SHIELDING ANALYSIS OF DUAL PURPOSE CASKS FOR SPENT NUCLEAR FUEL UNDER NORMAL STORAGE CONDITIONS |
Ko, Jae-Hun
(Korea Nuclear Engineering & Service Co.)
Park, Jea-Ho (Korea Nuclear Engineering & Service Co.) Jung, In-Soo (Korea Nuclear Engineering & Service Co.) Lee, Gang-Uk (Korea Nuclear Engineering & Service Co.) Baeg, Chang-Yeal (Korea Radioactive Waste Management Corporation) Kim, Tae-Man (Korea Radioactive Waste Management Corporation) |
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2 | NUREG/CR-6802, Recommendations for Shielding Evaluations for Transport and Storage Packages, Oak Ridge National Laboratory, US NRC, May 2010. |
3 | LA-UR-03-1987, MCNP - A General Monte Carlo N Particle Transport Code, Version 5, Release 1.40, 2005 |
4 | YAEC-1937, Axial Burnup Profile Database Pressurized Water Reactors, Yankee Atomic Electric Company, Bolton, Massachusetts, May 1997. |
5 | Conversion Coefficients for Use in Radiological Protection against External Radiation, Annals of the ICRP Publication 74, 1996. |
6 | 10 CFR Part 72, Licensing requirements for the independent storage of spent nuclear fuel and high-level radioactive waste |
7 | NUREG-1567, Standard Review Plan for Spent Fuel Dry Storage Facility, US NRC, 2000. |
8 | NUREG-1536, Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility, US NRC, July 2010. |
9 | NRC Docket No. 72.1008, "Final Safety Analysis Report for the HI-STAR 100 Cask System. Rev.0" |
10 | NRC Docket No. 72.1014, "Final Safety Analysis Report for the HI-STORM 100 Cask System. Rev.4", June, 2006. |
11 | ORNL/TM-2005-39, SCALE A Modular Code for performing Standardized computer Analyses for Licensing Evaluation, Sect. 32 S2 "SAS2:A Coupled 1-D Depletion and Shielding Analysis Module." Ver. 5.1 |
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