1 |
F. Vermeersch, Dose Assessment and ALARA Calculation with VISIPLAN 3D ALARA Planning Tool. Training Course, IDPBW Nuclear Studies, SCK-CEN, Mol, 2005.
|
2 |
W.F. Bakr, Assessment of the radiological impact of oil refining industry, J. Environ. Radioact. 101 (3) (2010) 237-243.
DOI
|
3 |
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.
DOI
|
4 |
Notice No, Of Nuclear Safety and Security Commission, Regulations on the Classification of Radioactive Waste and its Own Disposal Standards, 2017-65 (in Korean).
|
5 |
I. Stamatelatos, Dose assessment for decommissioning planning of the Greek Research reactor primary cooling system, Int. Nucl. Saf. J. 3 (4) (2014) 37-42.
|
6 |
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
|
7 |
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.
DOI
|
8 |
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
|
9 |
Icrp, Publication 51: Date for Use in Protection against External Radiation, 17, Pergamon Press, 1987.
|
10 |
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.
|
11 |
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.
DOI
|
12 |
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.
|
13 |
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.
|
14 |
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.
DOI
|
15 |
Icrp Publication 66, Annals of the Icrp, Human Respiratory Tract Model for Radiological Protection, Pergamon, 1994.
|
16 |
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.
DOI
|
17 |
Khnp, Wolseong Nuclear Power Plant Tritium and 14C Emission Status, 2005 (in Korean).
|
18 |
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.
|
19 |
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.
|
20 |
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.
DOI
|
21 |
F. Vermeersch, VISIPLAN 3D ALARA Planning Tool, User's Guide, SCK-CEN, Mol, 2000, pp. 1-21. NS/Fve/IDPBW/00-775.
|