Published July 1, 2021 | Version v1
Journal article

Finite element analysis of temperature field of nuclear fuel cladding tube

  • 1. School of Mechanical Engineering, University of South China, Hengyang (China)

Description

In this paper, the finite element software ANSYS is used to analyse the influence of the eccentricity of nuclear fuel pellet on the temperature field of the cladding tube. Furthermore, transient heat conduction analysis of a single fuel rod during a loss of coolant accident is carried out. It can be found that the pellet bias has little effect on the temperature difference between the inner and outer walls of cladding tube, but it has a great influence on the temperature of the pellet center. The results obtained by transient analysis show that the cladding tube will melt within 738 seconds in the loss of coolant accident. (paper)

Availability note (English)

Available from http://dx.doi.org/10.1088/1742-6596/1985/1/012061

Additional details

Publishing Information

Journal Title
Journal of Physics. Conference Series (Online)
Journal Volume
1985
Journal Issue
1
Journal Page Range
[5 p.]
ISSN
1742-6596

Conference

Title
5. International Conference on Fluid Mechanics and Industrial Applications
Acronym
FMIA 2021
Dates
26-27 Jun 2021
Place
Taiyuan Citry (China)

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
53086494
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CLADDING; COMPUTER CODES; FINITE ELEMENT METHOD; FUEL PELLETS; FUEL RODS; LOSS OF COOLANT; NUCLEAR FUELS; THERMAL CONDUCTION; TRANSIENTS; TUBES
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; DEPOSITION; ENERGY SOURCES; ENERGY TRANSFER; FUEL ELEMENTS; FUELS; HEAT TRANSFER; MATERIALS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; PELLETS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; SURFACE COATING