Contact visco-elastic stress analysis using finite element method
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki(Japan). Tokai Research Establishment
Description
In a high temperature gas-cooled reactor, thermal performance of an annular fuel rod is superior to that of the hollow rod. Differential thermal expansion and shrinkage, however, cause closure of the gap between fuel compact and inner graphite sleeve, producing larger stress of the compact and sleeve than in the hollow rod. The contact between compact and sleeve must be fully considered, in design of the annular fuel rod. Calculational method of this contact visco-elastic problem with the finite element method(FEM) for the annular fuel rod of HTGR is described. FEM results of the simplified problem are compared with those by an analytical one, and adequacy of the former is shown. The FEM is useful for stress analysis of the fuel in multi-purpose experimental very high temperature gas-cooled reactor. It is also applicable to other contact problems such as the pellet clad mechanical interaction in LWR or FBR fuels. (auth.)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.19.774Abstract (Japanese)
本報は、有限要素法による接触粘弾性応力解析についてその解析手法を述べ、黒鉛燃料の応力解析に適用して、解析手法の妥当性を解析解と比較することによって示し、さらに、この手法を多目的高温ガス実験炉の燃料応力解析に使用して、その有用姓を示したものである。 (著者)Additional details
Additional titles
- Original title (Japanese)
- 有限要素法による接触粘弾性応力解析
Identifiers
- DOI
- 10.3327/jaesj.19.774;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 19
- Journal Issue
- 11
- Journal Page Range
- p. 774-781
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53100834
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ANNULAR FUEL ELEMENTS; ELASTICITY; FINITE ELEMENT METHOD; FUEL-CLADDING INTERACTIONS; GRAPHITE; HTGR TYPE REACTORS; NUMERICAL SOLUTION; PERFORMANCE; PHYSICAL RADIATION EFFECTS; SHRINKAGE; STRESS ANALYSIS; THERMAL EXPANSION
- Descriptors DEC
- CALCULATION METHODS; CARBON; ELEMENTS; EXPANSION; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; MINERALS; NONMETALS; NUMERICAL SOLUTION; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 3412000; This record replaces 09392257