Numerical study on material behavior and core temperature field evolution under CDAs in LFR

Preventing radioactive leakage following a Core Disruptive Accident (CDA) is crucial for protecting the environment and human health. To mitigate such consequences, understanding in-reactor behavior is essential. In this study, a two-dimensional, three-velocity-field and multicomponent simulation code, ACENA, developed at XJTU, is employed to analyze CDA scenarios in the STAR-LM design. Steady-state results are first validated against design parameters to ensure model accuracy, and a hypothetical transient is then introduced to trigger CDA onset. The coupling between damaged core materials and coolant thermal–hydraulic fields is investigated, with particular focus on the motion and distribution of fuel particles with different densities. Results show that low-density fuel particles do not float to the coolant surface but accumulate at the interface between high- and low-temperature regions due to temperature-dependent coolant density variations. Various accident scenarios are further examined to assess material behavior and potential threats to reactor integrity. It is found that local Fuel Blockage Accidents (FBA) cause limited core degradation owing to structural confinement and sufficient cooling when the Primary Heat Exchanger (PHX) remains active, though transient boiling may occur. The study demonstrates ACENA’s capability for detailed CDA analysis in Liquid Metal Fast Reactors (LMFRs).

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Publication Details

Journal
Nuclear Engineering and Technology
Published
2025-11-05
DOI
https://doi.org/10.1016/j.net.2025.104020
Citations
2
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
1.04
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article

Numerical study on material behavior and core temperature field evolution under CDAs in LFR

Yaomin Cai, Suizheng Qiu, Wenxi Tian, Yapeng Liu et al.
2 citations
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Nuclear Materials and Properties
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article

Numerical study on material behavior and core temperature field evolution under CDAs in LFR

Yaomin Cai, Suizheng Qiu, Wenxi Tian, Yapeng Liu, Pengrui Qiao, Peng Du, Yue Lin, Dalin Zhang, Guanghui Su
article en
2 citations

Abstract

Preventing radioactive leakage following a Core Disruptive Accident (CDA) is crucial for protecting the environment and human health. To mitigate such consequences, understanding in-reactor behavior is essential. In this study, a two-dimensional, three-velocity-field and multicomponent simulation code, ACENA, developed at XJTU, is employed to analyze CDA scenarios in the STAR-LM design. Steady-state results are first validated against design parameters to ensure model accuracy, and a hypothetical transient is then introduced to trigger CDA onset. The coupling between damaged core materials and coolant thermal–hydraulic fields is investigated, with particular focus on the motion and distribution of fuel particles with different densities. Results show that low-density fuel particles do not float to the coolant surface but accumulate at the interface between high- and low-temperature regions due to temperature-dependent coolant density variations. Various accident scenarios are further examined to assess material behavior and potential threats to reactor integrity. It is found that local Fuel Blockage Accidents (FBA) cause limited core degradation owing to structural confinement and sufficient cooling when the Primary Heat Exchanger (PHX) remains active, though transient boiling may occur. The study demonstrates ACENA’s capability for detailed CDA analysis in Liquid Metal Fast Reactors (LMFRs).

Nuclear Engineering and TechnologyVol. 58(3)
Chengdu Institute of Information Technology (China) (CN), China Institute of Atomic Energy (CN), Xi'an Jiaotong University (CN)
Openalex Percentile: Top 21%
Nuclear Materials and Properties
1.04
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