Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Analysis of several VERA benchmark problems with the photon transport capability of STREAM

  • Mai, Nhan Nguyen Trong (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Kim, Kyeongwon (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Lemaire, Matthieu (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Nguyen, Tung Dong Cao (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Lee, Woonghee (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Lee, Deokjung (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology)
  • Received : 2021.11.10
  • Accepted : 2022.02.05
  • Published : 2022.07.25
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Abstract

STREAM - a lattice transport calculation code with method of characteristics for the purpose of light water reactor analysis - has been developed by the Computational Reactor Physics and Experiment laboratory (CORE) of the Ulsan National Institute of Science and Technology (UNIST). Recently, efforts have been taken to develop a photon module in STREAM to assess photon heating and the influence of gamma photon transport on power distributions, as only neutron transport was considered in previous STREAM versions. A multi-group photon library is produced for STREAM based on the ENDF/B-VII.1 library with the use of the library-processing code NJOY. The developed photon solver for the computation of 2D and 3D distributions of photon flux and energy deposition is based on the method of characteristics like the neutron solver. The photon library and photon module produced and implemented for STREAM are verified on VERA pin and assembly problems by comparison with the Monte Carlo code MCS - also developed at UNIST. A short analysis of the impact of photon transport during depletion and thermal hydraulics feedback is presented for a 2D core also from the VERA benchmark.

Keywords

Acknowledgement

This work was supported by Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government (MOTIE) (20206510100040).

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