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Title: Predicting fissile content of spent nuclear fuel assemblies with the passive neutron Albedo reactivity technique and Monte Carlo code emulation

There is a great need in the safeguards community to be able to nondestructively quantify the mass of plutonium of a spent nuclear fuel assembly. As part of the Next Generation of Safeguards Initiative, we are investigating several techniques, or detector systems, which, when integrated, will be capable of quantifying the plutonium mass of a spent fuel assembly without dismantling the assembly. This paper reports on the simulation of one of these techniques, the Passive Neutron Albedo Reactivity with Fission Chambers (PNAR-FC) system. The response of this system over a wide range of spent fuel assemblies with different burnup, initial enrichment, and cooling time characteristics is shown. A Monte Carlo method of using these modeled results to estimate the fissile content of a spent fuel assembly has been developed. A few numerical simulations of using this method are shown. Finally, additional developments still needed and being worked on are discussed.
Authors:
 [1] ;  [1]
  1. Los Alamos National Laboratory
Publication Date:
OSTI Identifier:
1036731
Report Number(s):
LA-UR-10-06933; LA-UR-10-6933
TRN: US1201467
DOE Contract Number:
AC52-06NA25396
Resource Type:
Conference
Resource Relation:
Conference: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering ; May 8, 2011 ; Rio de Janeiro, Brazil
Research Org:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION; ALBEDO; BURNUP; COOLING TIME; FISSION CHAMBERS; MONTE CARLO METHOD; NEUTRONS; NUCLEAR FUELS; PLUTONIUM; SAFEGUARDS; SIMULATION; SPENT FUELS