Evaluation of Creep-Fatigue Damage of KALIMAR Reactor Internals Using the Elastic Analysis Methods in RCC-MR

Journal of the Korean Nuclear Society, Vol. 33, Number 5, pp.566-584, December, 2001 Gyeong-Hoi Koo and Bong Yoo In this paper, the progressive deformation and the creep-fatigue damage for the conceptually designed reactor internals of KALIMAR (Korean Advanced LIquid MEtal Reactor) are carried out by using the elastic analysis method in the RCC-MR code for normal operating conditions including the thermal load, seismic load (OBE) and dead weight. The maximum operating temperature of this reactor is 530C and the total service lifetime is 30 years.