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Yamamura, Osamu; Yamamoto, Ryuichi; Nomura, Shigeo; Fujii, Yasuhiko*
Progress in Nuclear Energy, 50(2-6), p.666 - 673, 2008/03
Times Cited Count：4 Percentile：29.38(Nuclear Science & Technology)The application of safeguards to the Tokai Reprocessing Plant(TRP), the world's first reprocessing plant with a sole objective of commercial use, was made on try and error basis because it was the first experience for both the plant and the inspection sides. Through thirty years' faithful cooperation to the IAEA-initiated safeguards program, TRP contributed also to the developments of the international credibility upon the concept of safeguards system of Reprocessing plant in non-nuclear weapon countries. TRP also has been processing over 1,123 ton of spent fuels from the beginning of its active operation in Sept.'77. For 30 years operation of TRP, many technological problems have been overcome to obtain the stable and reliable operation. The process for establishments of maintenance technology in TRP was evaluated through the analysis of significant plant equipment failures reported to the Government and so on. Discussion in this paper is also emphasized that the safeguards system and the maintenance technologies developed by TRP have been applied to the first Rokkasho commercial reprocessing plant (RRP). Furthermore, this operation knowledge base can contribute to the design and construction of the next generation reprocessing plant.
Yamamura, Osamu; Yamamoto, Ryuichi; Nomura, Shigeo
Journal of Nuclear Materials Management, 36(3), p.36 - 45, 2008/00
This paper describes the role of Tokai Reprocessing Plant (TRP) for the safeguards (SG) technology development by Japan and IAEA and its application to the first large commercial plant in Japan. Through several negotiations between Japan and USA, TRP accepted the full scope application of IAEA's SG, the development of U-Pu mixed conversion process, and the experimental work of IAEA for development of SG activities. Results under the TASTEX, which was research and development program by an agreement made during Japan and USA negotiation on reprocessing, were reflected to the INFCE, which was organized by the change in US atomic energy policy. Most of the current SG technologies being applied by IAEA were developed at this time. Both effectiveness and reliability of such technologies have been validated extensively through the 30 years operation of TRP.
Yamamura, Osamu; Yamamoto, Ryuichi; Nomura, Shigeo
Nihon Genshiryoku Gakkai Wabun Rombunshi, 6(4), p.491 - 502, 2007/12
Tokai reprocessing plant (TRP) has been processing over 1,123 ton of spent fuels from the beginning of its active operation in Sept. 1977. For 30 years operation of TRP, many technological problems have been overcome to obtain the stable and reliable operation. The process for establishments of maintenance technology in TRP was evaluated through the analysis of significant plant equipment failures reported to the Government. These operation knowledge base can contribute to the safe and stable operation of Rokkasho reprocessing plant and the design and construction of the next reprocessing plant.
Ojima, Hisao; Dojiri, Shigeru; Tanaka, Kazuhiko; Takeda, Seiichiro; Nomura, Shigeo
Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.273 - 282, 2007/09
The Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency (JAEA) was established to take over activities of the Tokai Works of Japan Nuclear Cycle Development Institute (JNC). From 1959, several kinds of technologies (such as uranium refining, centrifuge for uranium enrichment, LWR spent fuel reprocessing and MOX fuel fabrication) have been accomplished. And also, R&Ds on the treatment and disposal of high level waste and the FBR fuel reprocessing have been carried out. Through such activities, control of environmental release of radioactive material and radiation exposure and management of nuclear materials have been done appropriately. The Laboratories will contribute to establish the closed cycle with R&Ds of the reprocessing technology during the transition period from LWR era to FBR era, improved MOX fuel fabrication technology, advanced FBR fuel reprocessing technology and high level waste disposal technology.
Shiotsuki, Masao; Aoshima, Atsushi; Nomura, Shigeo
Proceedings of International Waste Management Symposium 2006 (WM '06) (CD-ROM), 10 Pages, 2006/02
Achievement of reliable technologies on solidification and disposal of the HLW from future fuel cycle systems such for high burnup LWR, Pu-thermal (MOX), fast breeder reactor (FBR) and their transient stages is one of the most important issues to establish such advanced fuel cycle systems. In this paper, applicability and flexibility of the current vitrification technology for LWR fuel cycle to HLW from the future fuel cycle systems were reviewed by examining characteristics of the HLWs. The current developed vitrification technology is expected to have an advantage for applying to the solidification process of the HLW generated from future fuel cycle systems with some modification/optimization of the melting condition, etc. Moreover, it is thought that the advance aqueous reprocessing system developed for future FBR cycle has the potential which can contribute to the further reducing the number/volume of the HLW. It is also confirmed that development efforts on countermeasure for accumulation of noble metals, which JAEA has been carrying out aiming to accomplishing more stable and reliable operation of the vitrification process and extending the melter's life, will be able to contribute in the future fuel cycle system furthermore.
Nomura, Shigeo; Kikuchi, Ko; Omori, Eiichi; Inano, Masatoshi
Enerugi, 38(6), p.59 - 62, 2005/00
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Yonezawa, Rika; Nomura, Shigeo; Nakamura, Hirofumi; Ayame, Junko
Hoken Butsuri, 39(1), p.26 - 31, 2004/00
Risk Communication Study Team was set up on January 1, 2001. Our Activities are Audience analysis, Messege designing, Communication with local residents, Sharing infomation on Risk Communication among employees, etc. We carried out "Cycle" Friendly Talk.
