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Verification of a two-step code system MCS/RAST-F to fast reactor core analysis

  • Tran, Tuan Quoc (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Cherezov, Alexey (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Du, Xianan (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Lee, Deokjung (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology)
  • Received : 2021.07.26
  • Accepted : 2021.10.25
  • Published : 2022.05.25

Abstract

RAST-F is a new full-core analysis code based on the two-step approach that couples a multi-group cross-section generation Monte-Carlo code MCS and a multi-group nodal diffusion solver. To demonstrate the feasibility of using MCS/RAST-F for fast reactor analysis, this paper presents the coupled nodal code verification results for the MET-1000 and CAR-3600 benchmark cores. Three different multi-group cross-section calculation schemes are employed to improve the agreement between the nodal and reference solutions. The reference solution is obtained by the MCS code using continuous-energy nuclear data. Additionally, the MCS/RAST-F nodal solution is verified with results based on cross-section generated by collision probability code TULIP. A good agreement between MCS/RAST-F and reference solution is observed with less than 120 pcm discrepancy in keff and less than 1.2% root-mean-square error in power distribution. This study confirms the two-step approach MCS/RAST-F as a reliable tool for the three-dimensional simulation of reactor cores with fast spectrum.

Keywords

Acknowledgement

This work was partially supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT). (No.NRF-2017M2A8A2018595). This work was partially supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT). (No.NRF-2021M2D1A101906111).

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