방사선산업학회지 (Journal of Radiation Industry)

한국방사선산업학회 (Korean Society of Radiation Industry)
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감마핵종 In-Situ 측정 연구 동향 분석 및 방사능 측정 효율 민감도 평가

In-Situ Gamma Spectrometry Research Analysis and Radiation Efficiency Sensitivity Evaluation

  • 라현준 (경희대학교 원자력공학과) ;
  • 김혁재 (경희대학교 원자력공학과) ;
  • 이성연 (경희대학교 원자력공학과) ;
  • 곽민우 (경희대학교 원자력공학과) ;
  • 김광표 (경희대학교 원자력공학과)
  • Hyun Jun Na (Department of Nuclear Engineering, Kyung Hee University) ;
  • Hyeok Jae Kim (Department of Nuclear Engineering, Kyung Hee University) ;
  • Seong Yeon Lee (Department of Nuclear Engineering, Kyung Hee University) ;
  • Min Woo Kwak (Department of Nuclear Engineering, Kyung Hee University) ;
  • Kwang Pyo Kim (Department of Nuclear Engineering, Kyung Hee University)
  • 투고 : 2023.02.13
  • 심사 : 2023.03.13
  • 발행 : 2023.03.31
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초록

Since a large amount of radioactive waste is expected to be generated due to permanent shutdown of many nuclear power plants, it is necessary to prepare efficient management methods for radioactive waste. Therefore, there is a need for a based study to apply the In-Situ gamma spectrometry, which can simplify the measurement procedure. The purpose of this study is to analyze research cases of In-Situ gamma spectrometry and to analyze the sensitivity of measurement according to influencing factors on In-Situ gamma spectrometry. Research cases of five institutions, including the CERN and the Imperial College Reactor Centre (ICRC), were selected as the institutions to be investigated. Research on the In-Situ gamma spectrometry was conducted on the satisfaction of the acceptance criteria for radioactive waste and the analysis of residual radioactivity in the site. In-Situ Objective Counting System (ISOCS) was used as a major measuring device. Sampling and computer code were used to verify the analysis results. For evaluation of measuring sensitivity according to influencing factors on In-Situ gamma spectrometry, the thickness of the measurement target, the distance between the detector and the target, the angle of the collimator, and the contamination location were performed using ISOCS's Geometry Composer. In every case, based on 122 keV, the efficiency decreased as the energy increased in the high energy region, and the efficiency decreased as the energy decreased in the low energy region. As the target thickness increased, the efficiency decreased, and as the distance between target and detector increased, the efficiency decreased. As the distance between contamination and detector increased, the efficiency decreased, and as the angle of the collimator increased, the measurement efficiency increased. However, when simulating the measurement situation using Geometry Composer, the background is not considered, and the probability of incident in the background increases as the angle increases, so further research needs to be conducted in consideration of these. This study can be utilized when applying the In-Situ gamma spectrometry of radioactive waste clearance in the future.

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과제정보

본 연구는 원자력안전위원회의 재원으로 한국원자력안전재단의 지원을 받아 수행한 원자력안전연구사업의 연구결과입니다(No. 2106041).

참고문헌

  1. NSSC. 2022. Enforcement Decree Of The Nuclear Safety Act Article 107 Paragraph 1. 
  2. MOTIE. 2020. Korean 2nd Basic Plan for the Management of LILW. 
  3. KORAD. 2020. Implementation Plan for the Management of LILW in 2020. 
  4. IAEA. 1997. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. INFCIRC/546. 
  5. Sappok M. 1987. Results of Metallic Waste Treatment by Melting, Siemplekamp Gtiesserei GmbH & Co, CONF-874048, Westinghouse Handford, October, Vol 1:115-127. 
  6. Mies HP and Stang W. 1991. Decommissioning of Nuclear Power Plant Gundremmingen Unit A, Company Report-Kernkraftwerke Gundremmingen Betriebsgesellschaft. 
  7. Menon S, Hernborg G and Andersson L. 1990. Melting of low-level contaminated steels, Studsvik AB, Sweden in Decommissioning of Nuclear Installations, Elsevier Applied Science. 
  8. Gomer CR and Lambley JT. 1985. Melting of contaminated steel scrap arising in the dismantling of nuclear power plants, British Steel Corporation, for Commission of the European Communities, Final Report Contract No. DED-002-UK. 
  9. Jacquet-Francillon N, Jouan A, Moncouyoux JP and Sombret C. 1991. Melting-A Promising Technique for Processing Metallic Decladding Materials from Irradiated Nuclear Fuels, ICCN 91, Bombay, India. 
  10. Gelbutovsky AB, Kishhkin SA, Mochenov MI, Troshev AV, Cheremisin PI and Chernichenko AA. 2006. CJSC ECOMET-S facility for reporocessing and utilization of radioactive metal waste-operating experience. J. Nucl. Sci. Technol. 2(1-2):31-41. https://doi.org/10.1504/IJNEST.2006.010645. 
  11. Sin GB, Gang IS, Jang WH and Hong DS. 2015. Self-Disposal Process of Steel VLLW by KAERI. Abstracts of Proceedings of the Korean Radioactive Waste Society AUTUMN 2015:425-426. 
  12. Joe HT, Lee KH, Kim JC, Kim HC and Lee ED. 2011. Establishment and Execution Method of Self Disposal Procedure for Iron Radioactive Waste at Uljin 3 Nuclear Power Plant. Abstracts of Proceedings of the Korean Association For Radiation Protection SPRING 2011:114-115. 
  13. Jun HM, Kim JH, Song JJ, Kang TU, Lee JC, Han KH and Seo JS. 2016. Radioactivity Measurement and efficiency evaluation of 152Eu Radioactive Standard Source of Using the ISOCS. Abstracts of Proceedings of the Korean Radioactive Waste Society SPRING 2016:345-346. 
  14. Mirion Technologies. 2013. Model S573 ISOCS Calibration Software. 
  15. Mirion Technologies. 2008. In Situ Gamma Spectroscopy with ISOCSTM, an In Situ Object Counting System. 
  16. Frosio T, Bertreix P, Magistris M, Menaa N, Michaud R, Rimlinger M, Theis C, Ulrici L and Zaffora B. 2020. An enhanced characterization process for the elimination of very low level radioactive waste in particle accelerators. Applied Radiation and Isotopes 166. https://doi.org/10.1016/j.apradiso.2020.109312. 
  17. Shuhaimi AIM. 2016. Characterisation of Imperial College Reactor Centre Legacy Waste Using Gamma-Ray Spectrometry. AIP Conference Proceedings 1704. https://doi.org/10.1063/1.4940099. 
  18. Chapman JA, Boerner AJ and Abelqist EW. 2006. Spatially-Dependent Measurements of Surface and Near-Surface Radioactive Material Using In situ Gamma Ray Spectrometry (ISGRS) For Final Status Surveys. 
  19. Hong SB, Ju MS, Jung KH, Lee GW and Jung US. 2008. Evaluation of Residual Radioactivity in Buildings Using ISOCS. Abstracts of Proceedings of the Korean Radioactive Waste Society May 2008:55-56. 
  20. Song JS, Lee SH and Shin SS. 2018. A Study on the Assessment of Source-term for PWR Primary System Using MonteCarlo Code. J. Nucl. Fuel Cycle Waste Technol. 16(3):331-337. https://doi.org/10.7733/jnfcwt.2018.16.3.331.