TY - GEN
T1 - A methodology for determination of detector response for inspection of a spent fuel pool
AU - Walters, William
AU - Haghighat, Alireza
AU - Wenner, Michael
AU - Sitaraman, Shivakumar
AU - Ham, Young
N1 - Copyright:
Copyright 2021 Elsevier B.V., All rights reserved.
PY - 2010
Y1 - 2010
N2 - In this paper we examine the predicted response of a fission chamber detector in the spent fuel pool at the Atucha-I reactor using the adjoint methodology with the aim of detecting proliferation. Burnup calculations to determine material composition and intrinsic neutron source are performed using the ORIGEN-ARP depletion code. Sub-critical multiplication is modeled using a simplified fission-matrix method. Fission-matrix coefficients are determined using MCNP for several burnups and decay times, which can be interpolated to arbitrary values. This method can quickly and accurately calculate the subcritical multiplication for a pool of any size, assembly burnup and cooling time. Adjoint function calculations for a fission chamber placed in the pool were performed using the PENTRAN Sn code. These results show that the detector field-of-view (FOV) is relatively insensitive to detector position within the pool, assembly burnup and cooling time. The adjoint results are coupled with the source calculations to predict the detector response in the spent fuel pool under both normal and proliferation scenarios. Two spent fuel diversion scenarios are examined, including substitution with dummy assemblies and attempted masking of a dummy assembly using a high-burnup assembly. Both assembly diversion scenarios show a predicted deviation from unperturbed response by at least 20%.
AB - In this paper we examine the predicted response of a fission chamber detector in the spent fuel pool at the Atucha-I reactor using the adjoint methodology with the aim of detecting proliferation. Burnup calculations to determine material composition and intrinsic neutron source are performed using the ORIGEN-ARP depletion code. Sub-critical multiplication is modeled using a simplified fission-matrix method. Fission-matrix coefficients are determined using MCNP for several burnups and decay times, which can be interpolated to arbitrary values. This method can quickly and accurately calculate the subcritical multiplication for a pool of any size, assembly burnup and cooling time. Adjoint function calculations for a fission chamber placed in the pool were performed using the PENTRAN Sn code. These results show that the detector field-of-view (FOV) is relatively insensitive to detector position within the pool, assembly burnup and cooling time. The adjoint results are coupled with the source calculations to predict the detector response in the spent fuel pool under both normal and proliferation scenarios. Two spent fuel diversion scenarios are examined, including substitution with dummy assemblies and attempted masking of a dummy assembly using a high-burnup assembly. Both assembly diversion scenarios show a predicted deviation from unperturbed response by at least 20%.
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M3 - Conference contribution
AN - SCOPUS:79952403230
SN - 9781617820014
T3 - International Conference on the Physics of Reactors 2010, PHYSOR 2010
SP - 3412
EP - 3425
BT - International Conference on the Physics of Reactors 2010, PHYSOR 2010
PB - American Nuclear Society
T2 - International Conference on the Physics of Reactors 2010, PHYSOR 2010
Y2 - 9 May 2010 through 14 May 2010
ER -