Nomura, Shigeo
Proceedings of 1st International Science and Technology Forum on Protected Plutonium Utilization for Peace and Sustainable Prosperity, p.32 - 33, 2004/00
The application of the fluoride volatility process in the reprocessing of fuel from the fast breeder reactor is regarded as one of the economical methods. Plutonium hexafluoride (PuF
), however, reacting with fluorine (F2) and plutonium dioxide (PuO
) as the raw material, is in an unstable condition and tends to remain as a solid compound in the process after decomposing into plutonium tetrafluoride (PuF
). Suitable conditions should be established for the practical use of this process. One of them is to enhance the stability of PuF6. The behaviour of plutonium fluorination and relevant chemical reactions were investigated by referring to sundry literature and by thermodynamic calculation. It was then compared with recent data from laboratory scale experiments for this paper. Results from the theoretical analysis agreed with experimental observation that PuF could be formed stably under a high temperature condition (approx.1000 K) with over supply of figher concentration of F.
Tsuzuki, Kazuhiro; Kimura, Haruyuki; Kawashima, Hisato; Sato, Masayasu; Kamiya, Kensaku; Shinohara, Koji; Ogawa, Hiroaki; Hoshino, Katsumichi; Bakhtiari, M.; Kasai, Satoshi; et al.
Nuclear Fusion, 43(10), p.1288 - 1293, 2003/10
Times Cited Count：39 Percentile：73.93(Physics, Fluids & Plasmas)no abstracts in English
Nomura, Shigeo; Yamato, Aiji; Ojima, Hisao
CD-ROM, 5P., 5 Pages, 2003/00
In Japan, the Feasibility study for commercialization of FBR and its fuel cycle system (FS) has been conducted under the collaboration of JNC and the electric utilities since 1999. Through the FS, candidate technology will be selected by 2015.
; Nomura, Shigeo; Ojima, Hisao; Funasaka, Hideyuki
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1290 - 1298, 2003/00
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Nomura, Shigeo; Ojima, Hisao; Funasaka, Hideyuki
Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), 1290 Pages, 2003/00
Three candidate systems of spent fuel reprocessing integrated with fuel fabrication process,i.e.advanced aqueous,oxide electrowinning and metal electrorefining are studied as the Feasibility Study(FS)Phase-2 for advanced fast reactor fuel cycle.
Kisohara, Naoyuki; Uchita, Masato; Konomura, Mamoru; Kasai, Shigeo; Soman, Yoshindo; Shimakawa, Yoshio; Hori, Toru; Chikazawa, Yoshitaka; Miyahara, Shinya; Hamada, Hirotsugu; et al.
JNC TN9400 2003-002, 109 Pages, 2002/12
JNC-TN9400-2003-002.pdf:8.12MB
Sodium is the most promising candidate of an FBR coolant because of its excellent properties such as high thermal conductivity. Whereas, sodium reacts with water/air and its opaqueness makes it difficult to inspect sodium components. These weaknesses of sodium affect not only plant safety but also plant availability (economy). To overcome these sodium weak points, the appropriate countermeasure must be adopted to commercialized FBR plants. This report describes the working group activities for sodium/water reaction of steam generators (SG), in-service inspection for sodium components and sodium leak due to sodium components boundary failure. The prospect of each countermeasure is discussed in the viewpoint of the commercialized FBR plants. (1)Sodium/water reaction. The principle of the countermeasure for sodium/water reaction accidents was organized in the viewpoint of economy (the investment of SG and the plant availability). The countermeasures to restrain failure propagation were investigated for a large-sized SG. Preliminary analysis revealed the possibility of minimizing tubes failure propagation by improving the leak detection system and the blow down system. Detailed failure propagation analysis will be required and the early water leak detection system and rapid blow down system must be evaluated to realize its performance. (2)In-service inspection (ISI&R). The viewpoint of the commercialized plant's ISI&R was organized by comparing with the prototype reactor's ISI&R method. We also investigated short-term ISI&R methods without sodium draining to prevent the degrading of the plant availability, however, it is difficult to realize them with the present technology. Hereafter, the ISI&R of the commercialized plants must be defined by considering its characteristics. (3)Sodium leak from the components. This report organized the basic countermeasure policy for primary and secondary sodium leak accidents. Double-wall structure of sodium piping was ...
Nomura, Shigeo; *; *
Nihon Genshiryoku Gakkai-Shi, 41(12), p.1244 - 1251, 1999/12
Times Cited Count：2 Percentile：21.15(Nuclear Science & Technology)None
Nomura, Shigeo; Kawata, Tomio; ; Ojima, Hisao
Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/10
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Kawata, Tomio; Ojima, Hisao; ; Nomura, Shigeo
Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/00
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Nakajima, Ichiro; Ojima, Hisao; Nomura, Shigeo; Kawata, Tomio
4th OECD/NEA Information Exchange Meeting, 0 Pages, 1996/00
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