MACROSCOPIC CROSS SECTIONS GENERATION BY MONTE CARLO CODE MCS FOR FAST REACTOR ANALYSIS
نویسندگان
چکیده
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 nodal diffusion codes. The current study, therefore, presents a brief methodology MG XSs generation by in-house UNIST MC MCS, which can be compatibly utilized codes, PARCS and RAST-K. applicability is quantified on sodium (SFR) ABR-1000 design with metallic fuel from OECD/NEA SRF benchmark. few-group generated MCS two-dimensional (2D) assembly geometry are well consistent those SERPENT 2. Furthermore, simulation beginning-of-cycle (BOC) steady-state three-dimensional (3D) whole-core problem RAST-K conducted 24-group MCS. solutions, including core k eff , power profiles various reactivity parameters, compared reference results obtained Overall, code-to-code comparison indicates reasonable agreement between deterministic stochastic difference less than 100 pcm root-mean-square (RMS) error 1.15%. Therefore, it successfully demonstrated that employment codes feasible accurately perform analyses reactors.
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ژورنال
عنوان ژورنال: Epj Web of Conferences
سال: 2021
ISSN: ['2101-6275', '2100-014X']
DOI: https://doi.org/10.1051/epjconf/202124702007