Neutronic analysis of a fuel element with variations in fuel enrichment and burnable poison
The goal was to evaluate the neutronic behavior during the fuel burnup changing the amount of burnable poison and fuel enrichment. For these analyses, it was used a 17 x 17 PWR fuel element, simulated using the 238 groups library cross-section collapsed from ENDF/BVII.0 and TRITON module of SCALE 6....
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| Principais autores: | , , , , |
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| 格式: | Artigo |
| 語言: | Inglês |
| 出版: |
Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
2019-07-01
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| 叢編: | Brazilian Journal of Radiation Sciences |
| 主題: | |
| 在線閱讀: | https://bjrs.org.br/revista/index.php/REVISTA/article/view/769 |
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