A qualitative analysis of the neutron population in fresh and spent fuel assemblies during simulated interrogation using the differential die-away technique
- Uppsala Univ., Uppsala (Sweden); Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Swedish Nuclear Fuel and Waste Management Company (SKB), Blekholmstorget (Stockholm)
- Uppsala Univ., Uppsala (Sweden); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Uppsala Univ., Uppsala (Sweden)
In this study, 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 be ing 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.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE
- Grant/Contract Number:
- AC52-06NA25396
- OSTI ID:
- 1255832
- Report Number(s):
- LA-UR-15-23441
- Journal Information:
- ESARDA Bulletin, Journal Issue: 53; ISSN 0392-3029
- Publisher:
- European Safeguards Research & Development AssociationCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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