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事故容错燃料安全性能初步分析

Translated title of the contribution: Preliminary Analysis of Safety Performance for Accident-tolerant Fuel
  • Hongfa Yang
  • , Yingwei Wu
  • , Shasha Yin
  • , Minghao Liu
  • , Yu Wang
  • , Jianyong Lai
  • , Xianwei Liao
  • , Haiyan Xie
  • , Jiarui Wang
  • , Bin Ouyang
  • Nuclear Power Institute of China

Research output: Contribution to journalArticlepeer-review

3 Scopus citations

Abstract

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.

Translated title of the contributionPreliminary Analysis of Safety Performance for Accident-tolerant Fuel
Original languageChinese (Traditional)
Pages (from-to)1441-1447
Number of pages7
JournalYuanzineng Kexue Jishu/Atomic Energy Science and Technology
Volume54
Issue number8
DOIs
StatePublished - 20 Aug 2020

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