Acknowledgement
This work was supported by the Korea Institute of Energy Technology Evaluation and Planning (KETEP) and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea (No. 2021171020001A).
References
- Posiva Oy. Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto - Description of the Disposal System 2012, Posiva Oy Report, POSIVA 2012-05 (2012).
- Svensk Karnbranslehantering AB. Design and Production of the KBS-3 Repository, SKB Technical Report, SKB TR-10-12 (2010).
- L. Agrenius. Criticality Safety Calculations of Disposal Canisters, Svensk Karnbranslehantering AB Public Report, SKBdoc 1193244 Ver. 4 (2010).
- L. Agrenius. Criticality Safety Calculations of Storage Canisters, Svensk Karnbranslehantering AB Technical Report, SKB TR-02-17 (2002).
- M. Anttila. Criticality Safety Calculations for Three Types of Final Disposal Canisters, Posiva Oy Working Report, POSIVA 2005-13 (2005).
- D. Mennerdahl. Assessment of PWR Fuel Depletion and of Neutron Multiplication Factors for Intact PWR Fuel Copper Canisters - Main Review Phase, Stral sakerhets myndigheten Report, SSM 2013:16 (2013).
- D. Mennerdahl. Review of the Nuclear Criticality Safety of SKB's Licensing Application for a Spent Nuclear Fuel Repository in Sweden, Stral sakerhets myndigheten Report, SSM 2012:65 (2012).
- H. Yun, K. Park, W. Choi, and S.G. Hong, "An Efficient Evaluation of Depletion Uncertainty for a GBC-32 Dry Storage Cask With PLUS7 Fuel Assemblies Using the Monte Carlo Uncertainty Sampling Method", Ann. Nucl. Energy, 110, 679-691 (2017). https://doi.org/10.1016/j.anucene.2017.07.020
- H. Yun, D.Y. Kim, K. Park, and S.G. Hong, "A Criticality Analysis of the GBC-32 Dry Storage Cask With Hanbit Nuclear Power Plant Unit 3 Fuel Assemblies From the Viewpoint of Burnup Credit", Nucl. Eng. Technol., 48(3), 624-634 (2016). https://doi.org/10.1016/j.net.2016.01.011
- G. Radulescu, I.C. Gauld, G. Ilas, and J.C. Wagner, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses - Isotopic Composition Predictions, U.S. Nuclear Regulatory Commission, NUREG/CR-7108, Oak Ridge National Laboratory, ORNL/TM-2011/509 (2012).
- J.M. Scaglione, D.E. Mueller, J.C. Wagner, and W.J. Marchall, An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses - Criticality (keff) Predictions, U.S. Nuclear Regulatory Commission, NUREG/CR-7109, Oak Ridge National Laboratory, ORNL/TM-2011/514 (2012).
- H. Raiko. Canister Design 2012, Posiva Oy Report, POSIVA 2012-13 (2013).
- H. Raiko. Canister Production Line 2012 - Design, Production and Initial State of the Canister, Posiva Oy Report, POSIVA 2012-16 (2012).
- I. Thomas. Task Order 18: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems - UPDATED FINAL REPORT, U.S. Department of Energy Report (2015).
- E. Hardin, E. Matteo, and T. Hadgu, Multi-Pack Disposal Concepts for Spent Fuel, U.S. Department of Energy, FCRD-NFST-2016-000640 Rev. 1 (2016).
- G. Radulescu and I.C. Gauld. STARBUCS: A Scale Control Module for Automated Criticality Safety Analyses Using Burnup Credit, Oak Ridge National Laboratory Report, ORNL/TM-2005/39, Version 6.1, Section. C10 (2011).
- M. Juvankoski. Buffer Design 2012, Posiva Oy Report, POSIVA 2012-14 (2013).
- M. Juvankoski, K. Ikonen, and T. Jalonen. Buffer Production Line 2012 - Design, Production and Initial State of the Buffer, Posiva Oy Report, POSIVA 2012-17(2012).