2016
DOI: 10.1080/00223131.2016.1152921
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Seismic analysis of the APR 1400 reactor vessel internals using the model reduction method

Abstract: To secure reliability of the seismic design of the reactor vessel internals (RVIs) through the finite element analysis, it is important to develop the accurate analysis model which can represent the geometric complexity of the RVIs. However, the seismic analysis requires too large computation cost to solve the complex equations; thus, it needs to reduce the overall size of the analysis model. Here, we apply a model reduction method based on the fixed-interface component mode synthesis (CMS) method to practical… Show more

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Cited by 19 publications
(2 citation statements)
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“…This segment discusses the procedure of developing reduced spacer grid models of the spacer grid. The spacer grid model selected for this study was a mid spacer grid of PLUS7 nuclear fuel for OPR1000 and APR1400 which was an improved design to enhance the fuel efficiency and performance [13]. Using a full spacer grid model for FEA requires a high-performance computer and a huge amount of time since it results in a very large analytical model with 1,057,855 nodes and 383,867 elements.…”
Section: Methods Of Obtaining Optimized Fa Modelmentioning
confidence: 99%
“…This segment discusses the procedure of developing reduced spacer grid models of the spacer grid. The spacer grid model selected for this study was a mid spacer grid of PLUS7 nuclear fuel for OPR1000 and APR1400 which was an improved design to enhance the fuel efficiency and performance [13]. Using a full spacer grid model for FEA requires a high-performance computer and a huge amount of time since it results in a very large analytical model with 1,057,855 nodes and 383,867 elements.…”
Section: Methods Of Obtaining Optimized Fa Modelmentioning
confidence: 99%
“…The Japan Nuclear Energy Safety Organization (JNES) constructed a full-scale model in which base isolation systems were applied to the control room of a nuclear power plant, and a shaking table test was conducted in order to evaluate the seismic stability of the model [23]. In Korea, various experimental and analytical studies have been conducted on the application of base isolation systems to Advanced Power Reactor 1400 (APR1400) in order to reinforce the safety of nuclear power plants in the country [24,25].…”
Section: Introductionmentioning
confidence: 99%