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SPERT III E-Core critical experiment benchmarks calculation with NECP-X and KENO-VI

  • Chen Zhao
  • , Qicang Shen
  • , Zhouyu Liu
  • , Lu Cao
  • , Thomas Downar
  • , Liangzhi Cao
  • Xi'an Jiaotong University
  • University of Michigan, Ann Arbor

科研成果: 书/报告/会议事项章节会议稿件同行评审

摘要

The Special Power Excursion Reactor Test (SPERT) III E-Core is a small experimental reactor towards experimental and theoretical investigations of kinetic and safety behavior of nuclear reactors. The SPERT III E-core model was established with a high-fidelity direct whole-core transport code NECP-X and a Monte Carlo code KENO-VI. All components of the reactor core were explicitly modeled and a serial of steady-state cases, ranging from 2D lattice to 3D whole core, were calculated. The complicated geometry of transient rods is modeled by the Constructive Solid Geometry (CSG) method in NECP-X. Numerical results indicate that NECP-X shows the good agreement with KENO-VI for all test cases.

源语言英语
主期刊名International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
出版商American Nuclear Society
2619-2627
页数9
ISBN(电子版)9780894487699
出版状态已出版 - 2019
活动2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 - Portland, 美国
期限: 25 8月 201929 8月 2019

出版系列

姓名International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019

会议

会议2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019
国家/地区美国
Portland
时期25/08/1929/08/19

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