• Title/Summary/Keyword: Pressurized water reactor

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A Study on the Buckling Characteristics of Spacer Grids in Pressurized Water Reactor Fuel Assembly (경수로용 핵연료집합체 지지격자의 좌굴특성에 관한 연구)

  • Jeon Sang-Youn;Lee Young-Shin
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.18 no.4 s.70
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    • pp.405-416
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    • 2005

  • This study contains the static buckling tests and static buckling analyses for small size grids and full size grids. The buckling tests and finite element analyses were performed to evaluate the buckling characteristics of the spacer grids in a pressurized water reactor fuel assembly and to evaluate the possibility of the prediction lot the buckling strength of spacer grids. The buckling tests were performed for small size grids and full size grids, and the correlations between buckling strength and the number of straps and the correlations between buckling strength and the number of rows are derived based on the test results. The static buckling analyses were performed to identify the effect of the number of rows and the number of columns on the buckling strength of spacer grid by a finite element method using ANSYS program and the results were compared with the buckling test results.

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Interference Check for Reactor In-Core Instrumentation Guide Tube Routing (원자로 노내계측기 안내관의 배열을 위한 간섭검증)

  • Cho, Duk-Sang
    • Journal of the Korean Society of Industry Convergence
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    • v.3 no.3
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    • pp.201-207
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    • 2000

  • In this study, methodologies for checking the interference between in-core instrumentation (ICI) guide tubes for routing of ICI guide tubes in the reactor coolant system of typical Pressurized Water Reactor under cold and normal operation (NOP) conditions are presented. The closest points of ICI guide tubes under cold condition are calculated by using minimize technique and are used as data for NOP analysis. Movements of ICI guide tubes under NOP condition are performed by the commercial computer code, SUPERPIPE.

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