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Round Robin Analysis to Investigate Sensitivity of Analysis Results to Finite Element Elastic-Plastic Analysis Variables for Nuclear Safety Class 1 Components under Severe Seismic Load

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주제분류원자력공학

초록

As a part of round robin analysis to develop a finite element elastic-plastic seismic analysis procedure fornuclear safety class 1 components, a series of parametric analyses was carried out on the simulatedpressurizer surge line system model to investigate sensitivity of the analysis results to finite elementanalysis variables. The analysis on the surge line system model considered dynamic effect due to theseismic load corresponding to PGA 0.6 g and elastic-plastic material behavior based on the Chabochecombined hardening model. From the parametric analysis results, it was found that strains such asaccumulated equivalent plastic strain and equivalent plastic strain are more sensitive to the analysisvariables than von Mises effect stress. The parametric analysis results also identified that finite elementdensity and ovalization option in the elbow elements have more significant effect on the analysis resultsthan the other variables.

Abstract

As a part of round robin analysis to develop a finite element elastic-plastic seismic analysis procedure fornuclear safety class 1 components, a series of parametric analyses was carried out on the simulatedpressurizer surge line system model to investigate sensitivity of the analysis results to finite elementanalysis variables. The analysis on the surge line system model considered dynamic effect due to theseismic load corresponding to PGA 0.6 g and elastic-plastic material behavior based on the Chabochecombined hardening model. From the parametric analysis results, it was found that strains such asaccumulated equivalent plastic strain and equivalent plastic strain are more sensitive to the analysisvariables than von Mises effect stress. The parametric analysis results also identified that finite elementdensity and ovalization option in the elbow elements have more significant effect on the analysis resultsthan the other variables.

참고문헌 (20)

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  7. Codes for Nuclear Power Generation Facilities e Rules on Design and Construction for Nuclear Power Plant: Alternative Design for Seismic Design of Seismic S Class Steel Piping Based on Elastic-Plastic Response Analysis, "JSME", NCCC, ~, pp.NCCC-008 (2019)
  8. 김종성, "Simplified elastic-plastic analysis procedure for strain-based fatigue assessment of nuclear safety class 1 components under severe seismic loads", Nuclear Engineering and Technology, 52(12), pp.2918~2927 (2020), 한국원자력학회[DOI]
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  12. "APR1400 Design Control Document Tier 2, APR1400-K-X-FS-14002-NP, Revision 0", ~ (2014)
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