Validation of MCS code for shielding calculation using SINBAD
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 p...
| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2022-09-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573322001693 |
| _version_ | 1811281181694492672 |
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| author | XiaoYong Feng Peng Zhang Hyunsuk Lee Deokjung Lee Hyun Chul Lee |
| author_facet | XiaoYong Feng Peng Zhang Hyunsuk Lee Deokjung Lee Hyun Chul Lee |
| author_sort | XiaoYong Feng |
| collection | DOAJ |
| description | 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. |
| first_indexed | 2024-04-13T01:28:52Z |
| format | Article |
| id | doaj.art-be620259cf214f79ada17e1376170f47 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-04-13T01:28:52Z |
| publishDate | 2022-09-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-be620259cf214f79ada17e1376170f472022-12-22T03:08:34ZengElsevierNuclear Engineering and Technology1738-57332022-09-0154934293439Validation of MCS code for shielding calculation using SINBADXiaoYong Feng0Peng Zhang1Hyunsuk Lee2Deokjung Lee3Hyun Chul Lee4School of Mechanical Engineering, Pusan National University, 2, Busandaehak-ro 63beon-gil, Geumjeong-gu. Busan, 46241, South KoreaGraduate School of Artificial Intelligence, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon, 34141, South KoreaDepartment of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, South KoreaDepartment of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, South KoreaSchool of Mechanical Engineering, Pusan National University, 2, Busandaehak-ro 63beon-gil, Geumjeong-gu. Busan, 46241, South Korea; Corresponding author.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.http://www.sciencedirect.com/science/article/pii/S1738573322001693MCS codeSINBADShieldingVerification |
| spellingShingle | XiaoYong Feng Peng Zhang Hyunsuk Lee Deokjung Lee Hyun Chul Lee Validation of MCS code for shielding calculation using SINBAD Nuclear Engineering and Technology MCS code SINBAD Shielding Verification |
| title | Validation of MCS code for shielding calculation using SINBAD |
| title_full | Validation of MCS code for shielding calculation using SINBAD |
| title_fullStr | Validation of MCS code for shielding calculation using SINBAD |
| title_full_unstemmed | Validation of MCS code for shielding calculation using SINBAD |
| title_short | Validation of MCS code for shielding calculation using SINBAD |
| title_sort | validation of mcs code for shielding calculation using sinbad |
| topic | MCS code SINBAD Shielding Verification |
| url | http://www.sciencedirect.com/science/article/pii/S1738573322001693 |
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