Mechanical analysis of the nuclear class 1 piping in HTR-10
AbstractAbstract
[en] Nuclear codes have detailed regulations on the mechanical analysis of nuclear Class 1 piping. But limited calculation facilities restrict the analysis of Class 1 piping, so that design safety requirements are not satisfied. This paper discusses the mechanical analysis of Class 1 piping using general-purpose finite element software. The general-purpose finite element software MARC is used to analyze a Class 1 piping system in HTR-10 to introduce the procedure for mechanical analysis and safety evaluation. The objective is to satisfy the regulations for the Class 1 piping in nuclear codes. The method introduced in this paper can be used as a practical method for mechanical analysis of a nuclear Class 1 piping
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Journal Article
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Journal of Tsinghua University. Science and Technology; ISSN 1000-0054; ; CODEN QDXKE8; v. 40(12); p. 14-17
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CALCULATION METHODS, COMPUTER CODES, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HTGR TYPE REACTORS, MATHEMATICAL SOLUTIONS, NUMERICAL SOLUTION, REACTORS, RESEARCH AND TEST REACTORS, STANDARDS, TEST FACILITIES, TEST REACTORS, TUBES
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