Nuclear Engineering and Technology

  • 제54권2호
  • /
  • Pages.442-448
  • /
  • 2022
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Evaluation of dose received by workers while repairing a failed spent resin mixture treatment device

  • Choi, Woo Nyun (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) ;
  • Byun, Jaehoon (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) ;
  • Kim, Hee Reyoung (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST))
  • 투고 : 2021.03.09
  • 심사 : 2021.06.06
  • 발행 : 2022.02.25
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초록

Intermediate-level radioactive waste (ILW) is not subject to legal approval for cave disposal in Korea. To solve this problem, a spent resin treatment device that separates 14C-containing resin from zeolite/activated carbon and desorbs 14C through a microwave device has been developed. In this study, we evaluated the radiological safety of the operators performing repair work in the event of a failure in such a device treating 1 ton of spent resin mixture per day. Based on the safety evaluation results, it is possible to formulate a design plan that can ensure the safety of workers while developing a commercialized device. When each component of the resin treatment device can be repaired from the outside, the maximum and minimum allowable repair times are calculated as 263.2 h and 27.7 h for the 14C-detached resin storage tank and zeolite/activated carbon storage tank, respectively. For at least 6 h per quarter, the worker's annual dose limit remains within 50 mSv/year; further, over 5 years, it remained within 100 mSv. At least 6 h of repair time per quarter is considered, under conservative conditions, to verify the radiological safety of the worker during repair work within that time.

키워드

과제정보

This work was supported by the Korea Institute of Energy Technology Evaluation and Planning; the Ministry of Trade, Industry & Energy of the Republic of Korea (grant no. 20191510301110); and the National Research Foundation of Korea (NRF) grant funded by the Korean government (MSIP: Ministry of Science, ICT, and Future Planning) NRF-2016M2B2B1945082.

참고문헌

  1. J. Byun, W.N. Choi, H.R. Kim, Radiological safety assessment of lead shielded spent resin treatment facility with the treatment capacity of 1 ton/day, Nucl. Eng. Technol. 53 (2021) 273-281. https://doi.org/10.1016/j.net.2020.06.012
  2. S.K. Fiskum, I.E. Burgeson, O.T. Farmer III, L.R. Greenwood, C.Z. Soderquist, M.J. Steele, M.P. Thomas, Spherical Resorcinol-Formaldehyde Resin Analysis Following Actual Hanford Tank Waste Processing, PNWD-3752, Battelle-Pacific Northwest Division, Richland, WA, 2006, pp. 1.1-5.1. WTP-RPT-144, Rev 0.
  3. S.K. Fiskum, D.L. Blanchard Jr., M.J. Steele, J.J. Wagner, Analysis of spent SuperLig® 644 resin used for cesium removal from Hanford tank wastes, Solvent Extr, Ion Exch 24 (1) (2006) 65-79. https://doi.org/10.1080/07366290500388426
  4. C.P. Huang, T.Y. Lin, L.H. Chiao, H.B. Chen, Characterization of radioactive contaminants and water treatment trials for the Taiwan Research Reactor's spent fuel pool, J. Hazard Mater. 233 (2012) 140-147. https://doi.org/10.1016/j.jhazmat.2012.07.009
  5. A. Magnusson, K. Stenstrom, P.-O. Aronsson, 14C in spent ion-exchange resins and process water from nuclear reactors: a method for quantitative determination of organic and inorganic fractions, J. Radioanal. Nucl. Chem. 275 (2) (2008) 261-273. https://doi.org/10.1007/s10967-007-7035-0
  6. Khnp, Wolseong Nuclear Power Plant Tritium and 14C Emission Status, 2005 (in Korean).
  7. Notice No, Of Nuclear Safety and Security Commission, Regulations on the Classification of Radioactive Waste and its Own Disposal Standards, 2017-65 (in Korean).
  8. W.F. Bakr, Assessment of the radiological impact of oil refining industry, J. Environ. Radioact. 101 (3) (2010) 237-243. https://doi.org/10.1016/j.jenvrad.2009.11.005
  9. E.I. Tolstykh, M.O. Degteva, V.P. Kozheurov, E.A. Shishkina, A.A. Romanyukha, A. Wieser, P. Jacob, Strontium metabolism in teeth and enamel dose assessment: analysis of the Techa river data, Radiat. Environ. Biophys. 39 (3) (2000) 161-171. https://doi.org/10.1007/s004110000059
  10. I. Stamatelatos, Dose assessment for decommissioning planning of the Greek Research reactor primary cooling system, Int. Nucl. Saf. J. 3 (4) (2014) 37-42.
  11. S.W. Hong, M.S. Kim, K.I. Jung, J.B. Park, Determination of radionuclide concentration limit for low and intermediate-level radioactive waste disposal facility II: application of optimization methodology for underground silo type disposal facility, J. Nucl. Fuel Cycle Waste Technol. 15 (3) (2017) 265-279. https://doi.org/10.7733/jnfcwt.2017.15.3.265
  12. F. Vermeersch, VISIPLAN 3D ALARA Planning Tool, User's Guide, SCK-CEN, Mol, 2000, pp. 1-21. NS/Fve/IDPBW/00-775.
  13. W.N. Choi, U. Lee, H.R. Kim, Radiological assessment on spent resin treatment facility and transportation for radioactive waste disposal, Prog. Nucl. Energy 118 (2020) 103125. https://doi.org/10.1016/j.pnucene.2019.103125
  14. F. Vermeersch, VISIPLAN 3D ALARA Planning Tool Version 4.0, Step by Step Guide, SCK-CEN, Mol, 2006, pp. 1-21. NS/Fve/IDPBW/00-775.
  15. F. Vermeersch, Dose Assessment and ALARA Calculation with VISIPLAN 3D ALARA Planning Tool. Training Course, IDPBW Nuclear Studies, SCK-CEN, Mol, 2005.
  16. Icrp, Publication 51: Date for Use in Protection against External Radiation, 17, Pergamon Press, 1987.
  17. F. Vermeersch, VISIPLAN 3D ALARA Planning Tool Version 4.0 Calculation Method & Validation Tests, SCK-CEN, Mol, 2004, pp. 14-36. Ns/Fve/IDPBW/04-505 ver. 2.
  18. Occupational Safety and Health Administration, U.S. Department of Labor, Assigned Protection Factors for the Revised Respiratory Protection Standard, 2015, pp. 3-46. OSHA 3352-02 2009.
  19. J.S. Song, H.Y. Lee, S.I. Kim, A preliminary study on the evaluation of internal exposure effect by radioactive aerosol generated during decommissioning of NPPs by using BiDAS, J. Nucl. Fuel Cycle Waste Technol. 16 (4) (2018) 473-478. https://doi.org/10.7733/jnfcwt.2018.16.4.473
  20. Icrp Publication 66, Annals of the Icrp, Human Respiratory Tract Model for Radiological Protection, Pergamon, 1994.
  21. K. Eckerman, J. Harrison, H.-G. Menzel, C.H. Clement, ICRP Publication 119: compendium of dose coefficients based on ICRP Publication 60, in: C.H. Clement (Ed.), Annals of the ICRP, Elsevier, 42, 2013, pp. e1-e130.