Preliminary Analysis of Safety Performance for Accident-tolerant Fuel

被引：0

作者：

Yang H. ^{[1
]}

Wu Y. ^{[2
]}

Yin S. ^{[1
]}

Liu M. ^{[1
]}

Wang Y. ^{[1
]}

Lai J. ^{[1
]}

Liao X. ^{[1
]}

Xie H. ^{[1
]}

Wang J. ^{[1
]}

Ouyang B. ^{[1
]}

机构：

[1] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu

[2] School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an

来源：

| 1600年 / Atomic Energy Press卷 / 54期

关键词：

Accident-tolerant capacity; Accident-tolerant fuel; High temperature oxidation resistance; RELAP5; program;

D O I：

10.7538/yzk.2019.youxian.0563

中图分类号：

学科分类号：

摘要：

Accident-tolerant fuel (ATF) is to enhance the accident-tolerant capacity of nuclear fuel by improving the thermal properties of fuel materials or the high temperature oxidation resistance of cladding materials, so that nuclear fuel can endure serious accidents for a long time. Using RELAP5 program developed for ATF, safety analysis of UO2-FeCrAl, FCM-FeCrAl and conventional nuclear fuel UO2-Zir-4 was carried out. Compared with conventional UO2 pellets, FCM pellets with higher thermal conductivity have lower fuel center temperature and smaller radial fuel temperature gradient under steady state operating conditions. FCM pellets also have lower transient initial temperature and lower fuel temperature growth rate under transient accident condition. Compared with conventional cladding Zir-4, the peak cladding temperature of FeCrAl is smaller and reaches later under transient accident condition. Meanwhile, due to the better high temperature oxidation resistance of FeCrAl cladding, the smaller hydrogen mass production is produced during the accident progress. © 2020, Editorial Board of Atomic Energy Science and Technology. All right reserved.

引用

页码：1441 / 1447

页数：6

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