1. Kawanishi, K., “Experimental Study on PORV Break LOCA in PWR Plants,”Journal of Nuclear Science and Technology,27, No.2, pp.133–148, (1990).
2. Matsumoto, T., “Multichannel Thermal Hydraulic Model for LOCA Analysis of Heterogeneous BWR Core,”Journal of Nuclear Science and Technology,27, No.8, pp.718–730, (1990).
3. Miller, J.S., “Using PSA Methods at an Operating Nuclear Utility,” Proceedings of the American Power Conference,53, No.2 pp.826–830, (1991).
4. Alammar, Mansur A., “Severe Accident Analysis of TMI-1 LOCA Scenario Using MELCOR 1.8.2,” Power Plant Transients 1994 American Society of Mechanical Engineers, Fluids Engineering Division, ASME, New York, USA,204, pp.53–63, (1994).
5. D’Auria F. and Galassi G.M., “Assessment of Scaling Principles for the Simulation of Small Break LOCA Experiments in PWRs,”Nuclear Engineering and Design,102, pp.129–142, (1987).