1 |
M. Schneider, A. Froggatt, World Nuclear Industry Status Report 2018, 2018, p. 289.
|
2 |
K. Jeong, D. Lee, K. Lee, H. Lim, A qualitative identification and analysis of hazards, risks and operating procedures for a decommissioning safety assessment of a nuclear research reactor, Ann. Nucl. Energy 35 (2008) 1954-1962.
DOI
|
3 |
H.S. Park, S.K. Kim, K.W. Lee, C.H. Jung, S.I. Jin, Visualization of a dismantling environment for an evaluation of a worker's dose during the decommissioning of KRR-1&2, Ann. Nucl. Energy 35 (2008) 1117-1124.
DOI
|
4 |
H.-R. Kim, S.-K. Kim, B.-K. Seo, K.-W. Lee, J.-H. Park, The preliminary 3D dynamic simulation on the RSR dismantling process of the KRR-1&2, Ann. Nucl. Energy 30 (2003) 1487-1494.
DOI
|
5 |
Sang-Ho Lee, H.-W. Seo, C.-L. Kim, Preparation of radiological environmental impact assessment for the decommissioning of nuclear power plant in Korea, J. Nucl. Fuel Cycle Waste Technol. 16 (2018) 107-122.
DOI
|
6 |
J.F. Briesmeister, MCNPTM-A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709-M, Los Alamos National Laboratory, 2000, p. 2.
|
7 |
IAEA, Radiological Characterization of Shut Down Nuclear Reactors for Decommissioning P Urposes, Technical Reports Series, 1998.
|
8 |
K.-J. Lee, H.-S. Kim, S.-W. Sin, M.-J. Song, Y.-K. Lee, Preliminary estimation of activation products inventory in reactor components for Kori unit 1 decommissioning, J. Radiat. Protect. Res. 28 (2003) 109-116.
|
9 |
D. Lee, H.R. Kim, Preliminary source term assessment on Kori unit 1 radioactive bioshield for decommissioning, in: Transactions of the Korean Nuclear Society Spring Meeting, 2018.
|
10 |
D. Lee, in: Spatial Distribution of Radioactivity in Bioshield by Using Monte Carlo Simulation for Reducing Waste Volume and External Dose during Kori Unit 1 Nuclear Power Plant Decommissioning, Graduate School of UNIST, Ulsan, 2019. Ulsan.
|
11 |
F. Vermeersch, C.V. Bosstraeten, Development of the VISIPLAN ALARA Planning Tool, 1998.
|
12 |
F. Vermeersch, ALARA pre-job studies using the VISIPLAN 3D ALARA planning tool, Radiat. Protect. Dosim. 115 (2005) 294-297.
DOI
|
13 |
A. Anunti, H. Larsson, M. Edelborg, in: Decommissioning Study of Forsmark NPP, Swedish Nuclear Fuel and Waste Management Co., 2013.
|
14 |
U.S.DOE, Liquid Nitrogen-Cooled Diamond-Wire Concrete Cutting Innovative Technology Summary Report (DOE/EM-0392), 1998. Washington.
|
15 |
TYROLIT, Safety Manual System Description-Diamond Wire Saws, Pfaffikon, 2003.
|
16 |
U. NRC, 10 CFR Part 20: Standards for Radiation Protection, 2019. Washington, DC.
|
17 |
ICRP, ICRP publication 103, Ann. ICRP 37 (2007) 2.
|
18 |
P.O. Lopez, L. Dauer, R. Loose, C. Martin, D. Miller, E. Vano, M. Doruff, R. Padovani, G. Massera, C. Yoder, ICRP publication 139: occupational radiological protection in interventional procedures, Ann. ICRP 47 (2018), 1-118.
|