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Passive gamma analysis of the boiling-water-reactor assemblies
Los Alamos National Laboratory, Los Alamos, NM, USA.
Los Alamos National Laboratory, Los Alamos, NM, USA.
Oak Ridge National Laboratory, Oak Ridge, TN, USA.
Uppsala University, Disciplinary Domain of Science and Technology, Physics, Department of Physics and Astronomy, Applied Nuclear Physics.ORCID iD: 0000-0002-3136-5665
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2016 (English)In: Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, ISSN 0168-9002, E-ISSN 1872-9576, Vol. 830, 325-337 p.Article in journal (Refereed) Published
Abstract [en]

This research focused on the analysis of a set of stationary passive gamma measurements taken on the spent nuclear fuel assemblies from a boiling water reactor (BWR) using pulse height analysis data acquisition. The measurements were performed on 25 different BWR assemblies in 2014 at Sweden's Central Interim Storage Facility for Spent Nuclear Fuel (Clab). This study was performed as part of the Next Generation of Safeguards Initiative–Spent Fuel project to research the application of nondestructive assay (NDA) to spent fuel assemblies. The NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay (NDA) measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins, (3) estimate the plutonium mass, (4) estimate the decay heat, and (5) determine the reactivity of spent fuel assemblies. The final objective of this project is to quantify the capability of several integrated NDA instruments to meet the aforementioned goals using the combined signatures of neutrons, gamma rays, and heat.

This report presents a selection of the measured data and summarizes an analysis of the results. Specifically, trends in the count rates measured for spectral lines from the following isotopes were analyzed as a function of the declared burnup and cooling time:137Cs, 154Eu, 134Cs, and to a lesser extent, 106Ru and 144Ce. From these measured count rates, predictive algorithms were developed to enable the estimation of the burnup and cooling time. Furthermore, these algorithms were benchmarked on a set of assemblies not included in the standard assemblies set used by this research team.

Place, publisher, year, edition, pages
2016. Vol. 830, 325-337 p.
Keyword [en]
Passive gamma, Initial enrichment, Burnup, Cooling time, Spent fuel NDA, BWR
National Category
Subatomic Physics
Research subject
Physics with specialization in Applied Nuclear Physics
URN: urn:nbn:se:uu:diva-296168DOI: 10.1016/j.nima.2016.06.013OAI: oai:DiVA.org:uu-296168DiVA: diva2:936462
Available from: 2016-06-14 Created: 2016-06-14 Last updated: 2016-06-14

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Jansson, Peter
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Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
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