참고문헌

1. 1994, 2001 ASME Boiler and Pressure Vessel Code Section III, Subsection NH, ASME
2. 1987, 1993,2002 RCC-MR, Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, AFCEN
3. 2003, Assessment Procedure for the High Temrerature Response of Structures, British Energy Generation Ltd
4. 1984, Elevated Temperature Structural Design Guide for Class 1 Components of Prototype Fast Breeder Reactor, PNC N241-84-08, PNC
5. Shah, V.N., Majumdar, S., and Natesan, K., 2003, Review and Assessment of Codes and Procedures for HTGR Components, NUREG/CR-6816, ANL- 02/36, Argonne National Laboratory
6. Koo, G.H, Yoo, B., 2000, 'Elevated Temperature Design of KALIMER Reactor Internals Accounting for Creep and Stress Rupture Effects', Journal of the Korean Nuclear Society, Vol.32, No.6, pp.566-594
7. Koo, G.H., Yoo. B., 2001, 'Evaluation of Creep Fatigue Damage of KALIMER Reactor Internals Using the Elastic Analysis Method in RCC-MR', Journal of the Korean Nuclear Society, Vol.33, No.6, pp.566-594
8. Koo, G.H. and Lee, JH., Computer Program of SIE ASME-NH Code, KAERVTR-3161/2006, KAERI, 2006