Seismic responses of nuclear reactor vessel internals considering coolant flow under operating conditions
Nuclear power generates a large portion of the energy used today and plays an important role in energy development. To ensure safe nuclear power generation, it is essential to conduct an accurate analysis of reactor structural integrity. Accordingly, in this study, a methodology for obtaining accura...
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| Published in: | Nuclear engineering and technology Vol. 51; no. 6; pp. 1658 - 1668 |
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| Main Authors: | , , , , |
| Format: | Journal Article |
| Language: | English |
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Elsevier
01-09-2019
한국원자력학회 |
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| Abstract | Nuclear power generates a large portion of the energy used today and plays an important role in energy development. To ensure safe nuclear power generation, it is essential to conduct an accurate analysis of reactor structural integrity. Accordingly, in this study, a methodology for obtaining accurate structural responses to the combined seismic and reactor coolant loads existing prior to the shutdown of a nuclear reactor is proposed. By applying the proposed analysis method to the reactor vessel internals, it is possible to derive the seismic responses considering the influence of the hydraulic loads present during operation for the first time. The validity of the proposed methodology is confirmed in this research by using the finite element method to conduct seismic and hydraulic load analyses of the advanced APR1400 1400 MWe power reactor, one of the commercial reactors. The structural responses to the combined applied loads are obtained using displacement-based and stress-based superposition methods. The safety of the subject nuclear reactor is then confirmed by analyzing the design margin according to the American Society for Mechanical Engineers (ASME) evaluation criteria, demonstrating the promise of the proposed analysis method. Keywords: Nuclear reactor internals, Seismic analysis, Finite element analysis, Pump-pulsation, Turbulence, Displacement-based stress assessment |
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| AbstractList | Nuclear power generates a large portion of the energy used today and plays an important role in energy development. To ensure safe nuclear power generation, it is essential to conduct an accurate analysis of reactor structural integrity. Accordingly, in this study, a methodology for obtaining accurate structural responses to the combined seismic and reactor coolant loads existing prior to the shutdown of a nuclear reactor is proposed. By applying the proposed analysis method to the reactor vessel internals, it is possible to derive the seismic responses considering the influence of the hydraulic loads present during operation for the first time. The validity of the proposed methodology is confirmed in this research by using the finite element method to conduct seismic and hydraulic load analyses of the advanced APR1400 1400 MWe power reactor, one of the commercial reactors. The structural responses to the combined applied loads are obtained using displacement-based and stress-based superposition methods. The safety of the subject nuclear reactor is then confirmed by analyzing the design margin according to the American Society for Mechanical Engineers (ASME) evaluation criteria, demonstrating the promise of the proposed analysis method. Keywords: Nuclear reactor internals, Seismic analysis, Finite element analysis, Pump-pulsation, Turbulence, Displacement-based stress assessment Nuclear power generates a large portion of the energy used today and plays an important role in energydevelopment. To ensure safe nuclear power generation, it is essential to conduct an accurate analysis ofreactor structural integrity. Accordingly, in this study, a methodology for obtaining accurate structuralresponses to the combined seismic and reactor coolant loads existing prior to the shutdown of a nuclearreactor is proposed. By applying the proposed analysis method to the reactor vessel internals, it ispossible to derive the seismic responses considering the influence of the hydraulic loads present duringoperation for the first time. The validity of the proposed methodology is confirmed in this research byusing the finite element method to conduct seismic and hydraulic load analyses of the advancedAPR1400 1400 MWe power reactor, one of the commercial reactors. The structural responses to thecombined applied loads are obtained using displacement-based and stress-based superpositionmethods. The safety of the subject nuclear reactor is then confirmed by analyzing the design marginaccording to the American Society for Mechanical Engineers (ASME) evaluation criteria, demonstratingthe promise of the proposed analysis method. KCI Citation Count: 0 |
| Author | Park, Jong-beom Park, No-Cheol Kim, Yong-beom Lee, Eun-ho Lee, Sang-Jeong |
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