Published December 2016 | Version v1
Journal article Metadata-only

FCM fuel thermal performance analysis

Creators

  • 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute China, Chengdu (China)

Description

In this paper, the method to analyze the FCM fuel thermal performance using finite element software ABAQUS is studied, and the comparative analysis of thermal performance of FCM pellet and UO2 pellet is carried out. The results show that the temperature distribution trend of FCM pellet is similar with that of UO2 pellet but with a strong non-uniformity. The temperature of FCM pellet is much lower than that of UO2 pellet under typical PWR operating environment. The temperature of FCM is not sensitive to the burnup change at the same linear power density and the temperature increase rate of FCM pellet is much lower than that of UO2 pellet along with the linear power density increment at the same fuel burnup. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
37
Journal Issue
6
Journal Page Range
p. 150-154
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
52044231
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
A CODES; ACCIDENT-TOLERANT NUCLEAR FUELS; BURNUP; COMPUTER CODES; FINITE ELEMENT METHOD; FUELS; PELLETS; PERFORMANCE; POWER DENSITY; PWR TYPE REACTORS; TEMPERATURE DISTRIBUTION; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; MATHEMATICAL SOLUTIONS; NUCLEAR FUELS; NUMERICAL SOLUTION; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
7 figs., 3 tabs., 4 refs.