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JAEA Reports

Investigation of utilizing plutonium as mixed oxide fuel (5); BWR for next generation

*; *; *; *

JNC TJ9440 2000-007, 43 Pages, 2000/03

JNC-TJ9440-2000-007.pdf:1.73MB

Planning of the plutonium utihzation in the Light water thermal reactor has been investigated to evaluate scenario for FBR development. Plans for MOX fuel utilization in the ABWR including Ooma plant are studied, and information of high burnup fuels for a future BWR is summarized based on public documents. Nuclear compositions of the present burnup fuel (45,000MWd/t) and a high burnup fue (60,000MWd/t) have been evaluated using an open code: SRAC. Results of the study are follows; (1)Surveying the status of MOX fuel utilization. The status of MOX and UO$$_{2}$$ fuel utilization in the present BWR and future BWR have been summarized based on public documents. (2)Evaluation of spent MOX and UO$$_{2}$$ fuel composition. Nuclear compositions of spent MOX and UO$$_{2}$$ fuels at 45,000MWd/t and 60,000MWd/t burnup have been evaluated and summarized for recycle scenarios by FBR.

Journal Articles

MOX fuel behavior under reactivity accident conditions

Sasajima, Hideo; Fuketa, Toyoshi; Ishijima, Kiyomi; Kikuchi, Keiichi*; Abe, Tomoyuki*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

JAEA Reports

The economics of various fuel cycle systems

Kofuji, Hirohide;

PNC TN9410 98-066, 67 Pages, 1998/06

PNC-TN9410-98-066.pdf:2.05MB

The economics of various fuel cycle based on the current domestic situation were evaluated to confirm the adequacy of the economical target of the FBR fuel cycle. Four types of fuel cycle concepts, LWR-once through, LWR-reprocessing, LWR-Pu and FBR, were selected. The unit costs of the fuel cycle components were based on the domestic business base price or estimated values from published construction costs. These setting of the unit costs were the key point of this report. As the results, generating electricity cost of the LWR-reprocessing scenario which was thought to be the domestic reference scenario was estimated to be 8.2 yen/kWh, that of once through scenario was 7.5 yen/kWh, and LWR-Pu scenario was 8.2 yen/kWh. These differences of the generating electricity costs due to the deference of the fuel cycle costs because those three scenario were based on the same reactor concept. The generating electricity cost of the once through scenario is smaller than that of the reprocessing scenario equivalent for the reprocessing cost because that front end costs of the both scenario were equal and spent fuel or waste disposal cost occupied merely small parts of the fuel cycle costs. In the PWR-Pu scenario, natural uranium and enrichment cost were cut down but the fuel cycle cost was the same as the reprocessing scenario due to the relatively high cost of MOX fabrication. On the other hand, though the gcnerating electricity cost of the FBR scenario based on the current technology is 13.3 yen/kWh which is about 1.6 times of that of the LWR reprocessing scenario, its future cost was estimated to be 6.7 yen/kWh which is lower than every LWR scenario results of the future R&D. These economical evaluation showed the adequacy of the economical target of the FBR cycle, it is necessary to improve the evaluation accompanying with the trend of the LWR cycle and the progress of the R&D of the FBR cycle.

Journal Articles

Technical issues with regard to plutonium burning

Mukaiyama, Takehiko

NIRA Seisaku Kenkyu, 8(12), p.18 - 21, 1995/12

no abstracts in English

Oral presentation

Application of partitioning and transmutation technology to waste management; An Attempt to assess total performance of advanced nuclear fuel cycle, 4; A Trial assessment for MOX plu-thermal cycle

Makino, Hitoshi; Asano, Hidekazu*; Usami, Tsuyoshi*; Kanehira, Norio*; Ikeda, Takao*; Kawai, Kota*; Watanabe, Daisuke*

no journal, , 

This presentation shows current status of discussion on "A trial assessment for MOX plu-thermal cycle" which is a challenge as part of an attempt to assess total performance of advanced nuclear fuel cycle in the Research Committee on Disposal of Radioactive Waste and Partitioning-Transmutation Technology.

Oral presentation

Evaluation of long-term safety of geological disposal of high-level waste generated during reprocessing spent MOX-LWR fuels

Minari, Eriko*; Kabasawa, Satsuki; Mihara, Morihiro; Makino, Hitoshi; Nakase, Masahiko*; Asano, Hidekazu*; Takeshita, Kenji*

no journal, , 

As a study on long-term safety of geological disposal of high-level waste (HLW) generated during reprocessing spent mixed oxide fuel in light water reactors (MOX-LWRs), two types of HLW are considered. One is HLW generated from MOX-LWR reprocessing and another is blended MOX-UO$$_{2}$$ HLW generated during reprocessing process whereby MOX fuels are diluted by UO$$_{2}$$ fuels. Radionuclide migration analyses for those two HLWs are conducted, and commonalities and differences between two HLWs in the viewpoint of long-term safety are discussed.

Oral presentation

Study on nuclear utilization scenario towards the second half of the 21st century, 3; Evaluation of long-term safety of geological disposal of vitrified MOX-LWR high-level waste

Minari, Eriko*; Mihara, Morihiro; Makino, Hitoshi; Okamura, Tomohiro*; Oizumi, Akito; Nishihara, Kenji; Nakase, Masahiko*; Takeshita, Kenji*

no journal, , 

no abstracts in English

Oral presentation

Application of partitioning and transmutation technology to waste management; Assessment of total performance of advanced nuclear fuel cycle, 3; An Assessment for MOX plu-thermal cycle

Makino, Hitoshi; Asano, Hidekazu*; Usami, Tsuyoshi*; Tsukada, Takeshi*; Ikeda, Takao*; Kawai, Kota*; Watanabe, Daisuke*

no journal, , 

This presentation shows current status of discussion on "An assessment for MOX plu-thermal cycle" which is a challenge as part of an attempt to assess total performance of advanced nuclear fuel cycle in the Research Committee on Disposal of Radioactive Waste and Partitioning-Transmutation Technology.

Oral presentation

Management of plu-thermal spent fuel, 2; Quantity assessment

Nishihara, Kenji; Abe, Takumi

no journal, , 

In order to investigate the management of plu-thermal spent fuel, we compared the various cycle quantities of one-time recycling and two-time recycling, assuming long-term storage, direct disposal, and reprocessing of spent nuclear fuel. As a result, it was found that the volume handled in the front-end (U-mining and enrichment process) is less than that in the twice-recycled process, while the volume handled in the once-recycled process is less than that in many other processes, such as the back-end process.

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