Automated Defect Detection in Spent Nuclear Fuel Using Combined Cerenkov Radiation and Gamma Emission Tomography Data

Journal Article · Thu Jul 12 00:00:00 EDT 2018 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2018.1490123· OSTI ID:1495346

Brayfindley, Eva  ^[1]; Smith, Ralph C. ^[1]; Mattingly, John ^[2]; Brigantic, Robert ^[3]

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1. North Carolina State University, Department of Mathematics, Raleigh, North Carolina 27695
2. North Carolina State University, Department of Nuclear Engineering, Raleigh, North Carolina 27695
3. Pacific Northwest National Laboratory, Applied Statistics and Computational Modeling, 902 Battelle Boulevard, P.O. Box 999, MSIN: K7-20, Richland, Washington 99352

Spent fuel monitoring and characterization has been central to safeguards and nuclear facility monitoring for many years. The Digital Cerenkov Viewing Device (DCVD) has been used since the 1980s as a method of defect detection in spent fuel. In recent years, the accounting for large quantities of spent fuel before storage has renewed interest in this relatively quick and inexpensive method. This has an impact not only in safeguards, but also for nuclear power facilities, as accounting can be a long, arduous and costly process. Additionally, the DCVD demonstrates limited accuracy in more complex cases such as substitution of a fuel rod with steel, or a partial defect detection. A second method, Gamma Emission Tomography (GET) has been explored as an improved defect detection method, but is much more expensive and invasive than DCVD. This work identies deciencies in both methods, and proposes a combination of data gathered from each method to address these deciencies for improved spent fuel characterization. Initial results are promising, showing 97% detection of a single missing fuel rod when the data types are combined, versus approximately 50% and 70% respectively for DCVD and GET data on their own. These classication results are obtained with algorithms derived from facial recognition and applied to this problem, yielding unique accuracy in near real-time while also maintaining the information barrier between output and measurement desired in safeguards.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-76RL01830
• OSTI ID: 1495346
• Report Number(s): PNNL-SA-132748
• Journal Information: Nuclear Technology, Vol. 204, Issue 3; ISSN 0029-5450
• Publisher: Taylor & Francis - formerly American Nuclear Society (ANS)
• Country of Publication: United States
• Language: English