Neutron cross section measurements for BUC approaches

نویسندگان

چکیده

Criticality safety analysis is required at various stages of the back-end fuel cycle, i.e. reprocessing, transport, storage and disposal spent nuclear (SNF). To account for reduction in reactivity due to burnup, Burn-Up Credit (BUC) concept was introduced. Evidently, this depends on quality data, particular absorption cross sections some key nuclides. A dedicated programme has been established GELINA facility JRC-Geel produce accurate section data validate evaluated libraries neutron interactions with fission fragments that are relevant a BUC approach. In work, 103 Rh 155 Gd presented results compared main evaluation libraries, showing good agreement thermal energy region ENDF/B-VIII.0 JEFF-3.3, but not JENDL-4.0 Rh.

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ژورنال

عنوان ژورنال: Epj Web of Conferences

سال: 2023

ISSN: ['2101-6275', '2100-014X']

DOI: https://doi.org/10.1051/epjconf/202328408007