Determination of neutron emission from spent fuel for safeguards verification

Mario Cometto

Determination of neutron emission from spent fuel for safeguards verification

Mario Cometto

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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.

Original language	English
Awarding Institution	Università di Roma
Supervisors/Advisors	Borella, Alessandro, Supervisor Rossa, Riccardo, Supervisor
Place of Publication	Roma, Italy
Publisher	Sapienza Università di roma
State	Published - 16 Mar 2015

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Determination of neutron emission from spent fuel for safeguards verificationFinal published version, 3.03 MBLicense: Unspecified

Cite this

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title = "Determination of neutron emission from spent fuel for safeguards verification",

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AB - 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.

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KW - Evolution and depletion calculations

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M3 - Master's thesis

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CY - Roma, Italy

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