References
- Korea Atomic Industrial Forum, 2008, Nuclear Energy Annual Report
- Chang, M. H., et al., 1999, 'SMART-an Advanced Small Integral PWR for Nuclear Desalination and Power Generation.,' Proc. Of Global '99-International Conference on Future Nuclear System, Jackson Hole, Wyoming, U.S.A., Aug. 29-Sept. 3
- Song, C. H., et al., 2007, 'Thermal-Hydraulic Tests and Analyses for the APR1400's Development and Licensing,' Nuclear Eng. & Technol., 39, pp. 299~312 https://doi.org/10.5516/NET.2007.39.4.299
- Chung, Y. J., et al., 2009, 'Validation of the TASS/SMR and MARS Codes for a Natural Circulation Experiment at the VISTA Facility,' Nuclear Technology, 165, pp. 32~42 https://doi.org/10.13182/NT09-A4060
- Tim Abram, et al., 2008, 'Generation-IV Nuclear Power : A Review of the State of the Science,' Energy Policy, 36, pp. 4323~4330 https://doi.org/10.1016/j.enpol.2008.09.059
- Eoh, J. H., et al., 2008, 'Feasibility Study on the Design Options to Prevent the PDRC Loop Sodium Freezing in KALIMER-600,' Trans. KNS Spring Mtg., KyeongJu, Korea, May 28-30
- Lee, T. H., et al, 2009, 'Development of Passive Decay Heat Removal System PDRC,' The 24th KAIF/KNS Annual Conf., April 8-10
- Kim, Y. G., et al., 2007, 'Recent Development of the Inter-Assembly Flow Analysis Tools for SFR Core Thermal Hydraulics,' Trans. KNS Spring Mtg., Jeju, Korea, May 10-11
- Chang, J., et al., 2007, 'A Study of Nuclear Hydrogen Production Demonstration Plant,' Nuclear Eng. & Technol., 39, pp. 111-122 https://doi.org/10.5516/NET.2007.39.2.111
- Burchell, T.D., et al., 1994, 'The Effect of Neutron Irradiation on the Structure and Properties of Carbon- Carbon Composite Materials,' J. Nuclear Materials, 191- 194, pp.295-299 https://doi.org/10.1016/S0022-3115(09)80053-6
- Lee, W.J., et al., 2003, 'Development of MARS-GCR for Gas-Cooled Reactor Analysis-Incorporation of Gas Properties,' The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Seoul, Korea, October 5-9
- Kim, H. R., et al., 2008, 'Heat Transfer to Supercritical Pressure Carbon Dioxide Flowing Upward through Tubes and a Narrow Annulus Passage,' Nuclear Energy, 50, pp. 518-525 https://doi.org/10.1016/j.pnucene.2007.11.065
- Lee, D. W., et al., 2006, 'Current Status and R & D Plan on ITER TBMs of Korea, 'Journal of the Korean Physical Society, 49, pp. S340-S344
- Park, H. S., 2008, 'Characterization Tests on the SIT Injection Capability of the ATLAS for an APR1400 Simulation,' J. Energy Engineering, 17, pp. 67-76
- Kwon, T. S., et al., 2009, 'Advanced DVI for ECC Direct Bypass Mitigation,' Nuclear Eng. & Design., 239, pp. 1095-1102 https://doi.org/10.1016/j.nucengdes.2009.02.002
- Yun, B. J., 2008, 'Downcomer Boiling Phenomena During the Reflood Phase of a Large-Break LOCA for the APR1400,' Nuclear Eng. & Design., 238, pp. 2064-2074 https://doi.org/10.1016/j.nucengdes.2007.10.024
- Chung, M. K., 2004, 'Experimental Study on Design Verification of New Concept for Integral Reactor Safety System,' KSME, pp. 2053-2058
- Moon, S. K., et al., 2005, 'An Experimental Study on the Critical Heat Flux for Low Flow of Water in a Non- Uniformly Heated Vertical Rod Bundle over a Wide Range of Pressure Conditions,' Nuclear Eng. & Design., 235, pp. 2295-2309 https://doi.org/10.1016/j.nucengdes.2005.04.004
