Generating Multi-group Homogenized Cross-sections Using Continuous-energy Monte Carlo Method for Fast Reactor Analysis
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 o...
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| 第一著者: | |
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| フォーマット: | Artigo |
| 言語: | Inglês |
| 出版事項: |
Editorial Board of Atomic Energy Science and Technology
2024-03-01
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| シリーズ: | Yuanzineng kexue jishu |
| 主題: | |
| オンライン･アクセス: | https://yznkxjs.xml-journal.net/cn/article/doi/10.7538/yzk.2023.youxian.0889 |
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