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Outcomes of the JNT 1955 Phase I Viability Study of Gamma Emission Tomography for Spent Fuel Verification
Uppsala University, Disciplinary Domain of Science and Technology, Physics, Department of Physics and Astronomy, Applied Nuclear Physics.ORCID iD: 0000-0003-3411-7058
Pacific Northwest National Laboratory, USA.
Pacific Northwest National Laboratory, USA.
Lawrence Livermore National Laboratory, Livermore, CA, USA.
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2017 (English)In: ESARDA Bulletin, ISSN 1977-5296, no 55, p. 10-28Article in journal (Refereed) Published
Abstract [en]

The potential for gamma emission tomography (GET) to detect partial defects within a spent nuclear fuel assembly has been assessed within the IAEA Support Program project JNT 1955, phase I, which was completed and reported to the IAEA in October 2016. Two safeguards verification objectives were identified in the project; (1) independent determination of the number of active pins that are present in a measured assembly, in the absence of a priori information about the assembly; and (2) quantitative assessment of pin-by-pin properties, for example the activity of key isotopes or pin attributes such as cooling time and relative burnup, under the assumption that basic fuel parameters (e.g., assembly type and nominal fuel composition) are known. The efficacy of GET to meet these two verification objectives was evaluated across a range of fuel types, burnups and cooling times, while targeting a total interrogation time of less than 60 minutes.

The evaluations were founded on a modelling and analysis framework applied to existing and emerging GET instrument designs. Monte Carlo models of different fuel types were used to produce simulated tomographer responses to large populations of "virtual" fuel assemblies. The simulated instrument response data were then processed using a variety of tomographic-reconstruction and image- processing methods, and scoring metrics were defined and used to evaluate the performance of the methods.

This paper describes the analysis framework and metrics used to predict tomographer performance. It also presents the design of a "universal" GET (UGET) instrument intended to support the full range of verification scenarios envisioned by the IAEA. Finally, it gives examples of the expected partial-defect detection capabilities for some fuels and diversion scenarios, and it provides a comparison of predicted performance for the notional UGET design and an optimized variant of an existing IAEA instrument.

Place, publisher, year, edition, pages
2017. no 55, p. 10-28
Keywords [en]
Spent nuclear fuel assemblies, Partial defect verification, Gamma-ray emission tomography
National Category
Subatomic Physics
Research subject
Physics with specialization in Applied Nuclear Physics
Identifiers
URN: urn:nbn:se:uu:diva-347213OAI: oai:DiVA.org:uu-347213DiVA, id: diva2:1193798
Funder
Swedish Radiation Safety AuthorityAvailable from: 2018-03-27 Created: 2018-03-27 Last updated: 2018-04-19Bibliographically approved

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ESARDA Bulletin No 55

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Jacobsson, StaffanJansson, PeterAndersson, PeterDavour, AnnaGrape, Sophie

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