Evaluation of Canister Weld Flaw Depth for Concrete Storage Cask
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Moon, Tae-Chul
(Korea Radioactive Waste Agency)
Cho, Chun-Hyung (Korea Radioactive Waste Agency) Jung, Sung-Hun (Korea Nuclear Engineering & Service Corp) Lee, Young-Oh (Korea Nuclear Engineering & Service Corp) Jung, In-su (Korea Nuclear Engineering & Service Corp) |
1 | American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section III, Division 1, Subsection NB - Class 1 components (2010). |
2 | NUREG-1536, Revision 1, Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility (2010). |
3 | American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI - Rules for In-service Inspection of Nuclear Power Plant Components, Division 1, Appendix C (2010). |
4 | DASSAULT SIMULIA, ABAQUS 6.10 Documentation (2010). |
5 | ANSI/ANS 57.9, American National Standard Design Criteria for an Independent Spent Fuel Storage Installation - Dry Storage Type (1984). |
6 | American Concrete Institute (ACI) 349R-01, Code Requirements for Nuclear Safety related Concrete Structures (2001). |
7 | American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section II, Part A - Ferrous Material Specifications (2010). |
8 | American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section II, Part D - Properties (Customary) (2010). |
9 | Korea Radioactive Waste Agency, Concrete Storage Cask Technical Report, 14220-P1-N-TR-37 (2014). |
10 | Interim Stall Guidance (ISG) -4, Revision 1, Cask Closure Weld Inspections (2014). |
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