Expected total counts for the Self-Interrogation Neutron Resonance Densitometry measurements of spent nuclear fuel

Riccardo Rossa; Alessandro Borella; Pierre-Etienne Labeau; Nicolas Pauly; Klaas van der Meer

Expected total counts for the Self-Interrogation Neutron Resonance Densitometry measurements of spent nuclear fuel

Riccardo Rossa, Alessandro Borella, Pierre-Etienne Labeau, Nicolas Pauly, Klaas van der Meer

Nuclear Science and Technology Studies

Research output › peer-review

Abstract

This poster is focused on the estimation of the total neutron counts that can be achieved ideally with the SINRD measurements of spent nuclear fuel. The contributions compares different detector types and SINRD filters that are used to measure the neutron flux in the fast and in the resonance energy region. Fission chambers using 239Pu or 235U as active material and proportional counters containing 3He or 10B were compared. The fission chambers obtained the highest sensitivity to the 239Pu content, whereas the proportional counters showed the highest total neutron counts.

Original language	English
Title of host publication	Proceedings of the 2015 ANIMMA conference
Place of Publication	Portugal
Pages	1-6
State	Published - Apr 2015
Event	2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications: International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications - Lisbon Duration: 20 Apr 2015 → 24 Apr 2015

Conference

Conference	2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications
Country/Territory	Portugal
City	Lisbon
Period	2015-04-20 → 2015-04-24

Cite this

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title = "Expected total counts for the Self-Interrogation Neutron Resonance Densitometry measurements of spent nuclear fuel",

abstract = "This poster is focused on the estimation of the total neutron counts that can be achieved ideally with the SINRD measurements of spent nuclear fuel. The contributions compares different detector types and SINRD filters that are used to measure the neutron flux in the fast and in the resonance energy region. Fission chambers using 239Pu or 235U as active material and proportional counters containing 3He or 10B were compared. The fission chambers obtained the highest sensitivity to the 239Pu content, whereas the proportional counters showed the highest total neutron counts.",

keywords = "SINRD, spent fuel, NDA, 239Pu, safeguards",

author = "Riccardo Rossa and Alessandro Borella and Pierre-Etienne Labeau and Nicolas Pauly and {van der Meer}, Klaas",

note = "Score = 3; 2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications : International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications ; Conference date: 20-04-2015 Through 24-04-2015",

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month = apr,

language = "English",

pages = "1--6",

booktitle = "Proceedings of the 2015 ANIMMA conference",

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Rossa, R , Borella, A, Labeau, P-E, Pauly, N & van der Meer, K 2015, Expected total counts for the Self-Interrogation Neutron Resonance Densitometry measurements of spent nuclear fuel. in Proceedings of the 2015 ANIMMA conference. Portugal, pp. 1-6, 2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications, Lisbon, Portugal, 2015-04-20.

TY - GEN

T1 - Expected total counts for the Self-Interrogation Neutron Resonance Densitometry measurements of spent nuclear fuel

AU - Rossa, Riccardo

AU - Borella, Alessandro

AU - Labeau, Pierre-Etienne

AU - Pauly, Nicolas

AU - van der Meer, Klaas

N1 - Score = 3

PY - 2015/4

Y1 - 2015/4

N2 - This poster is focused on the estimation of the total neutron counts that can be achieved ideally with the SINRD measurements of spent nuclear fuel. The contributions compares different detector types and SINRD filters that are used to measure the neutron flux in the fast and in the resonance energy region. Fission chambers using 239Pu or 235U as active material and proportional counters containing 3He or 10B were compared. The fission chambers obtained the highest sensitivity to the 239Pu content, whereas the proportional counters showed the highest total neutron counts.

AB - This poster is focused on the estimation of the total neutron counts that can be achieved ideally with the SINRD measurements of spent nuclear fuel. The contributions compares different detector types and SINRD filters that are used to measure the neutron flux in the fast and in the resonance energy region. Fission chambers using 239Pu or 235U as active material and proportional counters containing 3He or 10B were compared. The fission chambers obtained the highest sensitivity to the 239Pu content, whereas the proportional counters showed the highest total neutron counts.

KW - SINRD

KW - spent fuel

KW - NDA

KW - 239Pu

KW - safeguards

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_139480

UR - http://knowledgecentre.sckcen.be/so2/bibref/12609

M3 - In-proceedings paper

SP - 1

EP - 6

BT - Proceedings of the 2015 ANIMMA conference

CY - Portugal

T2 - 2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications

Y2 - 20 April 2015 through 24 April 2015

ER -