科技报告详细信息
AGR-1 Safety Test Predictions using the PARFUME code
Collin, Blaise
Idaho National Laboratory
关键词: Probability;    Fuel Particles;    Diffusion;    Irradiation;    Ngnp + Tdo + Vhtr + R&;   
DOI  :  10.2172/1048407
RP-ID  :  INL/EXT-12-26014
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1048407
美国|英语
来源: UNT Digital Library
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【 摘 要 】

The PARFUME modeling code was used to predict failure probability of TRISO-coated fuel particles and diffusion of fission products through these particles during safety tests following the first irradiation test of the Advanced Gas Reactor program (AGR-1). These calculations support the AGR-1 Safety Testing Experiment, which is part of the PIE effort on AGR-1. Modeling of the AGR-1 Safety Test Predictions includes a 620-day irradiation followed by a 300-hour heat-up phase of selected AGR-1 compacts. Results include fuel failure probability, palladium penetration, and fractional release of fission products. Results show that no particle failure is predicted during irradiation or heat-up, and that fractional release of fission products is limited during irradiation but that it significantly increases during heat-up.

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