Browse > Article
http://dx.doi.org/10.1016/j.net.2021.06.007

Dose evaluation of workers according to operating time and outflow rate in a spent resin treatment facility  

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))
Publication Information
Nuclear Engineering and Technology / v.53, no.11, 2021 , pp. 3824-3836 More about this Journal
Abstract
Workers' safety from radiological exposure in a 1 ton/day capacity spent resin treatment facility was evaluated according to the operating times and outflow rate due to process related leakages. The conservative annual dose based on the operating times of the workers exceeded the dose limit by at least 7.38E+01 mSv for close work. The realistic dose range was derived as 1.62E+01 mSv-6.60E+01 mSv. The conservative and realistic annual doses for remote workers were 1.33E+01 mSv and 3.00E+00 mSv respectively, which were less than the dose limit. The MWR was identified as the major contributor to worker exposure within the 1 h period required for removal of radioactive materials. The dose considering both internal and external exposures without APF was derived to be 1.92E+01 mSv for conservative evaluation and 4.00E+00 mSv for realistic evaluation. Furthermore, the dose with APF was derived as 7.27E-01 mSv for conservative evaluation and 1.51E-01 mSv for realistic evaluation. Considering the APF for leakage from all parts, the dose range was derived as 1.25E+00 mSv-2.03E+00 mSv for conservative evaluation and 2.61E-01 mSv-4.23E-01 mSv for realistic evaluation. Hence, it was confirmed that radiological safety was secured in the event of a leakage accident.
Keywords
Dose evaluation; Outflow rate; Spent resin mixture; Treatment facility; Carbon-14;
Citations & Related Records
연도 인용수 순위
  • Reference
1 F. Vermeersch, Dose Assessment and ALARA Calculation with VISIPLAN 3D ALARA Planning Tool, Training Course, IDPBW Nuclear Studies, Boeretang: SCK, CEN, Belgium, 2005.
2 F. Paquet, G. Etherington, M.R. Bailey, R.W. Leggett, J. Lipsztein, W. Bolch, et al., ICRP (publication), ICRP Publication 130: occupational intakes of radionuclides: Part 1, Ann, ICRP 44 (2015) (2015) 5-188. F. Paquet, G. Etherington, M.R. Bailey, R.W. Leggett, J. Lipsztein, W. Bolch, K.F. Eckerman, J.D. Harrison.   DOI
3 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.   DOI
4 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 (2018) 65-82.   DOI
5 National Council on Radiation Protection and Measurements, C-14 in the environment, NCRP Rep. 81 (1985).
6 US Nuclear Regulatory Commission, Final Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive Waste Spent Ion Exchange Resins from Commercial Nuclear Power Plants, Office of Federal and State Materials and Environmental Management Programs, 2013.
7 S.J. Lee, H.Y. Yang, K.D. Kim, Analysis on the Generation Characteristics of 14C in PHWR and the Adsorption and Desorption Behavior of 14C onto Ion Exchange Resin.
8 Enforcement ordinance of nuclear safety act, Definition Dose Limit 2 (2015) (in Korean).
9 C. Gao, M. Jia, Y. Wang, The study of microwave ashing for spent radioactive resin, in: Proceedings of the 20th Pacific Basin Nuclear Conference, 2016. Singapore.
10 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 (2008) 261-273.   DOI
11 International Atomic Energy Agency, Application of Ion Exchange Processes for Treatment of Radioactive Waste and Management of Spent Ion Exchangers, STI, 2002. DOC/010/408.
12 M.I. Ojovan, W.E. Lee, S.N. Kalmykov, An Introduction to Nuclear Waste Immobilisation, third ed., Elsevier, 2019.
13 Z. Wan, L. Xu, J. Wang, Treatment of spent radioactive anionic exchange resins using Fenton-like oxidation process, Chem. Eng. J. 284 (2016) 733-740.   DOI
14 Occupational Safety, Health Administration, Assigned Protection Factors for the Revised Respiratory Protection Standard, Maroon E-Books, 2019.
15 D.R. MacKenzie, M. Lin, R.E. Barletta, Permissible Radionuclide Loading for Organic Ion Exchange Resins from Nuclear Power Plants, Brookhaven National Lab., 1983. No. NUREG/CR-2830; BNL-NUREG-51565.
16 W. Feng, Y. Wang, J. Li, K. Gao, H. An, Decomposition of spent radioactive ionexchange resin using photo-Fenton process, J. Chem. Technol. Biotechnol. 95 (2020) 2522-2529.   DOI
17 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.   DOI
18 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 (in Korean).   DOI
19 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.
20 J. Kim, B. Tseren, Occupational ALARA planning for reactor pressure vessel dismantling at Kori Unit 1, Int. J. Environ. Res. Publ. Health 17 (2020) 5346.   DOI
21 U. Lee, W.N. Choi, H.R. Kim, Radiological impact assessment for workers on treatment of radioactive spent resin from heavy water reactors, J. Radiol. Prot. 39 (2019) 422-442.   DOI