A preliminary study on seismic analysis of graphite cores for gas-cooled microreactor

<bold>Background</bold>Graphite serves as a vital structural material in high-temperature gas-cooled reactors. Ensuring its integrity under seismic loading is crucial for maintaining core safety.<bold>Purpose</bold>This study aims to assess the seismic response of a gas-cooled microreactor (GCMR) with graphite core and validate its compliance with the ASME design code.<bold>Methods</bold>GCMR with horizontal stacking structure of graphite components connected by pin keys was taken as seismic analysis object. Experimental collision tests and simulations involving small-scale graphite blocks were performed to determine stiffness and damping parameters. The finite element simulation calculation was carried out for several working conditions with oblique collision angle in the range of 0.01°~0.1°. Subsequently, a simplified core model incorporating equivalent spring-damper elements was developed and analyzed using time-history simulations to obtain the interaction force between graphite components, and the structure of GCMR with graphite core was evaluated by the failure probability method.<bold>Results</bold>Simulation and test results show that the Kelvin collision model successfully characterizes interactions between graphite blocks, exhibiting stiffness values ranging from 1.70×10<sup>9</sup> N∙m<sup>-1</sup> to 2.20×10<sup>9</sup> N∙m<sup>-1</sup> for collision angles of 0.02°~0.05°. The peak collision force between graphite components reaches 1.21×10<sup>5</sup> N. Stress assessment based on the Weibull distribution reveals a failure probability of less than 0.5% under design-level seismic loads.<bold>Conclusions</bold>The stiffness-equivalent method proposed in this study offers an effective means of simulating nonlinear core behavior, affirming the structural safety of the graphite core under seismic conditions.

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Publication Details

Journal
Nuclear Techniques
Published
2025-10-01
DOI
https://doi.org/10.3724/j.0253-3219.2025.hjs.48.250014
Citations
1
Primary Topic
Graphite, nuclear technology, radiation studies
Type
article
Field-Weighted Citation Impact
0.52

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article

A preliminary study on seismic analysis of graphite cores for gas-cooled microreactor

Tianyou Feng, Tianbao Lan, Zhong Huang, Sheng Feng
1 citations
Nuclear Techniques
Graphite, nuclear technology, radiation studies
0.52
article

A preliminary study on seismic analysis of graphite cores for gas-cooled microreactor

Tianyou Feng, Tianbao Lan, Zhong Huang, Sheng Feng
article en
1 citations

Abstract

<bold>Background</bold>Graphite serves as a vital structural material in high-temperature gas-cooled reactors. Ensuring its integrity under seismic loading is crucial for maintaining core safety.<bold>Purpose</bold>This study aims to assess the seismic response of a gas-cooled microreactor (GCMR) with graphite core and validate its compliance with the ASME design code.<bold>Methods</bold>GCMR with horizontal stacking structure of graphite components connected by pin keys was taken as seismic analysis object. Experimental collision tests and simulations involving small-scale graphite blocks were performed to determine stiffness and damping parameters. The finite element simulation calculation was carried out for several working conditions with oblique collision angle in the range of 0.01°~0.1°. Subsequently, a simplified core model incorporating equivalent spring-damper elements was developed and analyzed using time-history simulations to obtain the interaction force between graphite components, and the structure of GCMR with graphite core was evaluated by the failure probability method.<bold>Results</bold>Simulation and test results show that the Kelvin collision model successfully characterizes interactions between graphite blocks, exhibiting stiffness values ranging from 1.70×10<sup>9</sup> N∙m<sup>-1</sup> to 2.20×10<sup>9</sup> N∙m<sup>-1</sup> for collision angles of 0.02°~0.05°. The peak collision force between graphite components reaches 1.21×10<sup>5</sup> N. Stress assessment based on the Weibull distribution reveals a failure probability of less than 0.5% under design-level seismic loads.<bold>Conclusions</bold>The stiffness-equivalent method proposed in this study offers an effective means of simulating nonlinear core behavior, affirming the structural safety of the graphite core under seismic conditions.

Nuclear TechniquesVol. 48(10)
China National Nuclear Corporation
Openalex Percentile: Top 31%
Graphite, nuclear technology, radiation studies
0.52
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