan is located in a tectonically active zone. This report is a plan of research and development (R and D) for geosphere stability for long-term isolation of HLW in JAEA, in fiscal year 2010. The objectives and contents in fiscal year 2010 are described in detail based on the outline of 5 years plan (fiscal years 2010-2014). In addition, the plan framework is structured into the following categories: (1) Development and systematization of investigation techniques, (2) Development of models for long-term estimation and effective assessment, (3) Development of dating techniques. (author)

  4. Mizunami Underground Research Laboratory project. Annual report for fiscal year 2007

    Nishio, Kazuhisa; Matsuoka, Toshiyuki; Tsuruta, Tadahiko; Amano, Kenji; Ohyama, Takuya; Takeuchi, Ryuji; Saegusa, Hiromitsu; Hama, Katsuhiro; Mizuno, Takashi; Sai, Masataka; Hirano, Toru; Iyatomi, Yosuke; Shimada, Akiomi; Matsui, Hiroya; Ogata, Nobuhisa; Uchida, Masahiro; Sugihara, Kozo; Mikake, Shinichiro; Ikeda, Koki; Yamamoto, Masaru

    2009-03-01

    Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is developing a geoscientific research project named Mizunami Underground Research Laboratory (MIU) Project in crystalline rock environment in order to establish scientific and technological basis for geological disposal of HLW. Geoscientific research at MIU is planned to be carried out in three phases over a period of 20 years; Surface-based Investigation Phase (Phase I), Construction Phase (Phase II) and Operation Phase (Phase III). Currently, the project is under the Construction Phase. This document presents the following results of the research and development performed in fiscal year 2007, as a part of the Construction Phase based on the MIU Master Plan updated in 2002, 1) Investigation at the MIU Construction Site and the Shobasama Site, 2) Construction at the MIU Construction Site, 3) Research Collaboration. (author)

  5. Mizunami Underground Research Laboratory project. Annual report for fiscal year 2005

    Nishio, Kazuhisa; Matsuoka, Toshiyuki; Tsuruta, Tadahiko; Amano, Kenji; Ohyama, Takuya; Takeuchi, Ryuji; Saegusa, Hiromitsu; Hama, Katsuhiro; Mizuno, Takashi; Sai, Masataka; Iyatomi, Yosuke; Shimada, Akiomi; Ogata, Nobuhisa; Uchida, Masahiro; Sugihara, Kozo; Mikake, Shinichiro; Ikeda, Koki; Yamamoto, Masaru; Yoshida, Haruo; Nakama, Shigeo; Seno, Yasuhiro; Kuroda, Hidetaka; Semba, Takeshi

    2009-03-01

    Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is developing a geoscientific research project named Mizunami Underground Research Laboratory (MIU) project in crystalline rock environment in order to establish scientific and technological basis for geological disposal of HLW. Geoscientific research at MIU is planned to be carried out in three phases over a period of 20 years; Surface-based Investigation Phase (Phase 1), Construction Phase (Phase 2) and Operation Phase (Phase 3). Currently, the project is under the Construction Phase. This document presents the following results of the research and development performed in 2005 fiscal year, as a part of the Construction Phase based on the MIU Master Plan updated in 2002, 1) Investigation at the MIU Construction Site and the Shobasama Site, 2) Construction at the MIU Construction Site, 3) Research Collaboration. (author)

  6. Environmental performance data in environmental report 2008

    Sato, Yoshinori; Noritake, Kazumitsu; Kawasaki, Takanori; Nemoto, Asako

    2009-02-01

    Japan Atomic Energy Agency published the Environmental Report 2008 concerning the activities of FY 2007 in August, 2008 under 'Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc, by Facilitating Access to Environmental Information, and Other Measures'. This report has been edited to show detailed environmental performance data in FY 2007 as the base of the Environmental Report 2008. This report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA. The environmental objectives in FY 2007 were to reduce the amounts of electric power consumption, fossil fuel usage, carbon dioxide emissions, and water usage by more than one percent in comparison with those in the previous fiscal year. The detailed environmental performance data in this report has shown that the numerical targets of the environmental objectives in FY 2007 were achieved. (author)

  7. Extraction Chromatography for Am and Cm Recovery in Engineering Scale

    Koma, Y.; Watanabe, S.; Sano, Y.; Asakura, T.; Morita, Y.

