Published April 2016 | Version v1
Journal article Metadata-only

Thermal property analysis of accident tolerance fuel pellet

Creators

  • 1. China Nuclear Power Technology Research Institute, Shenzhen (China)

Description

In this paper, CFX has been used to simulate the thermal behaviors of UO2-Mo, UO2-SiC, UO2-BeO, U-Si, FCM and current UO2 fuel pellet under normal condition and accident condition, then evaluation has been made based on the simulation results. It turns out that FCM fuel has advantages due to its ability of thermal conductivity and resistance. (authors)

Additional details

Identifiers

DOI
10.13832/j.jnpe.2016.02.0082;

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
37
Journal Issue
2
Journal Page Range
p. 82-86
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
50036330
Subject category
S36: MATERIALS SCIENCE;
Descriptors DEI
BERYLLIUM OXIDES; EVALUATION; FUEL PELLETS; MOLYBDENUM; NUMERICAL ANALYSIS; REACTOR ACCIDENTS; SILICON; SILICON CARBIDES; SIMULATION; THERMAL CONDUCTIVITY; URANIUM; URANIUM DIOXIDE
Descriptors DEC
ACCIDENTS; ACTINIDE COMPOUNDS; ACTINIDES; ALKALINE EARTH METAL COMPOUNDS; BERYLLIUM COMPOUNDS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; ELEMENTS; MATHEMATICS; METALS; OXIDES; OXYGEN COMPOUNDS; PELLETS; PHYSICAL PROPERTIES; REFRACTORY METALS; SEMIMETALS; SILICON COMPOUNDS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENTS; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
7 figs., 1 tab., 13 refs.; http://dx.doi.org/10.13832/j.jnpe.2016.02.0082