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Kono, Yuko; Ayame, Junko; Yoshida, Tomoo*; Ikuta, Yuko; Kawase, Keiichi; Yamashita, Kiyonobu
JAEA-Review 2018-007, 36 Pages, 2018/06
JAEA-Review-2018-007.pdf:6.72MB
English translation of the material used at "Meeting to Answer Questions on Radiation" was made. "Meeting to Answer Questions on Radiation" was planned, just after the TEPCO Fukushima Daiichi Nuclear Power Plant Accident, by Japan Atomic Energy Agency (JAEA) with the purpose of providing comprehensive knowledge of radiation to the public. A total of 220 meetings was carried out from July, 2011 to February, 2013 mainly in Fukushima prefecture. Since the material used in the meetings contains many charts and is easy to understand, it has drawn attention of the International Atomic Energy Agency (IAEA) who has in recent years actively supported outreach activities to disseminate knowledge on nuclear and radiation. At one of the IAEA meetings in May, 2017, Asian Network for Education in Nuclear Technology (ANENT), it was requested to make it for the usage of all. Providing IAEA and the member states with the English translation of the material will be a meaningful contribution sharing the outreach activity experiences in Japan.
Yamaguchi, Mika; Hidaka, Akihide; Ikuta, Yuko; Murakami, Kenta*; Tomita, Akira*; Hirose, Hiroya*; Watanebe, Masanori*; Ueda, Kinichi*; Namaizawa, Ken*; Onose, Takatoshi*; et al.
JAEA-Review 2017-002, 60 Pages, 2017/03
JAEA-Review-2017-002.pdf:9.41MB
Since 2010, IAEA has held the NEM School to develop future leaders who plan and manage nuclear energy utilization in their county. Since 2012, JAEA together with Japan Nuclear HRD Network, University of Tokyo, Japan Atomic Industrial Forum and JAIF International Cooperation Center have cohosted the school in Japan in cooperation with IAEA. Since then, the school has been held in Japan every year. In 2006, Japanese nuclear technology and experience, such as lessons learned from the Fukushima Daiichi Nuclear Power Plant accident, were provided to offer a unique opportunity for the participants to learn about particular cases in Japan. Through the school, we contributed to the internationalization of Japanese young nuclear professionals, development of nuclear human resource of other countries including nuclear newcomers, and enhanced cooperative relationship with IAEA. Additionally, collaborative relationship within the network was strengthened by organizing the school in Japan.
Hidaka, Akihide; Nakano, Yoshihiro; Watanabe, Yoko; Arai, Nobuyoshi; Sawada, Makoto; Kanaizuka, Seiichi*; Katogi, Aki; Shimada, Mayuka*; Ishikawa, Tomomi*; Ebine, Masako*; et al.
JAEA-Review 2016-011, 208 Pages, 2016/07
JAEA-Review-2016-011-01.pdf:33.85MBJAEA-Review-2016-011-02.pdf:27.68MB
JAEA has been conducting the Instructor Training Program (ITP) since 1996 under the auspices of MEXT to contribute to human resource development in currently 11 Asian countries in the field of radiation utilization for seeking peaceful use of nuclear energy. ITP consists of Instructor Training Course (ITC), Follow-up Training Course (FTC) and Nuclear Technology Seminars. In the ITP, trainings or seminars relating to technology for nuclear utilization are held in Japan by inviting nuclear related people from Asian countries to Japan and after that, the past trainees are supported during FTC by dispatching Japanese specialists to Asian countries. News Letter is also prepared to provide the broad range of information obtained through the trainings for local people near NPPs in Japan. The present report describes the activities of FY2014 ITP and future challenges for improving ITP more effectively.
Hidaka, Akihide; Nakamura, Kazuyuki; Watanabe, Yoko; Yabuuchi, Yukiko; Arai, Nobuyoshi; Sawada, Makoto; Yamashita, Kiyonobu; Sawai, Tomotsugu; Murakami, Hiroyuki
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 9 Pages, 2015/05
Watanabe, Yoko; Shimada, Mayuka*; Yamashita, Kiyonobu
JAEA-Review 2014-044, 65 Pages, 2015/01
JAEA-Review-2014-044.pdf:12.4MBJAEA-Review-2014-044-appendix1(Students)(CD-ROM).pdf:7.28MBJAEA-Review-2014-044-appendix2(Teacher)(CD-ROM).pdf:8.7MB
JAEA has been organizing training programs for engineers in Asian countries introducing nuclear technology. In 2012, we launched a course "Basic Radiation Knowledge for School Education" as we thought disseminating accurate knowledge on radiation to school students and public would also be important in those countries after Fukushima-Daiichi Nuclear Power Plant accident. MEXT published supplemental learning material on radiation for secondary school students and teachers in Japanese in October 2011. Since the original Japanese version is designed to give a clear explanation of radiation and covers various topics, we thought it would also be beneficial for young students in the world if the English version was available. The English version of this learning material has been favourably evaluated by the International Atomic Energy Agency and will be widely used as a practical educational tool in many countries around the world through the IAEA.
