Development and Verification of the Thermal Behavior Analysis Code for MA Containing MOX Fuels
説明
<jats:p>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.</jats:p>
収録刊行物
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- 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
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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 2014-07-07
American Society of Mechanical Engineers