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 paperpeer-review

Standard

Sensitivity Studies On The Neutron Emission Of Spent Nuclear Fuel By Means Of The Origen-ARP Code. / Borella, Alessandro; Gad, Mahmoud; Rossa, Riccardo; van der Meer, Klaas; Turcanu, Catrinel (Peer reviewer).

INMM 55th Annual Meeting Proceedings. Atlanta, United States, 2014. p. 1-10.

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

Harvard

Borella, A, Gad, M, Rossa, R, van der Meer, K & Turcanu, C 2014, Sensitivity Studies On The Neutron Emission Of Spent Nuclear Fuel By Means Of The Origen-ARP Code. in INMM 55th Annual Meeting Proceedings. Atlanta, United States, pp. 1-10, INMM 2014 - 55th Annual Meeting, Atlanta, Georgia, United States, 2014-07-20.

Vancouver

Bibtex - Download

@inproceedings{ce61804c16134deeb61ec444bd26e1e3,
title = "Sensitivity Studies On The Neutron Emission Of Spent Nuclear Fuel By Means Of The Origen-ARP Code",
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.",
keywords = "Spent fuel composition, Spent fuel library, neutron emission, Origen",
author = "Alessandro Borella and Mahmoud Gad and Riccardo Rossa and {van der Meer}, Klaas and Catrinel Turcanu",
note = "Score = 3; INMM 2014 - 55th Annual Meeting ; Conference date: 20-07-2014 Through 24-07-2014",
year = "2014",
month = jul,
day = "24",
language = "English",
pages = "1--10",
booktitle = "INMM 55th Annual Meeting Proceedings",

}

RIS - Download

TY - GEN

T1 - Sensitivity Studies On The Neutron Emission Of Spent Nuclear Fuel By Means Of The Origen-ARP Code

AU - Borella, Alessandro

AU - Gad, Mahmoud

AU - Rossa, Riccardo

AU - van der Meer, Klaas

A2 - Turcanu, Catrinel

N1 - Score = 3

PY - 2014/7/24

Y1 - 2014/7/24

N2 - 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.

AB - 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.

KW - Spent fuel composition

KW - Spent fuel library

KW - neutron emission

KW - Origen

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_136399

UR - http://knowledgecentre.sckcen.be/so2/bibref/11708

M3 - In-proceedings paper

SP - 1

EP - 10

BT - INMM 55th Annual Meeting Proceedings

CY - Atlanta, United States

T2 - INMM 2014 - 55th Annual Meeting

Y2 - 20 July 2014 through 24 July 2014

ER -

ID: 170084