    2008-01-01

    The Japan Atomic Energy Agency (JAEA) has been developing the extraction chromatography for Am and Cm (An(III)) recovery from HLLW aiming at an engineering scale application. For process development, we started to assess the characteristics of adsorbents with some extractants by laboratory scale experiments. The experimental results with HDEHP/SiO 2 -P adsorbent suggested that An(III) is separated from other fission products by adjusting the pH of a feed solution and/or an eluent containing DTPA to be an appropriate value. The durability of CMPO/SiO 2 -P and HDEHP/SiO 2 -P adsorbents for gamma-ray irradiation were estimated to be 1 and 0.5 MGy, respectively. In the system development, system experiments for fluid flow, safety and durability using engineering scale column as well as studies on remote control/maintenance are now under progress. (authors)

  8. Review of the international forum on peaceful use of nuclear energy and nuclear security. Taking the lessons learned from Fukushima Daiichi Nuclear Power Plant accident to the 2012 Seoul nuclear security summit

    Tazaki, Makiko; Suda, Kazunori; Suzuki, Mitsutoshi; Kuno, Yusuke; Mochiji, Toshiro [Japan Atomic Energy Agency, Department of Science and Technology for Nuclear Material Management, Tokai, Ibaraki (Japan)

    2012-06-15

    The Japan Atomic Energy Agency (JAEA) held '2011 International Forum on the Peaceful Use of Nuclear Energy and Nuclear Security - Taking the lessons learned from Fukushima Daiichi Nuclear Power Plant Accident to the 2012 Seoul Nuclear Security Summit-' on 8 and 9 December, 2011. It intended to articulate effective strategies and measures for strengthening nuclear security using lessons learned from the Fukushima Nuclear Accident. Moreover, it was expected to explore comprehensive approaches which could contribute to enhancing both nuclear safety and security in order to support sustainable and appropriate development of the peaceful use of nuclear energy. This report includes abstracts of keynote speeches, summary of panel discussions and materials of the presentations in the forum. The editors take full responsibility for the wording and content of this report, excepts presentation materials. (author)

  9. Sulfur-Iodine Integrated Lab Scale Experiment Development

    Russ, Ben

    2011-01-01

    The sulfur-iodine (SI) cycle was determined to be the best cycle for coupling to a high temperature reactor (HTR) because of its high efficiency and potential for further improvement. The Japanese Atomic Energy Agency (JAEA) has also selected the SI process for further development and has successfully completed bench-scale demonstrations of the SI process at atmospheric pressure. JEA also plans to proceed with pilot-scale demonstrations of the SI process and eventually plans to couple an SI demonstration plant to its High Temperature Test Reactor (HHTR). As part of an international NERI project, GA, SNL, and the Frech Commissariat L'Energie Atomique performed laboratory-scale demonstrations of the SI process at prototypical temperatures and pressures. This demonstration was performed at GA in San Diego, CA and concluded in April 2009.

  10. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2006

    2009-01-01

    In the fiscal year 2006, the research reactor JRR-3 was operated 7 cycles (cycle operation: 26 days/cycle) for utilization sharing of the facility. And JRR-4 was operated 37 cycles (daily operation: 151 days). JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment in the nuclear reactor training, Practice of Reactor operation, Irradiation for activation analyses, RI productions, fission tracks, etc. The volume contains 294 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, neutron activation analyses, RI productions, prompt gamma-ray analyses, and others submitted by the users in JAEA and from other organizations. (author)

