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Nguyen TDC, Lee H, Du X, Dos V, Tran TQ, Lee D. MACROSCOPIC CROSS SECTIONS GENERATION BY MONTE CARLO CODE MCS FOR FAST REACTOR ANALYSIS. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124702007] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
Recent researches have become more interested in the feasibility of using Monte Carlo (MC) code to generate multi-group (MG) cross sections (XSs) for fast reactor analysis using nodal diffusion codes. The current study, therefore, presents a brief methodology for MG XSs generation by the in-house UNIST MC code MCS, which can be compatibly utilized in nodal diffusion codes, PARCS and RAST-K. The applicability of the methodology is quantified on the sodium fast reactor (SFR) ABR-1000 design with a metallic fuel from the OECD/NEA SRF benchmark. The few-group XSs generated by MCS with a two-dimensional (2D) fuel assembly geometry are well consistent with those of SERPENT 2. Furthermore, the simulation of beginning-of-cycle (BOC) steady-state three-dimensional (3D) whole-core problem with PARCS and RAST-K is conducted using the generated 24-group XSs by MCS. The nodal diffusion solutions, including the core keff, power profiles and various of reactivity parameters, are compared to reference whole-core results obtained by MC code MCS. Overall, the code-to-code comparison indicates a reasonable agreement between deterministic and stochastic codes, with the difference in keff less than 100 pcm and the root-mean-square (RMS) error in assembly power less than 1.15%. Therefore, it is successfully demonstrated that the employment of the MG XSs generation by MCS for nodal diffusion codes is feasible to accurately perform analyses for fast reactors.
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Wei L, Zheng Y, Du X, Wu H. Extension of SARAX code system for reactors with intermediate spectrum. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110883] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Häkkinen S, Syrjälahti E, Rintala A. Validation of the Serpent 2-HEXTRAN-SMABRE code sequence in a VVER-1000 coolant transient. J NUCL SCI TECHNOL 2020. [DOI: 10.1080/00223131.2020.1773348] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
Affiliation(s)
- Silja Häkkinen
- VTT Technical Research Centre of Finland Ltd, Espoo, Finland
| | | | - Antti Rintala
- VTT Technical Research Centre of Finland Ltd, Espoo, Finland
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Wei L, Zheng Y, Wu H. Improvement of few-group cross-section generation in fast reactor analysis system SARAX. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.04.026] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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