A Simulation Study of the Spent Nuclear Fuel Cask Condition Evaluation Using High Energy X-Ray Computed Tomography
Abstract
The dry cask storage time could be much longer ( > 60 years) for the spent nuclear fuels before final disposition in the United States. The casks have multiple internal components that are designed to provide structural integrity during storage and, in some cases, during transportation. The long-term internal stability of the internals and spent fuel and their cladding is important to maintain the sub-criticality of the fissile materials in the casks. In this study, we propose to develop a high-energy X-ray CT system to examine the integrity of casks and their inner components. With careful system design and advanced image reconstruction techniques, we estimate that a sub-centimeter spatial resolution can be achieved through the simulation study. A complete three-dimension "anatomical" picture of the cask and its inner components can be obtained with a reasonable scanning time.
Recommended Citation
X. Liu and H. Lee, "A Simulation Study of the Spent Nuclear Fuel Cask Condition Evaluation Using High Energy X-Ray Computed Tomography," NDT & E International, vol. 80, pp. 58 - 64, Elsevier, Jun 2016.
The definitive version is available at https://doi.org/10.1016/j.ndteint.2016.02.008
Department(s)
Nuclear Engineering and Radiation Science
Keywords and Phrases
Design; Fuel storage; Fuels; Image reconstruction; Iterative methods; Nuclear fuels; Radioactive wastes; Spent fuels; Tomography; Cask; Centimeter spatial resolution; Condition evaluation; High energy X ray; Image reconstruction techniques; Internal stability; Iterative reconstruction; Spent nuclear fuels; Computerized tomography; Computed tomography; High-energy X-ray; Iterative reconstruction; Spent nuclear fuel
International Standard Serial Number (ISSN)
0963-8695
Document Type
Article - Journal
Document Version
Citation
File Type
text
Language(s)
English
Rights
© 2016 Elsevier, All rights reserved.
Publication Date
01 Jun 2016
Comments
The work presented in this paper is supported by U.S. NRC under the Award number NRC-HQ-12-G-38-0039 .