Determination of neutron emission from spent fuel for safeguards verification

Research output: ThesisMaster's thesis

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Determination of neutron emission from spent fuel for safeguards verification. / Cometto, Mario.

Roma, Italy : Sapienza Università di roma, 2015. 97 p.

Research output: ThesisMaster's thesis

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Cometto M. Determination of neutron emission from spent fuel for safeguards verification. Roma, Italy: Sapienza Università di roma, 2015. 97 p.

Author

Cometto, Mario. / Determination of neutron emission from spent fuel for safeguards verification. Roma, Italy : Sapienza Università di roma, 2015. 97 p.

Bibtex - Download

@phdthesis{f419d0d123d144f2ba075cab851721b4,
title = "Determination of neutron emission from spent fuel for safeguards verification",
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.",
keywords = "Spent fuel, Evolution and depletion calculations, Origen",
author = "Mario Cometto",
note = "Score = 2",
year = "2015",
month = "3",
day = "16",
language = "English",
publisher = "Sapienza Universit{\`a} di roma",
school = "Sapienza - Universit{\`a} di Roma",

}

RIS - Download

TY - THES

T1 - Determination of neutron emission from spent fuel for safeguards verification

AU - Cometto, Mario

N1 - Score = 2

PY - 2015/3/16

Y1 - 2015/3/16

N2 - 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.

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.

KW - Spent fuel

KW - Evolution and depletion calculations

KW - Origen

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_140064

M3 - Master's thesis

PB - Sapienza Università di roma

CY - Roma, Italy

ER -

ID: 123801