References
- 1994, 2001 ASME Boiler and Pressure Vessel Code Section III, Subsection NH, ASME
- 1987, 1993,2002 RCC-MR, Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, AFCEN
- 2003, Assessment Procedure for the High Temrerature Response of Structures, British Energy Generation Ltd
- 1984, Elevated Temperature Structural Design Guide for Class 1 Components of Prototype Fast Breeder Reactor, PNC N241-84-08, PNC
- 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
- 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
- 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
- Koo, G.H. and Lee, JH., Computer Program of SIE ASME-NH Code, KAERVTR-3161/2006, KAERI, 2006