| Autor: |
GUO Hui, SHEN Yuyang, WU Yiwei, CHEN Cuilan, SONG Qufei, GU Hanyang |
| Jazyk: |
English<br />Chinese |
| Rok vydání: |
2024 |
| Předmět: |
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| Zdroj: |
Yuanzineng kexue jishu, Vol 58, Iss 3, Pp 593-603 (2024) |
| Druh dokumentu: |
article |
| ISSN: |
1000-6931 |
| DOI: |
10.7538/yzk.2023.youxian.0889 |
| Popis: |
The deterministic two-step method for the fast reactor neutronics calculation, composed of cross-section homogenization and diffusion or transport core calculations, was widely applied in the fast reactor engineering design and analysis field. The homogenized cross-section calculation method based on Monte Carlo with continuous-energy and fine geometry can provide high-precision cross-sections for advanced fast reactors. The current development status and trends of coupling Monte Carlo-generated homogenized cross-sections with diffusion and transport core calculations were briefly reviewed in this paper. The methods discussed include the Monte Carlo flux-volume homogenization method, the superhomogenization equivalence technique (SPH), and the Monte Carlo flux-moment homogenization method (MHT). The MET-1000 metal fuel fast reactor is used as a benchmark. The SPH equivalent techniques are widely used to preserve the reaction rates of a reference heterogeneous model and a homogenous model. In this paper, the SPH was applied to the control rods' cross-section address to improve the diffusion core calculations. This equivalence technique reduces the overestimation of the control rod worth using the diffusion core solver from 13.5% to 0.35% and improves power distribution prediction accuracy. With SPH correction, the MC/diffusion in this work exhibits about |
| Databáze: |
Directory of Open Access Journals |
| Externí odkaz: |
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