Verification of a two-step code system MCS/RAST-F to fast reactor core analysis
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 noda...
| Main Authors: | , , , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2022-05-01
|
| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573321006227 |
| _version_ | 1818395171877814272 |
|---|---|
| author | Tuan Quoc Tran Alexey Cherezov Xianan Du Deokjung Lee |
| author_facet | Tuan Quoc Tran Alexey Cherezov Xianan Du Deokjung Lee |
| author_sort | Tuan Quoc Tran |
| collection | DOAJ |
| description | 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. |
| first_indexed | 2024-12-14T06:12:52Z |
| format | Article |
| id | doaj.art-0dc3c3f570bd4de1bb79f900101e6dcf |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-14T06:12:52Z |
| publishDate | 2022-05-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-0dc3c3f570bd4de1bb79f900101e6dcf2022-12-21T23:14:07ZengElsevierNuclear Engineering and Technology1738-57332022-05-0154517891803Verification of a two-step code system MCS/RAST-F to fast reactor core analysisTuan Quoc Tran0Alexey Cherezov1Xianan Du2Deokjung Lee3Department of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, Republic of KoreaDepartment of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, Republic of KoreaSchool of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, ChinaDepartment of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, Republic of Korea; Corresponding author.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.http://www.sciencedirect.com/science/article/pii/S1738573321006227Fast reactorNodal diffusion codeRAST-FTPEN |
| spellingShingle | Tuan Quoc Tran Alexey Cherezov Xianan Du Deokjung Lee Verification of a two-step code system MCS/RAST-F to fast reactor core analysis Nuclear Engineering and Technology Fast reactor Nodal diffusion code RAST-F TPEN |
| title | Verification of a two-step code system MCS/RAST-F to fast reactor core analysis |
| title_full | Verification of a two-step code system MCS/RAST-F to fast reactor core analysis |
| title_fullStr | Verification of a two-step code system MCS/RAST-F to fast reactor core analysis |
| title_full_unstemmed | Verification of a two-step code system MCS/RAST-F to fast reactor core analysis |
| title_short | Verification of a two-step code system MCS/RAST-F to fast reactor core analysis |
| title_sort | verification of a two step code system mcs rast f to fast reactor core analysis |
| topic | Fast reactor Nodal diffusion code RAST-F TPEN |
| url | http://www.sciencedirect.com/science/article/pii/S1738573321006227 |
| work_keys_str_mv | AT tuanquoctran verificationofatwostepcodesystemmcsrastftofastreactorcoreanalysis AT alexeycherezov verificationofatwostepcodesystemmcsrastftofastreactorcoreanalysis AT xianandu verificationofatwostepcodesystemmcsrastftofastreactorcoreanalysis AT deokjunglee verificationofatwostepcodesystemmcsrastftofastreactorcoreanalysis |