  11. Research on the state-of-the-art of probabilistic safety assessment for non-reactor nuclear facilities (2)

    Yoshida, Kazuo; Abe, Hitoshi; Yamane, Yuichi; Tashiro, Sinsuke; Muramatsu, Ken

    2007-03-01

    Japan Atomic Energy Agency (JAEA) entrusted with a research on the state-of-the-art of probabilistic safety assessment (PSA) of non-reactor nuclear facilities (NRNF) such as fuel reprocessing and fuel fabrication facilities to the Atomic Energy Society of Japan (AESJ). The objectives of this research is to obtain the basic useful information related for establishing the quantitative performance requirement and for risk-informed regulation through qualifying issues needed to be resolved for applying PSA to NRNF. A special committee of 'Research on the analysis methods for accident consequence in NFRF' was organized by the AESJ. The research activities of the committee were mainly focused on the analysis method for upper bounding consequences of accidents such as events of criticality, explosion, fire and solvent boiling postulated in NRNF resulting in release of radio active material to the environment. This report summarizes the results of research conducted by the committee in FY 2005. (author)

  12. Input/output manual of light water reactor fuel analysis code FEMAXI-7 and its related codes

    Suzuki, Motoe; Udagawa, Yutaka; Nagase, Fumihisa [Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan); Saitou, Hiroaki [ITOCHU Techno-Solutions Corporation, Tokyo (Japan)

    2013-10-15

    A light water reactor fuel analysis code FEMAXI-7 has been developed, as an extended version from the former version FEMAXI-6, for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which are fully disclosed in the code model description published in the form of another JAEA-Data/Code report. The present manual, which is the very counterpart of this description document, gives detailed explanations of files and operation method of FEMAXI-7 code and its related codes, methods of input/output, sample Input/Output, methods of source code modification, subroutine structure, and internal variables in a specific manner in order to facilitate users to perform fuel analysis by FEMAXI-7. (author)

  13. Input/output manual of light water reactor fuel analysis code FEMAXI-7 and its related codes

    Suzuki, Motoe; Udagawa, Yutaka; Nagase, Fumihisa; Saitou, Hiroaki

    2013-10-01

    A light water reactor fuel analysis code FEMAXI-7 has been developed, as an extended version from the former version FEMAXI-6, for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which are fully disclosed in the code model description published in the form of another JAEA-Data/Code report. The present manual, which is the very counterpart of this description document, gives detailed explanations of files and operation method of FEMAXI-7 code and its related codes, methods of input/output, sample Input/Output, methods of source code modification, subroutine structure, and internal variables in a specific manner in order to facilitate users to perform fuel analysis by FEMAXI-7. (author)

  14. Annual progress and future plans of laser R and D group

    Sugiyama, Akira; Kiriyama, Hiromitsu; Ochi, Yoshihiro; Tanaka, Momoko; Nakai, Yoshiki; Sasao, Hajime; Tateno, Ryo; Okada, Hajime; Kosuge, Atsushi; Tsubouchi, Masaaki

    2010-01-01

    Main subjects of our group in this middle term program are upgrade of J-KAREN and TOPAZ laser systems. The J-KAREN achieves the potential for generating a peak power of 500 TW, and exceeds a contrast ratio of 10E10. The TOPAZ achieves pulse power of 15 J at a repetition rate of 0.1 Hz. We also started a development of laser system named QUADRA (Quality Ultra ADvanced RAdiation Source) in C-Phost program. The QUADRA system aims a high averaged short pulse laser pumped by high power LD at kHz-class repetition rate. This development is essential for the elemental technology for the other new laser systems in the next 5-year program of JAEA. (author)

  15. Evaluation of mass transport property using natural uranium-series and thorium-series nuclides in the Toki Granite

    Hama, Katsuhiro

    2016-07-01

    The Mizunami Underground Research Laboratory (MIU) project is being pursued by the Japan Atomic Energy Agency (JAEA) to enhance the reliability of relevant disposal technologies through investigations of the deep geological environment within the host crystalline rock at Mizunami City in Gifu Prefecture, central Japan. The project proceeds in three overlapping phases, 'Phase I: Surface-based investigation Phase', 'Phase II: Construction Phase' and 'Phase III: Operation Phase'. As a part of the Phase III investigation, the mass transport property has been evaluated by using natural uranium-series and thorium-series nuclides in the Toki Granite. In this report, the compilation of existing data and preliminary evaluation was carried out. (author)

