In order to develop a minor actinide (MA) containing MOX (MA-MOX) fuel design method, the analysis models to predict irradiation behavior of MA-MOX fuel have to be developed and the accuracy of the irradiation behavior analysis code should be evaluated with the results of post-irradiation examinations (PIEs) for MA-MOX fuels. In this study, we developed the computer module TRANSIT (Thermal Property and Vapor Pressure Analysis Module for Minor Actinide Containing MOX Fuel) to compute thermal properties of MA-MOX fuel. TRANSIT can give thermal conductivity, melting temperature and vapor pressures of MA-MOX. By using this module, we improved the thermal behavior analysis code DIRAD and developed the DIRAD-TRANSIT code system to compute the irradiation behavior of MA-MOX fuel. This system was verified with the results of PIEs for the conventional MOX fuels and the MA-MOX fuels irradiated in the experimental fast reactor JOYO. As the result of the verification, we determined that the DIRAD-TRANSIT code system would precisely predict the fuel thermal behavior, i.e. fuel temperature and fuel restructuring, for oxide fuels containing several percent minor actinides.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4589-9
PROCEEDINGS PAPER
Development and Verification of the Thermal Behavior Analysis Code for MA Containing MOX Fuels
Yoshihisa Ikusawa,
Yoshihisa Ikusawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Takayuki Ozawa,
Takayuki Ozawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Shun Hirooka,
Shun Hirooka
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Koji Maeda,
Koji Maeda
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Masato Kato,
Masato Kato
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Seiichiro Maeda
Seiichiro Maeda
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Yoshihisa Ikusawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Takayuki Ozawa
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Shun Hirooka
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Koji Maeda
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Masato Kato
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Seiichiro Maeda
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Paper No:
ICONE22-30005, V001T02A001; 6 pages
Published Online:
November 17, 2014
Citation
Ikusawa, Y, Ozawa, T, Hirooka, S, Maeda, K, Kato, M, & Maeda, S. "Development and Verification of the Thermal Behavior Analysis Code for MA Containing MOX Fuels." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues. Prague, Czech Republic. July 7–11, 2014. V001T02A001. ASME. https://doi.org/10.1115/ICONE22-30005
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