Yamashita, Kiyonobu; Ikuta, Yuko; Yamaguchi, Mika
Nihon Genshiryoku Gakkai-Shi ATOMO
, 56(12), P. 812, 2014/12
no abstracts in English
Ohgama, Kazuya; Ando, Yoko; Yamaguchi, Mika; Ikuta, Yuko; Shinohara, Nobuo; Murakami, Hiroyuki; Yamashita, Kiyonobu; Uesaka, Mitsuru*; Demachi, Kazuyuki*; Komiyama, Ryoichi*; et al.
JAEA-Review 2013-004, 76 Pages, 2013/05
JAEA-Review-2013-004.pdf:13.53MB
JAEA together with the Japan Nuclear Human Resource Development Network (JN-HRD Net), the University of Tokyo (UT) and the Japan Atomic Industrial Forum (JAIF) cohosted the IAEA-Nuclear Energy Management School in Tokai Village, aiming that Japan will be the center of nuclear HRD in the Asian region. In the school, not only lectures by IAEA experts, but also lectures by Japanese experts and technical visits were included for foreign participants. The school contributed to the internationalization of Japanese young professionals, development of nuclear human resource of other countries, and enhancement of cooperation between IAEA and Japan. Additionally, collaborative relationship within JN-HRD Net was strengthened by the school. In this report, findings obtained during the preparatory work and the school period are reported for future international nuclear HRD activities in Japan.
Yamashita, Kiyonobu; Ikuta, Yuko
Nihon Genshiryoku Gakkai-Shi ATOMO, 55(5), p.271 - 273, 2013/05
no abstracts in English
Uesaka, Mitsuru*; Yamashita, Kiyonobu; Ohgama, Kazuya; Hattori, Takuya*
Nihon Genshiryoku Gakkai-Shi ATOMO, 55(1), p.53 - 56, 2013/01
no abstracts in English
Arai, Nobuyoshi; Yabuuchi, Yukiko; Yamashita, Kiyonobu
Transactions of International Topical Meeting on Safety of Nuclear Power Plants (ENS TopSafe 2012) (Internet), 5 Pages, 2012/04
NuHRDeC (Nuclear Human Resource Development Center) has been conducting a training scheme "Instructor Training Programme" (ITP) as a part of international human resource development (HRD) activities for Asian countries at JAEA since 1996. ITP consists of three categories; Instructor Training Course (ITC), Follow up Training Course (FTC) and Nuclear Seminar. Despite the Fukushima Dai-ichi Nuclear Power Plant (NPP) accident occurred on 11th March 2011, most of Asian countries have not changed their nuclear policy. NuHRDeC is therefore conducting the International training course including the curriculum related to the accident to expand nuclear safety for Asian countries.
Yagi, Masahiro; Watanabe, Masanori; Oyama, Koji; Yamamoto, Kazuyoshi; Komeda, Masao; Kashima, Yoichi; Yamashita, Kiyonobu
Applied Radiation and Isotopes, 67(7-8), p.1225 - 1229, 2009/07
Times Cited Count：11 Percentile：58.91(Chemistry, Inorganic & Nuclear)Nakagawa, Shigeaki; Umeda, Masayuki; Beddingfield, D. H.*; Menlove, H. O.*; Yamashita, Kiyonobu
JAEA-Technology 2007-003, 24 Pages, 2007/02
JAEA-Technology-2007-003.pdf:3.61MB
As of the safeguards approach in the HTTR facility, an unattended spent fuel flow monitor (UFFM) was applied to carry out an item counting of spent fuel blocks. The UFFM is so designed and fabricated as to be the compact and unique monitor system to verify a movement of spent fuel blocks in "difficult to access" area and reduce inspection efforts. This system consists of two detector packages, electronics and computer. One package consists of two ionization chambers and a He-3 counter. The IAEA acceptance tests were performed and it was confirmed the followings: (1) All the detectors were functioning properly to measure a spent fuel block flow. (2) The time difference between detector signals was sufficient to determine the direction of the spent fuel blocks. (3) The UFFM was useful to carry out the item counting. The UFFM was approved as the IAEA safeguards equipment in the safeguards approach in the HTTR.
Fujimoto, Nozomu; Yamashita, Kiyonobu*; Nojiri, Naoki; Takeuchi, Mitsuo; Fujisaki, Shingo; Nakano, Masaaki*
Nuclear Science and Engineering, 150(3), p.310 - 321, 2005/07
Times Cited Count：6 Percentile：39.99(Nuclear Science & Technology)Annular cores were formed in startup-core-physics tests of the High Temperature Engineering Test Reactor (HTTR) to obtain experimental data for verification of calculation codes. The first criticality, control rod positions at critical conditions, neutron flux distribution, excess reactivity etc. were measured as representative data. These data were evaluated with Monte Carlo code MVP that can consider the heterogeneity of coated fuel particles (CFP) distributed randomly in fuel compacts directly. It was made clear that the heterogeneity effect of CFP on reactivity for annular cores is smaller than that for fully-loaded cores. Measured and calculated effective multiplication factors (k) were agreed with differences less than 1%
k. Measured neutron flux distributions agreed with calculated results. The revising method was applied for evaluation of excess reactivity to exclude negative shadowing effect of control rods. The revised and calculated excess reactivity agreed with differences less than 1%k/k.
