Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and Their Irradiated Fuel - A comparison between Libraries
| Data(s) |
01/04/2014
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|---|---|
| Resumo |
The uncertainties on the isotopic composition throughout the burnup due to the nuclear data uncertainties are analysed. The different sources of uncertainties: decay data, fission yield and cross sections; are propagated individually, and their effect assessed. Two applications are studied: EFIT (an ADS-like reactor) and ESFR (Sodium Fast Reactor). The impact of the uncertainties on cross sections provided by the EAF-2010, SCALE6.1 and COMMARA-2.0 libraries are compared. These Uncertainty Quantification (UQ) studies have been carried out with a Monte Carlo sampling approach implemented in the depletion/activation code ACAB. Such implementation has been improved to overcome depletion/activation problems with variations of the neutron spectrum. |
| Formato |
application/pdf |
| Identificador | |
| Idioma(s) |
eng |
| Publicador |
E.T.S.I. Industriales (UPM) |
| Relação |
http://oa.upm.es/26205/1/INVE_MEM_2013_162810.pdf.pdf http://www.sciencedirect.com/science/article/pii/S0090375214001586 info:eu-repo/semantics/altIdentifier/doi/10.1016/j.nds.2014.04.128 |
| Direitos |
http://creativecommons.org/licenses/by-nc-nd/3.0/es/ info:eu-repo/semantics/openAccess |
| Fonte |
Nuclear Data Sheets, ISSN 0090-2014, 2014-04, Vol. 118 |
| Palavras-Chave | #Energía Nuclear |
| Tipo |
info:eu-repo/semantics/article Artículo PeerReviewed |
