Neutronic analysis of a fuel element with variations in fuel enrichment and burnable poison
In this work, the goal was to evaluate the neutronic behavior during the fuel burnup changing the amount of burnable poison and fuel enrichment. The analyses 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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| Pubblicato in: | Brazilian Journal of Radiation Sciences |
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| Autori principali: | , , , , , |
| Natura: | Artigo |
| Lingua: | Inglês |
| Pubblicazione: |
Sociedade Brasileira de Proteção Radiológica - SBPR
2019
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| Soggetti: | |
| Accesso online: | https://www.redalyc.org/articulo.oa?id=722280898023 |
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