Preliminary analysis of safety performance for accident-tolerant fuel
Creators
- 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
- 2. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an (China)
Description
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. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 54
- Journal Issue
- 8
- Journal Page Range
- p. 1441-1447
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55097316
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCIDENTS; ACCIDENT-TOLERANT NUCLEAR FUELS; CLADDING; COMPARATIVE EVALUATIONS; FUEL CANS; HYDROGEN; OXIDATION; PELLETS; R CODES; SAFETY ANALYSIS; STEADY-STATE CONDITIONS; TEMPERATURE GRADIENTS; TEMPERATURE RANGE 0400-1000 K; THERMAL CONDUCTIVITY; TRANSIENTS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; COMPUTER CODES; DEPOSITION; ELEMENTS; ENERGY SOURCES; EVALUATION; FUELS; MATERIALS; NONMETALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR MATERIALS; SURFACE COATING; TEMPERATURE RANGE; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 6 figs., 5 tabs., 16 refs.; http://dx.doi.org/10.7538/yzk.2019.youxian.0563