- Chang, S. K., et al., 2008, 'Phenomenological Investigations on the Turbulent Flow Structures in a Rod Bundle Array with Mixing Devices,' Nuclear Eng. & Design., 238, pp. 600-209 https://doi.org/10.1016/j.nucengdes.2007.02.037
- Euh, D. J., et al., 2001, 'Development of the Five- Sensor Conductivity Probe Method for the Measurement of the Interfacial Area Concentration," Nuclear Eng. & Design., 205, pp. 35-51 https://doi.org/10.1016/S0029-5493(00)00376-9
- Kim, S. J., et al., 2007, 'Development of Algorithm to Measure Temperatures of Liquid/Gas Phases Using Micro-Thermocouple and Experiment with Optical Chopper,' J. Mechanical Science and Technology, 21, pp. 184-195 https://doi.org/10.1007/BF03161724
- Kim, S. J., et al., 2004, 'Development of Two- Directional Image Processing Algorithm to Measure Bubble Size and Volume in Two-phase Flow,' Proceedings of the Korean Nuclear Society Autumn Meeting, Yongpyong, October
- Lee, K. H., et al., 2008, 'An Integral Loop Test and MARS Code Analysis for a DVI Line Break LOCA in the APR1400,' Nuclear Eng. & Design., 238, pp. 3336-3347 https://doi.org/10.1016/j.nucengdes.2008.06.018
- Lee, Y. G., et al., 2008, 'Condensation Heat Transfer in the Presence of Noncondensable Gas at High Pressure,' HEAT 2008, Bialystok, Poland, June 30-July 3
- Yoon, S. J., et al., 2007, 'Experimental Evaluation of the Bypass Flow in the VHTR Core,' SMiRT-19, Toronto, Canada, Aug. 12-17
- Lee, K. Y., et al., 2008, 'Experimental and Empirical Study of Steam Condensation Heat Transfer with a Noncondensable Gas in a Small-Diameter Vertical Tube,' Nuclear Eng. & Design., 238, pp. 207-216 https://doi.org/10.1016/j.nucengdes.2007.07.001
- Lee, Y. Y., 2001, 'An Experimental Study on the Direct Contact Condensation in IRWST,' Ms. Thesis, Pohang University of Science and Technology, Korea
- Kim, H. D., et al., 2007, 'Experimental Studies on CHF Characteristics of Nano-Fluids at Pool Boiling,' Int. J. Multiphase Flow, 33, pp. 691-706 https://doi.org/10.1016/j.ijmultiphaseflow.2007.02.007
-
Shin, B. S., et al., 2009, 'CHF Experiment and CFD Analysis in a
$2\times3$ Rod Bundle with Mixing Vane,' Nuclear Eng. & Design., 239, pp. 899-912 https://doi.org/10.1016/j.nucengdes.2009.01.011 - Park, J. H., 2008, 'A Study on the Effect of the Twisted Tape on CHF Enhancement in a Circular Tube with R-134a,' Ms. Thesis, Korea Advanced Institute of Science and Technology, Korea
- Kim, I. H., et al., 2008, 'Thermal-Hydraulic Performance of the Printed Circuit Heat Exchanger in a Helium Test Loop,' Proc. of Nthas 6 of proceedings, N6P1081, Okinawa, Japan
- Yoon, H. J., et al., 2009, 'Experimental Studies of an Optimal Operating Condition for the Bunsen Process in the I-S Thermochemical Cycle,' Proc. of ICAPP 09, Paper 9417, Tokyo, Japan, May 10-14
-
Shin Yoo, 2008, 'Experimental Analysis of Heat Transfer Characteristics for
$TiO_2$ Nanofluid,” Ms. Thesis, Handong Global University, Korea. - Lee, S. Y., et al., 2008, 'Status and Perspective of the Hydraulic Solver Development for SPACE Code,' KNS, Gyeongju, Korea, May 29-30
- Lim, H. S. and No, H. C., 2006, 'GAMMA Multidimensional Multicomponent Mixture Analysis to Predict Air Ingress Phenomena in an HTGR,' Nuclear Sci. & Eng., 152, No. 1, pp. 1-11 https://doi.org/10.13182/NSE06-A2557
- Hwang, J. S., et al., 2007, 'Computational Analysis of Battery Optimized Reactor Integral System,' ICENES, TURKdYE, dstanbul, June 3-8