A Qualitative Analysis of the Neutron Population in Fresh and Spent Fuel Assemblies during Simulated Interrogation using the Differential Die-Away Technique
2015 (English)In: ESARDA Bulletin, ISSN 0392-3029, no 53, 13-21 p.Article in journal (Refereed) Published
Monte Carlo simulations were performed for the differential die-away (DDA) technique to analyse the time-dependent behaviour of the neutron population in fresh and spent nuclear fuel assemblies as part of the Next Generation Safeguards Initiative Spent Fuel (NGSI-SF) Project. Simulations were performed to investigate both a possibly portable as well as a permanent DDA instrument. Taking advantage of a custom made modification to the MCNPX code, the variation in the neutron population, simultaneously in time and space, was examined. The motivation for this research was to improve the design of the DDA instrument, as it is being considered for possible deployment at the Central Storage of Spent Nuclear Fuel and Encapsulation Plant in Sweden (Clab), as well as to assist in the interpretation of the both simulated and measured signals.
Place, publisher, year, edition, pages
2015. no 53, 13-21 p.
Differential die-away, Spent fuel, Used fuel, Active neutron interrogation
Research subject Physics with specialization in Applied Nuclear Physics
IdentifiersURN: urn:nbn:se:uu:diva-296595OAI: oai:DiVA.org:uu-296595DiVA: diva2:938917