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

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

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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.

Details

Original languageEnglish
Title of host publicationProceedings of the 2015 ANIMMA conference
Place of PublicationPortugal
Pages1-6
Publication statusPublished - Apr 2015
Event2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications: International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications - Lisbon, Portugal
Duration: 20 Apr 201524 Apr 2015

Conference

Conference2015 - ANIMMA - Advancements in Nuclear Instrumentation Measurement Methods and their Applications
CountryPortugal
CityLisbon
Period2015-04-202015-04-24

Keywords

  • SINRD, spent fuel, NDA, 239Pu, safeguards

ID: 106515