The Impact of fuel cycle options on the space requirements of a HLW repository

Kawata, Tomio

Nuclear Engineering and Technology, 39(6), p.683 - 690, 2007/12

To make nuclear energy truly sustainable, it is necessary to ensure not only the sustainability of the fuel supply but also the sustained availability of waste repositories, especially those for high-level radioactive waste (HLW). From this perspective, the effort to maximize the waste loading density in a given repository is important for easing repository capacity problems. In most cases, the loading of a repository is controlled by the decay heat of the emplaced waste. In this paper, a comparison of the decay heat characteristics of HLW is made among the various fuel cycle options. It is suggested that, for a future fast breeder reactor (FBR) cycle, the removal and burning of minor actinides (MA) would significantly reduce the heat load in waste and would allow for a reduction of repository size by half.

Preparing for the transition from LWR era to FBR era

Kawata, Tomio

Nihon Genshiryoku Gakkai-Shi ATOMO, 49(6), p.410 - 415, 2007/06

http://ci.nii.ac.jp/naid/10018762976

no abstracts in English

A Study on the optimized fuel cycle systems during the transition period from LWR era to FBR era

Ojima, Hisao; Hayashi, Naoto; Nagai, Toshihisa; Fujita, Yuji; Kawata, Tomio

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 5 Pages, 2005/10

This paper mentions a preliminary evaluation on the typical LWR-to-FBR transition scenarios. Deployment rate of FBRs is strongly connected with replacement rate of LWRs, however, the transition should be seen as a matter of the optimization of fuel cycle systems. Based on the Pu balance evaluation, it seems definitely necessary to save an adequate amount of LWR spent fuels before beginning the deployment of FBRs. The mission of the second LWR fuel reprocessing plant in Japan will most provably be to feed Pu needed for starting up new FBRs. Along with the Pu utilization, especially as LWR-MOX fuel, the accumulation of minor actinides(MAs) in the high-level radioactive waste will become dominant and finally result in larger number of vitrified HLW because of heat generation from MAs. MA recovery cycle combined with the FBR will gives successful solution on this matter. Requirements on the next generation reprocessing plant, which corresponds to the transition scenario, are studied and innovative concept named

The Support Activities of JNC against the JCO Criticality Accident

Kanamori, Masashi; Kawata, Tomio; Hitoshi, Watanabe,; Tobita, Yoshiharu; Sugiyama, Toshihide; Miyabe, Kenjiro; Kobayashi, Hirohide

JNC TN8450 2003-009, 506 Pages, 2004/03

JNC-TN8450-2003-009.pdf:14.21MB

This paper describes all the activities that were executed by JNC related to JCO criticality accident on September 30,1999. During the JCO accident, the activities of radiation monitoring, environmental monitoring, criticality termination operation, computer simulation of criticality accident, whole body exposure measurements by WBC about 24-Na, back up of local government like consultation of residents near by were performed by JNC. After the accident Japanese government and Nuclear Safety Commission establishes the investigation committee of JCO accident. JNC has also back up this activity. For example, investigation of the causes, accident scenario, estimation of the doses of the workers and personnel for deserter, counter measure operation. This paper summarizes all the important activity executed by JNC in the meantime.

None

Kawata, Tomio; Takeda, Seietsu; ; ; Makino, Hitoshi

JNC TN1400 2001-017, 50 Pages, 2002/01

JNC-TN1400-2001-017.pdf:5.59MB

no abstracts in English

The Advanced fuel recycle for coming century

Nomura, Shigeo; Kawata, Tomio; ; Ojima, Hisao

Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/10

None

The Advanced fuel recycle for coming century

Kawata, Tomio; Ojima, Hisao; ; Nomura, Shigeo

Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/00

None

Advanced fuel recycle system concept to realize minor actinides recycle

Nakajima, Ichiro; Ojima, Hisao; Nomura, Shigeo; Kawata, Tomio

4th OECD/NEA Information Exchange Meeting, 0 Pages, 1996/00

None

Development of remote dismantling and removal of large components in Reprocessing Plant

Ishibashi, Yuzo; Kawata, Tomio; Tanaka, Yasumasa; ;

Proceedings of 3rd International Conference on Nuclear Engineering (ICONE-3), p.0 - 0, 1995/00

None

Outline of recycle equipment test facility for development of FBR fuel reprocessing technologies

Koyama, Tomozo; ; Kawata, Tomio;

Proceedings of 4th International Conference on Nuclear Fuel Reprocessing and Waste Management (RECOD '94), 0 Pages, 1994/00

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