The metal fuel core is superior to the mixed oxide fuel core because of its higher breeding ratio and compact core size resulting from neutron economics, hard neutron spectrum, and high content of heavy metal nuclides. Meanwhile, the metal fuel core exhibits the characteristic of a lower allowable maximum cladding temperature. Utilizing the advantage of the metal fuel core, conceptual sodium-cooled fast breeder reactor designs have been pursued for the attractive core properties of high breeding ratio, small inventory, compact size, low sodium void reactivity, and high transmutation ratio of the minor actinides. Among attractive cores, a conceptual design for a high breeding ratio was performed without blanket fuels. The design conditions were set so a sodium void reactivity of less than 8 $, a core height of less than 150 cm, a maximum cladding temperature of 650 °C, and a fuel pin bundle pressure drop of 0.4MPa. The breeding ratio of the resultant core was 1.34 without blanket fuels.
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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
Study on Enhanced Performance Sodium-Cooled Metal Fuel Core Concepts by Adopting Advanced Fuel and Flexible Design Criteria
Noboru Kobayashi,
Noboru Kobayashi
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Takashi Ogawa,
Takashi Ogawa
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Shigeo Ohki,
Shigeo Ohki
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Tomoyasu Mizuno,
Tomoyasu Mizuno
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Takanari Ogata
Takanari Ogata
Central Research Institute of Electric Power Industry, Ibaraki, Japan
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Noboru Kobayashi
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Takashi Ogawa
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Shigeo Ohki
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Tomoyasu Mizuno
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Takanari Ogata
Central Research Institute of Electric Power Industry, Ibaraki, Japan
Paper No:
ICONE16-48469, pp. 373-381; 9 pages
Published Online:
June 24, 2009
Citation
Kobayashi, N, Ogawa, T, Ohki, S, Mizuno, T, & Ogata, T. "Study on Enhanced Performance Sodium-Cooled Metal Fuel Core Concepts by Adopting Advanced Fuel and Flexible Design Criteria." 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. 373-381. ASME. https://doi.org/10.1115/ICONE16-48469
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