참고문헌
- Y. I. Kim, S. G. Hong, and D. H. Hahn, “SFR Deployment Strategy for the Re-Use of Spent Fuel in Korea,” Nuclear Engineering and Technology, Vol. 40, No. 6, pp. 517-526 (2008) https://doi.org/10.5516/NET.2008.40.6.517
- D. Hahn, et al, “KALIMER-600 Conceptual Design Report,” KAERI/TR-3381/2007, Korea Atomic Energy Research Institute, Daejeon, Korea (2007)
- Hyung-Kook Joo, Jin-Wook Jang, Jae-Woon Yoo, and Yeong-Il Kim, "SFR Breakeven Core Designs with Various Rated Powers," Transactions of the Korean Nuclear Society Spring Meeting, Gyeongju, Korea (2008)
- Hoon Song, Sang-Ji Kim, Hae-Yong Jeong, Yeong-Il Kim, “Design Studies on a Large-Scale Sodium-Cooled TRU Burner,” Proceedings of 2008 Internal Congress on Advances in Nuclear Power Plants, pp. 450-457 (2008)
- Hyung-Kook Joo, Ki-Bog Lee, Jae-Woon Yoo, and Yeong- Il Kim, “Conceptual Core Designs for a 1200MWe Sodium Cooled Fast Reactor,” Proceedings of 2008 Internal Congress on Advances in Nuclear Power Plants, pp. 414-420 (2008)
- Ki-Bog Lee , Hyung-Kook Joo, Jae-Woon Yoo, Yeong-il Kim, “Sensitivity study of dimensional variables for a 1,200 MWe sodium cooled fast reactor core design,” Internal Conference on the Physics of Reactors (2008)
- Jaewoon Yoo, et al., “Impact of Up-to-date Evaluated Nuclear Data Files on the Monte-Carlo Analysis Results of Metallic Fueled BFS Critical Assemblies,” Proceedings of 2009 Internal Congress on Advances in Nuclear Power Plants, paper no. 9400, Tokyo, Japan (2009)
- Jaewoon Yoo, et al., "Analysis of Metallic Uranium Fueled BFS Critical Assemblies with Different Evaluated Nuclear Data Files," Proceedings of PHYSOR2008, paper no. 426, Interlaken, Switzerland (2008)
- Jaewoon Yoo, et. al., “Analysis of a Metallic Plutonium Fueled BFS-55-1 Critical Assembly with Different Evaluated Nuclear Data Files,” Transactions of the Korean Nuclear Society Autumn meeting, Pyeongchang, Korea (2008)
- Seong-O Kim, J.J. Sienicki, Supercritical Carbon Dioxide Brayton Cycle Energy Conversion, International Nuclear Energy Research Initiative (INERI) Technical Report (2005)
- Seung-Hwan Seong, Tae-Ho Lee, Hae-Yong Jeong, Seong-O Kim, “Development of a Preliminary Model for Analyzing Performance of PHTS and IHTS loop in a SFR,” Transactions of the Korean Nuclear Society Autumn Meeting, PyeongChang, Korea (2008)
- ASME B&PV Code, Section XI, Division 3, “Rules for In-service Inspection of Nuclear Power Plant Component,” (1992)
- Y.S. Joo et al., “Feasibility study on ultrasonic waveguide sensor for under-sodium visualization of sodium fast reactor,” KAERI/TR-3540/2008, Korea Atomic Energy Research Institute, Daejeon, Korea (2008)
- Ha, K. S., “Development of MARS-LMR and Steady-state Calculation for KALIMER-600,” Technical Report No. KAERI/TR-3418/2007, Korea Atomic Energy Research Institute, Daejeon, Korea (2007)
- Young, D. A., “A Soft-sphere Model for Liquid Metal,” Technical Report No. UCRL-52352 (1977)
- Cheng, S. K., and Todreas, N. E., “Hydrodynamic models and Correlations for Bare Rod and Wire-wrapped Hexagonal Rod Bundles - Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters,” Nucl. Eng. Des., 92, pp. 227-251 (1986) https://doi.org/10.1016/0029-5493(86)90249-9
- Kazimi, M. S., and Carelli, M. D., “Heat Transfer Correlation for Analysis of CRBRP Assemblies,” Westinghouse Report, CRBRP-ARD-0034 (cited from Ref. 7) (1976)
- Aoki, S., “Current Liquid-metal Heat Transfer Research in Japan,” Prog. Heat Mass Transfer, 7, pp. 569-573 (1973)
- Graber, H., and Rieger, M., “Experimental Study of Heat Transfer to Liquid Metals flowing in-line through Tube Bundles,” Prog. Heat Mass Transfer, 7, pp. 151-166 (1973)
- D. Mohr, L.K. Chang, E.E. Feldman, P.R. Betten, and H.P. Planchon, “Loss-of-Primary-Flow-without-Scram Tests: Pretest Predictions and Preliminary Results,” N.E.D. Vol. 101, pp. 45-56 (1987) https://doi.org/10.1016/0029-5493(87)90149-X
- T.J. Kim, J.Y. Jeong, and S. Hur, “Performance Test for developing the Acoustic Leak Detection System of the LMR Steam Generator”, Transactions of the Korean Nuclear Society Autumn Meeting, Busan, Korea (2005)
피인용 문헌
- Decomposition analysis of the sodium void reactivity of the Korean sodium-cooled fast reactor vol.79, pp.5, 2014, https://doi.org/10.3139/124.110431
- VALIDATION OF A DESIGN CODE FOR SODIUM-TO-SODIUM HEAT EXCHANGERS BY UTILIZING COMPUTATIONAL FLUID DYNAMICS vol.21, pp.1, 2016, https://doi.org/10.6112/kscfe.2016.21.1.019
- Design and preliminary test of an annular linear induction electromagnetic pump for a sodium-cooled fast reactor thermal hydraulic experiment vol.54, pp.12, 2017, https://doi.org/10.1080/00223131.2017.1365020