Determination of neutron emission from spent fuel for safeguards verification

Research output: ThesisMaster's thesis

Institutes & Expert groups

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Documents

Abstract

With the purpose of creating a reference spent fuel composition that can be used to investigate and improve NDA methods, SCK-CEN started the definition of a spent fuel library through the simulations performed with the ORIGEN-ARP and ALEPH2.2 codes. Previous work considered a PWR 17x17 fuel geometry and the cases of low enriched uranium (LEU) fuel with initial enrichment in 235U between 3.5 and 5%, discharge burnup between 5 and 70 GWd/tU and cooling time up to 3 million years. The aim of this work is to expand the existing LEU library, extending the initial enrichment range in order to represent the most of the enrichments currently worldwide used, and to develop a spent fuel library for mixed oxide (MOX) fuel assemblies.

Details

Original languageEnglish
Awarding Institution
  • Sapienza - Università di Roma
Supervisors/Advisors
Place of PublicationRoma, Italy
Publisher
  • Sapienza Università di roma
Publication statusPublished - 16 Mar 2015

Keywords

  • Spent fuel, Evolution and depletion calculations, Origen

ID: 123801