3D finite element analysis of a nuclear fuel rod with gap elements between the pellet and the cladding

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Nuclear fuel rods which comprises an important component of a nuclear power plant are composed of nuclear fuel and cladding. Simulating the nuclear fuel rod using a computer program is the universal method to verify its safety. The computer program used for this is called the fuel performance code. The main objective of this study is to simulate the nuclear fuel rod behavior considering the gap conductance using three-dimensional gap elements. Gap elements are used because, unlike other methods, this approach does not require special methods or other variables such as the Lagrange multiplier. In this work, a nuclear fuel rod has been simulated and the results are compared with the experimental results.
Publisher
TAYLOR FRANCIS LTD
Issue Date
2016-02
Language
English
Article Type
Article
Citation

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.53, no.2, pp.232 - 239

ISSN
0022-3131
DOI
10.1080/00223131.2015.1037374
URI
http://hdl.handle.net/10203/205483
Appears in Collection
ME-Journal Papers(저널논문)
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