| Influence of contact shape and supporting condition on tube fretting wear HK Kim, YH Lee Wear 255 (7-12), 1183-1197, 2003 | 68 | 2003 |
| Fretting wear of laterally supported tube HK Kim, SJ Kim, KH Yoon, HS Kang, KN Song Wear 250 (1-12), 535-543, 2001 | 66 | 2001 |
| A comparative study on the fretting wear of steam generator tubes in korean power plants YH Lee, HK Kim, HD Kim, CY Park, IS Kim Wear 255 (7-12), 1198-1208, 2003 | 61 | 2003 |
| Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition YH Lee, HK Kim Wear 301 (1-2), 569-574, 2013 | 57 | 2013 |
| Approximation of contact stress for a compressed and laterally one side restrained O-ring HK Kim, SH Park, HG Lee, DR Kim, YH Lee Engineering Failure Analysis 14 (8), 1680-1692, 2007 | 57 | 2007 |
| Effect of spring shapes on the variation of loading conditions and the wear behaviour of the nuclear fuel rod during fretting wear tests YH Lee, HK Kim Wear 263 (1-6), 451-457, 2007 | 51 | 2007 |
| Mechanical and experimental investigation on nuclear fuel fretting HK Kim, YH Lee, SP Heo Tribology international 39 (10), 1305-1319, 2006 | 51 | 2006 |
| Verification test and model updating for a nuclear fuel rod with its supporting structure HS Kang, KN Song, HK Kim, KH Yoon, YH Jung Nuclear Engineering and Technology 33 (1), 73-82, 2001 | 49 | 2001 |
| On the geometry of the fuel rod supports concerning a fretting wear failure HK Kim, YH Lee, KH Lee Nuclear Engineering and Design 238 (12), 3321-3330, 2008 | 48 | 2008 |
| Control rod drop analysis by finite element method using fluid–structure interaction for a pressurized water reactor power plant KH Yoon, JY Kim, KH Lee, YH Lee, HK Kim Nuclear Engineering and Design 239 (10), 1857-1861, 2009 | 41 | 2009 |
| Axial-flow-induced vibration for a rod supported by translational springs at both ends HS Kang, KN Song, HK Kim, KH Yoon Nuclear Engineering and Design 220 (1), 83-90, 2003 | 36 | 2003 |
| High burnup fuel technology in Korea KW Song, YH Jeong, KS Kim, JG Bang, TH Chun, HK Kim, KN Song Nuclear Engineering and Technology 40 (1), 21, 2008 | 34 | 2008 |
| Effect of impact frequency on the wear behavior of spring-supported tubes in room and high temperature distilled water YH Lee, HK Kim, YH Jung Wear 259 (1-6), 329-336, 2005 | 30 | 2005 |
| Spacer grid for nuclear reactor fuel assemblies with grid springs maintaining conformal contact with fuel rods and enlarged elastic range KH Yoon, HS Kang, HK Kim, KN Song, YH Jung, TH Chun, DS Oh, WK In, ... US Patent 6,707,872, 2004 | 29 | 2004 |
| Evaluation of O-ring stresses subjected to vertical and one side lateral pressure by theoretical approximation comparing with photoelastic experimental results HK Kim, JH Nam, JS Hawong, YH Lee Engineering Failure Analysis 16 (6), 1876-1882, 2009 | 27 | 2009 |
| Spacer grid with hybrid flow-mixing device for nuclear fuel assembly T Chun, D Oh, W In, K Song, H Kim, H Kang, K Yoon, Y Jung US Patent 6,845,138, 2005 | 27 | 2005 |
| Mechanical analysis of fuel fretting problem HK Kim Nuclear engineering and design 192 (1), 81-93, 1999 | 25 | 1999 |
| Nuclear fuel spacer grid with dipper vanes HS Kang, KH Yoon, HK Kim, KN Song, YH Jung, TH Chun, DS Oh, WK In US Patent 6,421,407, 2002 | 24 | 2002 |
| Spacer grid with H-spring for fuel rods for use in nuclear reactor fuel assemblies KH Yoon, HS Kang, HK Kim, KN Song, YH Jung, TH Chun, DS Oh, WK In US Patent 6,167,105, 2000 | 24 | 2000 |
| Model description of TASS/SMR code YD Hwang, SH Yang, SH Kim, SW Lee, HK Kim, HY Yoon, GH Lee, ... | 23 | 2005 |
