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Optimization of Yonsei Single-Photon Emission Computed Tomography (YSECT) Detector for Fast Inspection of Spent Nuclear Fuel in Water Storage

  • Hyung-Joo Choi (Department of Radiation Convergence Engineering, Yonsei University) ;
  • Hyojun Park (Department of Radiation Oncology, Seoul National University Hospital) ;
  • Bo-Wi Cheon (Department of Radiation Convergence Engineering, Yonsei University) ;
  • Kyunghoon Cho (ARALE Laboratory Co. Ltd.) ;
  • Hakjae Lee (ARALE Laboratory Co. Ltd.) ;
  • Yong Hyun Chung (Department of Radiation Convergence Engineering, Yonsei University) ;
  • Yeon Soo Yeom (Department of Radiation Convergence Engineering, Yonsei University) ;
  • Sei Hwan You (Department of Radiation Oncology, Yonsei University Wonju College of Medicine) ;
  • Hyun Joon Choi (Department of Radiation Oncology, Yonsei University Wonju College of Medicine) ;
  • Chul Hee Min (Department of Radiation Convergence Engineering, Yonsei University)
  • Received : 2023.08.04
  • Accepted : 2023.12.22
  • Published : 2024.03.31

Abstract

Background: The gamma emission tomography (GET) device has been reported a reliable technique to inspect partial defects within spent nuclear fuel (SNF) of pin-by-pin level. However, the existing GET devices have low accuracy owing to the high attenuation and scatter probability for SNF inspection condition. The purpose of this study is to design and optimize a Yonsei single-photon emission computed tomography version 2 (YSECT.v.2) for fast inspection of SNF in water storage by acquisition of high-quality tomographic images. Materials and Methods: Using Geant4 (Geant4 Collaboration) and DETECT-2000 (Glenn F. Knoll et al.) Monte Carlo simulation, the geometrical structure of the proposed device was determined and its performance was evaluated for the 137Cs source in water. In a Geant4-based assessment, proposed device was compared with the International Atomic Energy Agency (IAEA)-authenticated device for the quality of tomographic images obtained for 12 fuel sources in a 14 × 14 Westinghouse-type fuel assembly. Results and Discussion: According to the results, the length, slit width, and septal width of the collimator were determined to be 65, 2.1, and 1.5 mm, respectively, and the material and length of the trapezoidal-shaped scintillator were determined to be gadolinium aluminum gallium garnet and 45 mm, respectively. Based on the results of performance comparison between the YSECT.v.2 and IAEA's device, the proposed device showed 200 times higher performance in gamma-detection sensitivity and similar source discrimination probability. Conclusion: In this study, we optimally designed the GET device for improving the SNF inspection accuracy and evaluated its performance. Our results show that the YSECT.v.2 device could be employed for SNF inspection.

Keywords

Acknowledgement

This research was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea (No. 2106073); the Basic Science Research Program through the National Research Foundation of Korea (NRF) funded by the Ministry of Education (NRF-2021R1I1A1A0105987512); the Korea Institute of Energy Technology Evaluation and Planning (KETEP), and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea (No. 20214000000070).

References

  1. International Atomic Energy Agency. Safeguards techniques and equipment, International Nuclear Verification Series No. 1 (Revised). 2003 ed. IAEA; 2003. p. 1-49.
  2. Levai F, Desi S, Tarvainen M, Arlt R. Use of high energy gamma emission tomography for partial defect verification of spent fuel assemblies. Final report on the task FIN A98 of the Finnish Support Programme to IAEA Safeguards (STUK-YTO-TR 56). Finnish Centre for Radiation and Nuclear Safety; 1993.
  3. Mayorov M, White T, Lebrun A, Brutscher J, Keubler J, Birnbaum A, et al. Gamma emission tomography for the inspection of spent nuclear fuel. Proceedings of the 2017 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC); 2017 Oct 21-28; Atlanta, GA. p. 1-2.
  4. Honkamaa T, Levai F, Berndt R, Schwalbach P, Vaccaro S, Turunen A. A prototype for passive gamma emission tomography. Proceedings of the IAEA Symposium on International Safeguards: Linking Strategy, Implementation and People; 2014 Oct 20-24; Vienna, Austria. p. 287.
  5. Smith EL, Jacobsson S, Mozin V, Jansson P, Miller E, Honkamaa T, et al. A viability study of gamma emission tomography for spent fuel verification: JNT 1955 phase I technical report [Internet]. Digitala Vetenskapliga Arkivet; 2016 [cited 2024 Jan 30]. Available from: https://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-306584
  6. Miller EA, Smith LE, Wittman RS, Campbell LW, Deshmukh NS, Zalavadia MA, et al. Hybrid gamma emission tomography (HGET): FY16 Annual Report [Internet]. Pacific Northwest National Laboratory; 2017 [cited 2024 Jan 30]. Available from: https://www.pnnl.gov/publications/hybrid-gama-emission-tomography-hgetfy16-annual-report
  7. Choi HJ, Kang IS, Kim KB, Chung YH, Min CH. Optimization of single-photon emission computed tomography system for fast verification of spent fuel assembly: a Monte Carlo study. J Instrum. 2019;14(7):T07002.
  8. Choi SH, Choi HJ, Min CH, Chung YH, Ahn JJ. Development of de-noised image reconstruction technique using convolutional AutoEncoder for fast monitoring of fuel assemblies. Nucl Eng Technol. 2021;53(3):888-893.
  9. Choi H, Cheon BW, Baek MK, Chung H, Chung YH, You SH, et al. Experimental evaluation of fuel rod pattern analysis in fuel assembly using Yonsei single-photon emission computed tomography (YSECT). Nucl Eng Technol. 2022;54(6):1982-1990.
  10. Park HM, Joo KS, Kim JH, Kim DS, Park KH, Park CJ, et al. Evaluation of the photon transmission efficiency of light guides used in scintillation detectors using LightTools code. J Radiat Prot Res. 2016;41(3):282-285.
  11. Agostinelli S, Allison J, Amako K, Apostolakis J, Araujo H, Arce P, et al. GEANT4: a simulation toolkit. Nucl Instrum Methods Phys Res A. 2023;506(3):250-303.
  12. Cayouette F, Laurendeau D, Moisan C. DETECT2000: an improved Monte-Carlo simulator for the computer aided design of photon sensing devices. In: Lessard RA, Lampropoulos GA, Schinn GW, editors. Proceedings of SPIE, Applications of Photonic Technology 5. Society of Photo Optical; 2003. p. 69-76.
  13. Kim HS, Smith MB, Koslowsky MR, Kwak SW, Ye SJ, Kim G. Characterization of a CLYC detector and validation of the Monte Carlo simulation by measurement experiments. J Radiat Prot Res. 2017;42(1):48-55.
  14. Sorenson JA, Phelps ME. Physics in nuclear medicine. 2nd ed. Grune & Stratton; 1987. p. 115-121.
  15. Berger MJ, Hubbell JH, Seltzer SM, Chang J, Coursey JS, Sukumar R, et al. XCOM: Photon Cross Sections Database. NIST Standard Reference Database 8 (XGAM) [Internet]. Physical Measurement Laboratory; 2010 [cited 2024 Jan 30]. Available from: http://www.nist.gov/pml/data/xcom/index.cfm
  16. Mahbod A, Tsakiraki E. Comparison of FBP and iterative methods. Royal Institute of Technology; 2015.