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Investigation of the modified RELAP5 MOD 3.2 capability to simulate the transients of the fluoride-salt high-temperature reactors

  • Limin Liu
  • , Qiqi Yan
  • , Dalin Zhang
  • , Suizheng Qiu
  • , G. H. Su
  • Xi'an Jiaotong University

科研成果: 书/报告/会议事项章节会议稿件同行评审

1 引用 (Scopus)

摘要

Fluoride-salt-cooled high-temperature reactors (FHRs) are a new concept that uses solid fuel and employs high temperature liquid salts as both primary and secondary side working fluids. The thermo-physical properties of the fluoride salts and specific heat transfer correlations have been implemented into the RELAP5-MOD3.2 code to enable the code to simulate the transient thermal-hydraulic response in accidents. The thermophysical properties calculated by the modified code have been benchmarked versus the experimental data. The results of thermal-hydraulic responses of the PB-AHTR in the steady state and simple loss of forced flow from the publications using the RELAP5-3D are used to verify the ability of the modified RELAP5-MOD3.2 to simulate the transients of the FHRs. The code can predict the variations of the thermalhydraulic parameters well whereas some results may distinguish from that calculated by the RELAP5-3D. The unprotected loss of flow is analyzed by the modified code, indicating that the passive residual heat removal system can mitigate the consequence of the accidents.

源语言英语
主期刊名Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues
出版商American Society of Mechanical Engineers (ASME)
ISBN(电子版)9780791850022
DOI
出版状态已出版 - 2016
活动2016 24th International Conference on Nuclear Engineering, ICONE 2016 - Charlotte, 美国
期限: 26 6月 201630 6月 2016

丛书

姓名International Conference on Nuclear Engineering, Proceedings, ICONE
2

会议

会议2016 24th International Conference on Nuclear Engineering, ICONE 2016
国家/地区美国
Charlotte
时期26/06/1630/06/16

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