Yamashita, Kiyonobu; Ozawa, Masaki; Ikegami, Tetsuo; Harada, Hideo; Osaka, Masahiko; Oki, Shigeo; Tachi, Yoshiaki; Furutaka, Kazuyoshi; Nakamura, Shoji
JNC TN9420 2004-001, 106 Pages, 2005/03
JNC-TN9420-2004-001.pdf:12.85MB
Research Evaluation Committee carried out a pre-evaluation of Research and Development of Partitioning and Transmutation Technology of Long-Lived-Nuclides namely, partitioning, nuclear data, reactor physics, fuel, creative transmutation technology, in Aug. 2000. Following results are obtained from the research and development. For example, two extract ant systems, capable of recovering all actinides in spent fuel, were newly nominated in partitioning technology. Also, neutron capture cross sections of 7 nuclides of MA and Fission Products (FP) were determined in nuclear data measurements. Some of those measurements are for the first time in the world. An advanced measurement system of a full solid angle Bi4Ge3O12 detector etc. was developed to measure the energy dependence of the neutron capture cross sections. These achievements in the first phase are summarized in the report to promote the research and development in the second phase effectively.
Fujimoto, Nozomu; Nojiri, Naoki; Yamashita, Kiyonobu*
Nuclear Engineering and Design, 233(1-3), p.155 - 162, 2004/10
Times Cited Count：2 Percentile：16.97(Nuclear Science & Technology)The HTTR uses low-enriched uranium fuel with burnable poison rod. For validation of the nuclear design code system for the HTTR, a critical assembly of VHTRC had been constructed. The calculation uncertainties of effective multiplication factor, neutron flux distribution, burnable poison reactivity worth, and control rod worth, temperature coefficients were evaluated. Calculation accuracy of a Monte Carlo code is also evaluated.
Fujimoto, Nozomu; Nojiri, Naoki; Ando, Hiroei*; Yamashita, Kiyonobu*
Nuclear Engineering and Design, 233(1-3), p.23 - 36, 2004/10
Times Cited Count：13 Percentile：63.33(Nuclear Science & Technology)In the nuclear design of the HTTR, the reactivity balance is planned so that the design requirements are fully satisfied. Moreover, the reactivity coefficients are evaluated to confirm the safety characteristics of the reactor. The power distribution in the core was optimized by changing the uranium enrichment to maintain the fuel temperature at less than the limit (1600
C). Deviation from the optimized distribution due to the burnup of fissile materials was avoided by flattening time-dependent changes in local reactivities. Flattening was achieved by optimizing the specifications of the burnable poisons. The original nuclear design model had to be modified based on the first critical experiments. The Monte Carlo code MVP was also used to predict criticality of the initial core. The predicted excess reactivities are now in good agreement with the experimental results.
Yamashita, Kiyonobu; Ichimiya, Masakazu; Yamashita, Hidetoshi
Proceedings of 14th Pacific Basin Nuclear Conference (PBNC-14), p.834 - 841, 2004/00
Large-scale Sodium-Cooled Fast Reactor Concept was created. It satisfies development targets such as ensuring safety, economic competitiveness, efficient utilization of resoueces and non-proliferation. Its concept and recent fundamental reseaches will be reported.
Yamashita, Kiyonobu; Ichimiya, Masakazu; Yamashita, Hidetoshi
Roshia Kosokuro Kokusai Kaigi, 0 Pages, 2003/00
A Promising Sodium-Cooled Fast Reactor Concept was created. It satisfies development targets such as ensuring safety, economic competitiveness, efficient utilization of resoueces and non-proliferation. Its concept and R&D plan will be reported.
Fujimoto, Nozomu; Nojiri, Naoki; Yamashita, Kiyonobu; Shimakawa, Satoshi; Ando, Hiroei; Mori, Takamasa
Nihon Genshiryoku Gakkai Monte Karuro Ho Ni Yoru Ryushi Shimyureshon No Genjo To Kadai, p.201 - 210, 2002/01
no abstracts in English
ray from fuel of High Temperature Engineering Test Reactor; Method of measurement and resultsFujimoto, Nozomu; Nojiri, Naoki; Takada, Eiji*; Yamashita, Kiyonobu; Kikuchi, Takayuki; Nakagawa, Shigeaki; Kojima, Takao; Umeta, Masayuki; Hoshino, Osamu; Kaneda, Makoto*; et al.
JAERI-Tech 2001-002, 64 Pages, 2001/02
JAERI-Tech-2001-002.pdf:3.64MB
no abstracts in English
