Thermal-Hydraulic Research Review and Cooperation Outcome for Light Water Reactor Fuel |
In, Wang Kee
(Dept. of LWR Fuel Technology Development, Korea Atomic Energy Research Institute)
Shin, Chang Hwan (Dept. of LWR Fuel Technology Development, Korea Atomic Energy Research Institute) Lee, Chi Young (Dept. of Fire Protection Engineering, Pukyong Nat'l Univ.) Lee, Chan (Dept. of LWR Fuel Technology Development, Korea Atomic Energy Research Institute) Chun, Tae Hyun (Dept. of LWR Fuel Technology Development, Korea Atomic Energy Research Institute) Oh, Dong Seok (Dept. of LWR Fuel Technology Development, Korea Atomic Energy Research Institute) |
1 | Shin, C. H., Chun, T. H., Oh, D. S. and In, W. K., 2012, "Evaluation of Loss Coefficient for an End Plug with Side Holes in Dual-cooled Annular Nuclear Fuel," J. of Mechanical Science and Technology, Vol. 26, No. 10, pp. 1-6. DOI |
2 | Lee, C. Y., Shin, C. H. and In, W. K., 2012, "Pressure Drop in Dual-cooled Annular and Cylindrical Solid Fuel Assemblies for Pressurized Water Reactor," Nuclear Engineering and Design, Vol. 50, pp. 287-293. |
3 | In, W. K., Hwang, Shin, C. H., Kwack, Y. K. and Lee, C. Y., 2015, " Measurement and CFD Calculation of Spacer Loss Coefficient for a Tight-Lattice Fuel Bundle," Nuclear Engineering and Design, Vol. 284, pp. 153-161. DOI |
4 | Lee, C. Y., Shin, C. H. and In, W. K., 2013, "Effect of Gap Width on Turbulent Mixing of Parallel Flow in a Square Channel with a Cylindrical Rod," Experimental Thermal and Fluid Science, Vol. 47, pp. 98-107. DOI |
5 | In, W. K., Shin, C. H. and Lee, C. Y., 2014, "Experimental Observation of Forced Flow Mixing in a Tight-Lattice Rod Bundle," American Nuclear Soc. Annual Meeting, June 16, Reno NV, USA. |
6 | Lee, C. Y., Shin, C. H. and In, W. K., 2015, "Convective Heat Transfer Experiment of Rod Bundle Flow with Twist-vane Spacer Grid," Nuclear Engineering and Design, Vol. 295, pp. 173-181. DOI |
7 | Lee, C. and In, W. K., 2014, "Prediction of Water Droplet Evaporation in Zircaloy Surface," J. of Nuclear Science and Technology, Vol. 51, No. 4, pp. 348-356. |
8 | Lee, C., Chun, T. H. and In, W. K., 2014, "Effect of Change in Surface Condition induced by Oxidation on Transient Pool Boiling Heat Transfer of Vertical Stainless Steel and Copper Rodlets," Int. J. Heat and Mass Transfer, Vol. 79, pp. 397-407. DOI |
9 | In, W. K., Hwang, D. H. and Jeong, J. J., 2013, " A Subchannel and CFD Analysis of Void Distribution for the BWR Fuel Bundle Test Benchmark," Nuclear Engineering and Design, Vol. 258, pp. 211-225. DOI |
10 | In, W. K., Kwack, Y. K., Kook, D. H. and Koo, Y. H., 2014, "CFD Analysis of Fluid Flow and Heat Transfer in Spent Fuel for a Dry Storage," NTHAS9: The Korean-Japan Symposium on Nuclear Thermal Hydraulics and Safety, November 16-19, Buyeo, Korea. |