참고문헌
- Raiko. H., Salo. J. P., 'Design Report of the Canister for Nuclear Fuel Disposal,' Report POSIVA 96-13, Posiva Oy, Helsinki, ISBN 951-652-012-x, Finland, 1996
- Raiko, H., Salo, J.P., 'Design Report of the Disposal Canister for Twelve Fuel Assemblies,' Report Posiva-99-18, Posiva Oy, Helsinki. Finland, 1999
- Bond, A. E., Hoch, A. R., Jones, G. D., Tomczyk, A. J., Wiggin, R., M., Worraker, W. J., 'Assessment of A Spent Fuel Disposal Canister', AEA Technology, Harwell, UK. 1997
- Mayer, E., 'Spent Fuel Encapsulation Plant, Preliminary Design of Dold-process Plant,' TVO/KPA Turva11isuus Ja Tekniikka, Work Report 89-1, Teollisuuden Voima Oy, Helsinki, 1985
- Kwon, Y.J, Kang,S.U., Choi. J.W., Kang,C.H., 'Structural Analysis for the Determination Design Variables of Spent Nuclear Fuel Disposal Canister,'KSME International Journal, Vol.15, No.3, 2001 pp.327-338
-
Sav
$\aa$ s, L., 'Canister for Nuclear Waste Disposal. Preliminary Design of the Steel Cylinder,' Arbetsrapport 93-38, VBB Viak AB, Stockholm, Sweden, 1993 - O'Neil, W.C., Gregg, D.W., Heckman, J.N., Russel. E.W. Stein, W., 'PreclosureAnalysis of Conceptual Waste Package Design for a Nuclear Waste Repository inTuff.' Lawrence Livermore National Laboratory, 1984
- Thunvik, R., Braester, C., 'Heat Propagation from a Radioactive Waste Repository. SKB 91 Reference Canister,' Royal Institute of Technology, Stockholm, Sweden, March, 1991
-
Renstr
$\"o$ m, P., 'Heating of Copper/Steel Canisters by Decay Power of Encapsulated Nuclear Waste-Finite Element Analysis,' Arbetsrapport 93-29, VBB Viak AB, Stockholm, Sweden, 1993 - 권영주, 하준용, 최종원,'가압경수로 고준위폐기물 처분용기의 열응력 해석,' 한국전산구조공학회 논문집, 제15권 제3호, pp.471-480, 2002
- Ahonen, L., 'Chemical Stability of Copper Canisters in Deep Repository,' Report YJ T-94-13, Nuclear Waste Commission of Finnish Power Companies, Helsinki, p.101, 1995
- Anttila, M., 'Criticality Safety Calculations for the Nuclear Waste Disposal Canisters,' Report POSIVA-96-11, Posiva Oy, Helsinki, 1996
- Anttila, M., 'Criticality Safety Calculations of the Nuclear Waste Disposal Canisters for Twelve Spent Fuel Assemblies', Working Report 99-03. Posiva Oy. Helsinki. 1999, p.20
- Auerkari, P., Holmstrom, S., 'Long-term Strength of EB Welds of the Canister forNuclear Fuel Disposal.' Working Report 97-35e, Posiva Oy. Helsinki, p. 21. 1997
- Raiko, H., Salo, J. P., 'The Design Analysis of ACP-Canister for Nuclear WasteDisposal,' Report YJT-92-05, Nuclear Waste Commission of Finnish Power Companies, Helsinki, Finland, 1992
- Salo, J. P., Raiko, H., 'The Copper/ Steel Canister Design for Nuclear Waste Disposal,' TVO/KPA Turva11isuus Ja Tekniikka, Work Report 90-10, Rev. 1., Teollisuuden Voima Oy, Helsinki. Finland, 1990
- Werme, L., 'Design Premises for Canister for Spent Nuclear Fuel,' Technical Report TR-98-08, Swedish Nuclear Fuel and Waste Management Co (SKB), Stockholm, Sweden, ISSN 0284-3757, 1998, p.46
- Borgesson, L., 'Interaction between Rock, Bentonite buffer and Canister. FEM Calculations of Some Mechanical Effects on the Canister in Different Disposal Concepts,' Technical report TR 92-20, Swedish Nuclear fuel and Waste Management Co.(SKB), Stockholm. appendixes, ISSN 0284-3757. 1992, p.83
- Choi. J.W., Choi, Y.S., Kwon, S.K.. Kuh, J.E., Kang, C.H., 'Technology Assessment of the Repository Alternatives to Establish a Reference HLW Disposal Concept,' Journal of the Korean Nuclear Society, Vol.31. 1999, pp.83-100
- Choi. J.W., Ko, W.I., Kang, C.H., 'Reference Spent Fuel and Its Characteriscticsfor a Deep Geological Repository Concept Development,' Journal of the Korean Nuclear Society, Vol.31. No.6, 1999, pp.23-38
- Skrzypek, J. J., 'PLASTICITY and CREEPTheory, Examples, and Problems,' CRC Press, 1993
- Compiled and Edited by Hagrman. D. L., A. R. Reymann, 'Matro-Version II, a Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior,' Idaho National Engineering Laboratory, 1979