Validation of MCS code for shielding calculation using SINBAD
نویسندگان
چکیده
The MCS code is a computer developed by the Ulsan National Institute of Science and Technology (UNIST) for simulation calculation nuclear reactor systems based on Monte Carlo method. currently used to solve two main types physics problems, namely, criticality problems radiation shielding problems. In this paper, capability validated simulating some selected SINBAD (Shielding Integral Benchmark Archive Database) experiments. whole validation was performed in ways. Firstly, functionality computational rationality verified comparing results with those MCNP code. Secondly, validity accuracy confirmed experimental SINBAD. are highly consistent code, they within 2σ error bound experiment results. It shows that reliable when
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ژورنال
عنوان ژورنال: Nuclear Engineering and Technology
سال: 2022
ISSN: ['1738-5733', '2234-358X']
DOI: https://doi.org/10.1016/j.net.2022.03.029