Evaluation of radiological safety according to accident scenarios for commercialization of spent resin mixture treatment device
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Spent resin often exceeds radiation limits for safe disposal, creating a need for commercial-scale treatment techniques to reduce resin radioactivity. In this study, the radiological safety of a commercialized spent resin treatment device with a treatment capacity of 1 ton/day was evaluated. The results confirm that the device is radiologically safe in the event of an accident. This device desorbs 14C from the spent resin, allowing disposal as low-level waste instead of intermediate-level waste. The device also reduces overall waste by recycling the extracted 14C. Potential accident scenarios were explored to enable dose assessments for both internal and external exposure while preventing further spillage of the device and processing the spilled resin. The scenarios involved the development of a surface fracture on the resin mixture separator and microwave systems, which were operated under pressure and temperature of 0 e6 bar and 0e150 C, respectively. In the case of accidents with separator and microwave device, the maximum allowable working time of worker were derived, respectively, considering external and internal exposures. When wearing the respirator corresponding to APF 50, in the case of the microwave device accident scenario, the radiological safety was confirmed when the maximum worker worked within 132.1 h
Abstract
Spent resin often exceeds radiation limits for safe disposal, creating a need for commercial-scale treatment techniques to reduce resin radioactivity. In this study, the radiological safety of a commercialized spent resin treatment device with a treatment capacity of 1 ton/day was evaluated. The results confirm that the device is radiologically safe in the event of an accident. This device desorbs 14C from the spent resin, allowing disposal as low-level waste instead of intermediate-level waste. The device also reduces overall waste by recycling the extracted 14C. Potential accident scenarios were explored to enable dose assessments for both internal and external exposure while preventing further spillage of the device and processing the spilled resin. The scenarios involved the development of a surface fracture on the resin mixture separator and microwave systems, which were operated under pressure and temperature of 0 e6 bar and 0e150 C, respectively. In the case of accidents with separator and microwave device, the maximum allowable working time of worker were derived, respectively, considering external and internal exposures. When wearing the respirator corresponding to APF 50, in the case of the microwave device accident scenario, the radiological safety was confirmed when the maximum worker worked within 132.1 h
참고문헌 (16)
- Processing Technology Development of Heavy-Water Reactor Resin Mixture Containing C-14 to Ensure Disposal Safety, 20151520302120, "Y.K. Choi", Industry & Energy of the Republic of Korea, ~ (2018)
- D. Moir, "Determination of 14C in spent moderator ion-exchange resin from bruce nuclear generating station A", J. Radioanal. Nucl. Chem, 185(1), pp.69~81 (1994)
- M. L. Joshi, "Measurement of 14C emission rates from a pressurised heavy water reactor", Health Phys, 52(6), pp.787~791 (1987)
- 홍성욱, "중저준위방사성폐기물 처분시설의 처분농도제한치 설정에 대한 고찰 II: 최적화 방법론 개발 및 적용", Journal of Nuclear Fuel Cycle and Waste Technology, 15(3), pp.265~279 (2017), 한국방사성폐기물학회[DOI]
- W. N. Choi, "Radiological assessment on spent resin treatment facility and transportation for radioactive waste disposal", Prog. Nucl. Energy, 118, pp.103125~ (2020)
- Development of Adsorbent for C-14 Gas Trapping and Characteristics Evaluation, "G.I. Park", Korea Atomic Energy Research Institute, ~, pp.KAERI (2006), CR-245[DOI]
- F. Vermeersch, "Visiplan 3D Alara Planning Tool, User's Guide", SCK CEN, ~ (2005)
- A. R. Benedetto, "Data for use in protection against external radiation, ICRP publication 51", Ann. ICRP, 17, pp.1~132 (1987)
- K. Eckerman, "ICRP publication 119 : compendium of dose coefficients based on ICRP publication 60", Ann. ICRP, 41, pp.1~130 (2012)
- Hyeon-Oh Park, "Heavy Water Reactor (HWR) Spent Resin Mixture Processor Development", Proceedings of the Korean Radioactive Waste Society Conference (2017), Korean Radioactive Waste Society
- K.R. Lee, "Development of C-14 stripping method from waste resin generated from HWR via microwave treatment: Part 1, characterization of anion and cation surrogate waste resin with microwave treatment", Proceedings of the Conference and Symposium Korean Radioactive Waste Society Fall Meeting, pp.384~ (2017)
- M. Hornacek, "The use of codes VISIPLAN 3D ALARA and MATLAB for assessment of contributions from radiation sources within the decommissioning of nuclear power plants", Proceedings of the 21st international conference on Applied Physics of Condensed Matter, pp.238~242 (2015)
- N. Safety, "Standards for Protection against Radiation", Notice No. 2019-10, ~ (2019)
- Occupational Safety and Health Administration, "Assigned protection factors for the revised respiratory protection standard OSHA 3352-02", 3~6 (2009)
- 송종순, "BiDAS를 적용한 원전 해체 공정 시 발생되는 방사성 에어로졸의 내부피폭영향평가 사전 연구", Journal of Nuclear Fuel Cycle and Waste Technology, 16(4), pp.473~478 (2018), 한국방사성폐기물학회[DOI]
- ICRP, "ICRP Publication 66, Human Respiratory Tract Model for Radiological Protection, 66", Elsevier Health Sciences, ~ (1995)
