We proposed the “Flexible Fuel Cycle Initiative” (FFCI), which has flexibility for the uncertainties like the introduction speed of FBRs. On the other hand, during the FBR introduction period, Pu from LWR spent fuel is used for startup of FBRs. But the FBR core being loaded with Pu from LWR spent fuel has larger burnup reactivity due to its larger isotopic fraction of Pu-241 than the core being loaded with Pu from the FBR multi-recycling core. The increased burnup reactivity may reduce the cycle length of the FBR. In this paper, an FBR transitional core concept to handle the issues of the FBR introductory period was investigated. Core specifications are based on the compact type sodium-cooled MOX-fueled core designed in the Japanese FBR cycle feasibility studies, because the lower Pu inventory should be better for the FBR introductory period in view of its flexibility for the required reprocessing amount of LWR spent fuel to start up the FBR. The reference specifications are selected as follows. Output is 1500MWe and the average discharge fuel burnup is about 150GWd/t. Minor Actinides (MAs) recovered from LWR spent fuels which provide Pu to startup FBR are loaded to the initial loading fuels and exchanged fuels during some cycles until equilibrium. We set a kind of MA fraction rate of the initial loading fuel with 4 as the number of the fuel exchange batches. The average of the MA fraction of the initial loading fuel assumed is 3%, and the MA fraction of the exchange fuel is set as 5%. This 5% maximum of the MA fraction is based on the irradiation results of the experimental fast reactor Joyo. The core performance including burnup characteristics and reactivity coefficient were evaluated, and we confirmed that the transitional core from the initial loading until equilibrium cycle loaded Pu from LWR spent fuels could keep the resemble performance with the FBR multi-recycling core.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4817-5
PROCEEDINGS PAPER
Minor Actinides-Loaded FBR Core Concept Suitable for the Introductory Period Available to Purchase
Koji Fujimura,
Koji Fujimura
Hitachi, Ltd., Hitachi, Ibaraki, Japan
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Akira Sasahira,
Akira Sasahira
Hitachi, Ltd., Hitachi, Ibaraki, Japan
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Junichi Yamashita,
Junichi Yamashita
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Tetsuo Fukasawa,
Tetsuo Fukasawa
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Kuniyoshi Hoshino
Kuniyoshi Hoshino
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Koji Fujimura
Hitachi, Ltd., Hitachi, Ibaraki, Japan
Akira Sasahira
Hitachi, Ltd., Hitachi, Ibaraki, Japan
Junichi Yamashita
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Tetsuo Fukasawa
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Kuniyoshi Hoshino
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Paper No:
ICONE16-48880, pp. 479-484; 6 pages
Published Online:
June 24, 2009
Citation
Fujimura, K, Sasahira, A, Yamashita, J, Fukasawa, T, & Hoshino, K. "Minor Actinides-Loaded FBR Core Concept Suitable for the Introductory Period." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance. Orlando, Florida, USA. May 11–15, 2008. pp. 479-484. ASME. https://doi.org/10.1115/ICONE16-48880
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