  16. Proceedings of the 2011 symposium on nuclear data

    Harada, Hideo; Yokoyama, Kenji; Iwamoto, Nobuyuki; Nakamura, Shoji

    2012-12-01

    The 2011 data symposium on nuclear data, organized by the Nuclear Data Division of Atomic Energy Society of Japan (AESJ) was held at Ricotti, Tokai, on Nov. 16 and 17, 2011 in cooperation with Nuclear Science and Engineering Directorate of JAEA and North-Kanto Branch of AESJ. The symposium was devoted for discussions and presentations of current topics in the field of nuclear data such as nuclear accident and accident analysis code, innovative methods on nuclear data theory and measurements, and nuclear data applications, including 2 tutorial talks, NJOY99 and PHITS. Talks as well as posters presented at the symposium aroused lively discussions among 97 participants. This report contains 34 papers submitted from the oral and poster presenters. (author)

  17. Proceedings of the 2010 symposium on nuclear data

    Watanabe, Yukinobu; Koura, Hiroyuki; Chiba, Satoshi

    2011-09-01

    The 2010 symposium on nuclear data organized by the Nuclear Data Division of Atomic Energy Society of Japan (AESJ) was held at C-CUBE, Chikushi Campus, Kyushu University, on November 25 and 26, 2010, with approximately 60 domestic and foreign participants, in cooperation with Advanced Science Research Center of JAEA and under financial support from the Kyushu Branch of AESJ. The symposium was devoted to presentations and discussions about recent research results in a wide variety of fields associated with nuclear data, such as JENDL-4 related evaluation and benchmark tests, nuclear data measurements and facilities, theoretical model calculations, applications, and so on. A tutorial on nuclear data evaluation for actinide nuclides was given in the symposium. This report consists of total 40 papers including 15 oral presentations and 25 poster presentations. (author)

  18. Developpement of a GoldSim Biosphere Model, Evaluation, and Its Verification

    Lee, Youn Myoung; Hwang, Yong Soo

    2009-12-01

    For the purpose of evaluating dose rate to individual due to long-term release of nuclides from the repository for an HLW or a pyroprocessing repository, a biosphere assessment model and the implemented program based on BIOMASS methodology have been developed by utilizing GoldSim, a general model developing tool. To show its practicability and usability as well as to see the sensitivity of parametric and scenario variations to the annual exposure, some probabilistic calculations are made and investigated. For the cases when changing the exposure groups and associated GBIs as well as varying selected input values, all of which seem important for the biosphere evaluation, dose rate per nuclide release rate is probabilistically calculated and analyzed. A series of comparison studies with JAEA, Japan have been also carried out to verify the model

  19. Neutron data compilation at the International Atomic Energy Agency

    Lemmel, H.D.; Attree, P.M.; Byer, T.A.; Good, W.M.; Hjaerne, L.; Konshin, V.A.; Lorens, A.

    1968-03-01

    The paper describes the present status of the neutron data compilation center of the IAEA Nuclear Data Unit, which is now in full operation. An outline i s given of the principles and objectives, the working routines, and the services available within the two-fold functions of the Unit: a) to promote cooperation and international neutron data exchange between the four major centers at Brookhaven, Saclay, Obninsk and Vienna, which share responsibilities in a geographical distribution of labour; b) to collect systematically the neutron data arising from countries in East Europe, Asia, Australia, Africa, South and Central America and to offer certain services to these countries. A brief description of DASTAR, the DAta STorage And Retrieval system, and of CINDU, the data Catalog of the JAEA Nuclear Data Unit, is given. (author)

  20. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2009

    NONE

    2014-02-15

    JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment in the nuclear reactor training, Practice of Reactor operation, Irradiation for activation analyses, RI productions, fission tracks, etc. In the fiscal year 2009, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 6 cycles (daily operation : 24 days). The volume contains 138 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, prompt gamma-ray analyses, neutron activation analyses, RI productions, and others submitted by the users in JAEA and from other organizations. (author)