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.
| Original language | English |
|---|---|
| Pages (from-to) | 1658-1668 |
| Number of pages | 11 |
| Journal | Nuclear Engineering and Technology |
| Volume | 51 |
| Issue number | 6 |
| DOIs | |
| Publication status | Published - 2019 Sep |
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All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
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Seismic responses of nuclear reactor vessel internals considering coolant flow under operating conditions. / Park, Jong beom; Lee, Sang Jeong; Lee, Eun ho; Park, No Cheol; Kim, Yong beom.
In: Nuclear Engineering and Technology, Vol. 51, No. 6, 09.2019, p. 1658-1668.Research output: Contribution to journal › Article
TY - JOUR
T1 - Seismic responses of nuclear reactor vessel internals considering coolant flow under operating conditions
AU - Park, Jong beom
AU - Lee, Sang Jeong
AU - Lee, Eun ho
AU - Park, No Cheol
AU - Kim, Yong beom
PY - 2019/9
Y1 - 2019/9
N2 - 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.
AB - 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.
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UR - http://www.scopus.com/inward/citedby.url?scp=85070193383&partnerID=8YFLogxK
U2 - 10.1016/j.net.2019.04.013
DO - 10.1016/j.net.2019.04.013
M3 - Article
AN - SCOPUS:85070193383
VL - 51
SP - 1658
EP - 1668
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
SN - 1738-5733
IS - 6
ER -