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Title: Examining Fuel-Cycle Scenarios with the Safeguards Analysis Toolbox

Journal Article · · Nuclear Technology
 [1]; ORCiD logo [1];  [2]
  1. Colorado School of Mines, Golden, CO (United States). Nuclear Science and Engineering Program
  2. Univ. of Idaho, Moscow, ID (United States). Center for Advanced Energy Studies
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SafeGuards Analysis (SGA) is a toolbox developed to allow engineers and scientists to create detailed simulations of safeguards material control and accountability simulations. SGA accepts material flow data from an external material flow model, and can be used with any existing fuel cycle or material control code. This work examines some new developments to the SGA code that allow the code to consider material losses over long timeframes. The first scenario described in this paper examined an enrichment facility consisting of two material balance areas (MBAs). Cumulative sum and basic control chart tests evaluate to a case involving a loss of material from both MBAs simultaneously and a case in which material is removed from the facility over a timescale of double the one that the tests were calibrated to detect. A second scenario represents an entire fuel-cycle consisting of four MBAs and two materials of interest (low-enriched uranium and plutonium). This scenario evaluated the calibrated safeguards system with three blind unidentified stream cases, with the goal of determining the calibrated system’s ability to detect where the material loss occurred in each case. SGA was able to produce the expected results for all of the examples examined in this paper, demonstrating that modules produced using the toolbox are capable of examining larger systems in realistic multi-MBA scenarios.

Research Organization:
Colorado School of Mines, Golden, CO (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Office of Nonproliferation and Verification Research and Development (NA-22)
Grant/Contract Number:
NA0001730
OSTI ID:
1461842
Journal Information:
Nuclear Technology, Vol. 204, Issue 2; ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)Copyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 1 work
Citation information provided by
Web of Science

References (3)

A New Modeling Technique to Analyze Safeguards Measurements in Large Systems journal August 2017
Verifiable Fuel Cycle Simulation Model (VISION): A Tool for Analyzing Nuclear Fuel Cycle Futures journal November 2010
Continuous Inspection Schemes journal January 1954

Figures / Tables (19)

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
Safeguards
modeling
uncertainty analysis