Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Validation of MCS code for shielding calculation using SINBAD

  • Feng, XiaoYong (School of Mechanical Engineering, Pusan National University) ;
  • Zhang, Peng (Graduate School of Artificial Intelligence, Korea Advanced Institute of Science and Technology) ;
  • Lee, Hyunsuk (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Lee, Deokjung (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Lee, Hyun Chul (School of Mechanical Engineering, Pusan National University)
  • Received : 2021.12.31
  • Accepted : 2022.03.21
  • Published : 2022.09.25
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Abstract

The MCS code is a computer code developed by the Ulsan National Institute of Science and Technology (UNIST) for simulation and calculation of nuclear reactor systems based on the Monte Carlo method. The code is currently used to solve two main types of reactor physics problems, namely, criticality problems and radiation shielding problems. In this paper, the radiation shielding capability of the MCS code is validated by simulating some selected SINBAD (Shielding Integral Benchmark Archive and Database) experiments. The whole validation was performed in two ways. Firstly, the functionality and computational rationality of the MCS code was verified by comparing the simulation results with those of MCNP code. Secondly, the validity and computational accuracy of the MCS code was confirmed by comparing the simulation results with the experimental results of SINBAD. The simulation results of the MCS code are highly consistent with the those of the MCNP code, and they are within the 2σ error bound of the experiment results. It shows that the calculation results of the MCS code are reliable when simulating the radiation shielding problems.

Keywords

Acknowledgement

This work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (2019R1A2C2089962).

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