Development and validation of FRAT code for coated particle fuel failure analysis

被引:3
作者
Li, Jian [1 ]
She, Ding [1 ]
Shi, Lei [1 ]
Sun, Jun [1 ]
机构
[1] Tsinghua Univ, Inst Nucl & New Energy Technol, Collaborat Innovat Ctr Adv Nucl Energy Technol, Key Lab Adv Reactor Engn & Safety,Minist Educ, Beijing 100084, Peoples R China
基金
中国博士后科学基金;
关键词
TRISO-coated fuel particlc; Fuel performance; FRAT; IAEA CRP-6 benchmark; Code validation;
D O I
10.1016/j.net.2022.06.025
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
TRISO-coated particle fuel is widely used in high temperature gas cooled reactors and other advanced reactors. The performance of coated fuel particle is one of the fundamental bases of reactor safety. The failure probability of coated fuel particle should be evaluated and determined through suitable fuel performance models and methods during normal and accident condition. In order to better facilitate the design of coated particle fuel, a new TRISO fuel performance code named FRAT (Fission product Release Analysis Tool) was developed. FRAT is designed to calculate internal gas pressure, mechanical stress and failure probability of a coated fuel particle. In this paper, FRAT was introduced and benchmarked against IAEA CRP-6 benchmark cases for coated particle failure analysis. FRAT's results agree well with bench-mark values, showing the correctness and satisfactory applicability. This work helps to provide a foun-dation for the credible application of FRAT.(c) 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
引用
收藏
页码:4049 / 4061
页数:13
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