Sensitivity Studies On The Neutron Emission Of Spent Nuclear Fuel By Means Of The Origen-ARP Code

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Documents & links

Abstract

This paper focuses on the impact of some parameters of the irradiation history on the total neutron emission of a SFE. The tool used to determine the neutron emission was the ORIGEN-ARP code. The cases considered a Low Enriched Uranium (LEU) 17×17 PWR fuel with an initial enrichment of 4.5%. The burnup ranged between 5 and 70 GWd/tU and 30 values of cooling time, from 0 up to 3 million years, were considered. The parameters that were varied were the average power level, the cooling time between cycles and the duration of the irradiation cycle. The obtained neutron emission values are presented and discussed. Conclusions on the role of the considered irradiation history parameters on the total neutron emission and on the impact of the main neutron emitters are drawn.

Details

Original languageEnglish
Title of host publicationINMM 55th Annual Meeting Proceedings
Place of PublicationAtlanta, United States
Pages1-10
Publication statusPublished - 24 Jul 2014
EventINMM 2014 - 55th Annual Meeting - INMM - Institute of Nuclear Materials Management, Atlanta, Georgia, United States
Duration: 20 Jul 201424 Jul 2014

Conference

ConferenceINMM 2014 - 55th Annual Meeting
CountryUnited States
CityAtlanta, Georgia
Period2014-07-202014-07-24

Keywords

  • Spent fuel composition, Spent fuel library, neutron emission, Origen

ID: 170084