Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Radiological safety assessment of lead shielded spent resin treatment facility with the treatment capacity of 1 ton/day

  • Byun, Jaehoon (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) ;
  • Choi, Woo Nyun (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))
  • Received : 2020.03.09
  • Accepted : 2020.06.10
  • Published : 2021.01.25
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Abstract

The radiological safety of the spent resin treatment facility with a14C treatment capacity of 1 ton/day was evaluated in terms of the external and internal exposure of worker according to operation scenario. In terms of external dose, the annual dose for close work for 1 h/day at a distance of more than 1 m (19.8 mSv) satisfied the annual dose limit. For 8 h of close work per day, the annual dose exceeded the dose limit. For remote work of 2000 h/year, the annual dose was 14.4 mSv. Lead shielding was considered to reduce exposure dose, and the highest annual dose during close work for 1 h/day corresponded to 6.75 mSv. For close work of 2000 h/year and lead thickness exceeding 1.5 cm, the highest value of annual dose was derived as 13.2 mSv. In terms of internal exposure, the initial year dose was estimated to be 1.14E+03 mSv when conservatively 100% of the nuclides were assumed to leak. The allowable outflow rate was derived as 7.77E-02% and 2.00E-01% for the average limit of 20 mSv and the maximum limit of 50 mSv, respectively, where the annual replacement of the worker was required for 50 mSv.

Keywords

Acknowledgement

This work was supported by the Korea Institute of Energy Technology Evaluation and Planning and the Ministry of Trade, Industry & Energy of the Republic of Korea (grant no. 20191510301110). This work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korean government (MSIP: Ministry of Science, ICT and Future Planning) NRF-2016M2B2B1945082, NRF-22A20153413555.

References

  1. N.S. Kamaruzaman, D.S. Kessel, C.L. Kim, Management of spent ion-exchange resins from nuclear power plant by blending method, J. Nucl Fuel Cycle Waste Technol. 16 (1) (2018) 65-82. https://doi.org/10.7733/jnfcwt.2018.16.1.65
  2. 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
  3. 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, Battelle-Pacific Northwest Report WTP-RPT-144, Rev 0, 2006.
  4. 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 (2006) 65-79. https://doi.org/10.1080/07366290500388426
  5. 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
  6. 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 (2007) 261-273. https://doi.org/10.1007/s10967-007-7035-0
  7. W.F. Bakr, Assessment of the radiological impact of oil refining industry, J. Environ. Radioact. 101 (2010) 237-243. https://doi.org/10.1016/j.jenvrad.2009.11.005
  8. 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 (2000) 161-171. https://doi.org/10.1007/s004110000059
  9. I. Stamatelatos, Dose assessment for decommissioning planning of the Greek Research reactor primary cooling system, Int Nucl Safety J 3 (2014) 37-42.
  10. V. Vaitkeviciene, J. Mazeika, Z. Skuratovic, S. Motiejunas, A. Vaidotas, A. Orysaka, S. Ovcinikov, 14C in radioactive waste for decommissioning of the ignalina nuclear power plant, Radiocarbon 55 (2013) 783-790. https://doi.org/10.1017/S0033822200057945
  11. A.B. Osteen, J.P. Bibler, Treatment of radioactive laboratory waste for mercury removal, Water, Air, & Soil Poll 56 (1991) 63-74. https://doi.org/10.1007/BF00342261
  12. S.V. S Rao, R. Lekshmi, A.G.S. Mani, P.K. Sinha, Treatment of low level radioactive liquid wastes using composite ion-exchange resins based on polyurethane foam, J. Radioanal. Nucl. Chem. 283 (2010) 379-384. https://doi.org/10.1007/s10967-009-0377-z
  13. The Code of Nuclear Safety and Security Commission: Regulation for the Clearance of Radioactive Waste, 2017.
  14. KHNP, Report on the Development of Spent Resin Treatment Technologies, 2006.
  15. G.I. Park, I.T. Kim, K.W. Kim, Development of Adsorbent for C-14 Gas Trapping and Characteristics Evaluation (No. KAERI/CR-245/2005, Korea Atomic Energy Research Institute, 2006.
  16. F. Vermeersch, Dose Assessment and ALARA Calculation with VISIPLAN 3D ALARA Planning Tool. Training Course, IDPBW Nuclear Studies, Boeretang: SCK. CEN, Belgium, 2005.
  17. K. Eckerman, J. Harrison, H.G. Menzel, H.C. Clement, ICRP publication 119: compendium of dose coefficients based on ICRP publication 60, Ann. ICRP 41 (2012) 1-130.
  18. Enforcement Ordinance of Nuclear Safety Act No.2: Definition of Dose Limit, 2015.
  19. F. Paquet, G. Etherington, M.R. Bailey, R.W. Leggett, J. Lipsztein, W. Bolch, J.D. Harrison, ICRP publication 130: occupational intakes of radionuclides: Part 1, Ann. ICRP 44 (2015) 5-188. https://doi.org/10.1177/0146645315577539
  20. Occupational Safety, Health Administration, Assigned Protection Factors for the Revised Respiratory Protection Standard, Maroon Ebooks, 2019.
  21. E.K. Chung, Characteristics of internal and external exposure of radon and thoron in process handling monazite, J Korean Soc Occup Environ Hyg 29 (2019) 167-175. https://doi.org/10.15269/JKSOEH.2019.29.2.167