참고문헌
- Chang, M. H. et al., 'SMART-An Advanced Small Integral PWR for Nuclear Desalination and Power Generation,' Proc. of Global 99, Jackson Hole, USA (1999)
- Chang, M. H. et al., 'Basic Design Report of SMART,' KAERI/TR-2142/2002 (2002)
- Kim, S. H. et al., 'Design Verification Program of SMART,' Proc. of GENES4/ANP2003, Kyoto, Japan, September 15-19 (2003)
- Choi, K. Y. et al., 'Dynamic System Characteristics Report of the High Temperature/High Pressure Thermal Hydraulic Test Facility (VISTA) for Power Variation,' KAERI/TR-2605/2003 (2003a)
- Choi, K. Y. et al., 'Characteristics and Performance Analysis of the Major Thermal Hydraulic Components in the High Temperature/High Pressure Thermal Hydraulic Test Facility (VISTA),' KAERI/TR-2606/2003 (2003b)
- Park, H. S. et al., 'Experiments for Heat Transfer Characteristics and Natural Circulation Performance of PRHRS of the High Temperature/High Pressure Thermal Hydraulic Test Facility (VISTA),' KAERI/TR-2656/2004 (2004a)
- Park, H. S. et al., 'Analysis Report of the Thermal Hydraulic Characteristics Report of the High Temperature/High Pressure Thermal Hydraulic Test Facility (VISTA) in Steady State Conditions,' KAERI/TR-2657/2004 (2004b)
- Choi, K. Y. et al., 'VISTA : Thermal-Hydraulic Integral Test Facility for the SMART Reactor,' The 10th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9 (2003c)
- Choi, K. Y. et al., 'Thermal-Hydraulic Characteristics during Transient Operation of the Integral Type Reactor,' The 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-4), Sapporo, Japan, November 28-December 1 (2004)
- Park, H. S. et al., 'Experiments on the Heat Transfer and Natural Circulation Characteristics of the Passive Residual Heat Removal System for the Advanced Integral Type Reactor,' Proc. of Int. Congress on Advances in Nuclear Power Plants (ICAPP '04), Pittsburgh, PA, USA, June 13-17 (2004c)
- Park, H. S. et al., 'Experimental and Analytical Studies on the Passive Residual Heat Removal System for the Advanced Integral Type Reactor,' The 6th Int. Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6), Nara, Japan, October 4-8 (2004d)
- Chung Y. J. et al., 'Study on the Thermal Hydraulic Characteristics of a Residual Heat Removal System for the SMART Plant,' The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9 (2003)