Publications

In situ investigation of the oxidation of Zr–Nb–Cu alloy in high-temperature hydrogenated water
- T. Kim, S. Kim, C. Lee, Y. Mok and J. H. Kim*
- Corrosion Science, Vol 119, Pages 91–101, 2017.05


- J. KIM, B. Hou, C. Park, C. B. Bahn, J. Hoffman, J. Black, A. Bhattacharya, N. Balke, H. Hong, J. H. Kim and S. Hong*
- Scientific Reports, Vol 4.847, 2017.03

Orientation-Dependent Hydration Structures at Yttria-Stabilized Cubic Zirconia Surfaces
- B. Hou, S. Kim, T. Kim, C. Park, C. B. Bahn, S. Hong, S. Lee, S. Y. Kim and J. H. Kim*
- Journal of Physical Chemistry C, Vol 120, Pages 29089-29097, 2016.12

Mechanism of corrosion of 9Cr and 12Cr ferritic/martensitic steels under oxygen-saturated sodium
- S. H. Shin, J. Lee, J. H. Kim and J. H. Kim*
- Corrosion Science, Vol 112, Pages 611-624, 2016.11

Modeling of radiation-induced sink evolution in 6061 aluminum alloy in nuclear reactors
- S. I. Choi, G. G. Lee, J. Kwon and J. H. Kim*
- Physica Status Solidi A - Application and Materials Science, Vol 213, Pages 3000-3006, 2016.11

Microstructural evolution and stress-corrosion-cracking behavior of thermally aged Ni-Cr-Fe alloy
- S. C. Yoo, K. J. Choi, T. Kim, S. H. Kim, J. Y. Kim and J. H. Kim*
- Corrosion Science, Vol 111, Pages 39-51, 2016.10

Effects of thermal aging and stress triaxiality on PWSCC initiation susceptibility of nickel-based Alloy 600
- S. C. Yoo, K. J. Choi, T. Kim and J. H. Kim*
- Journal of Mechanical Science and Engineering, Vol 30, Pages 4403-4406, 2016.10

- K. J. Choi, S. C. Yoo, H. -H. Jin, J. Kwon, M. -J. Choi, S. S. Hwang and J. H. Kim*
- Journal of Nuclear Materials, Vol 476, Pages 243-254, 2016.08

The Hydration Structure at Yttria-Stabilized Cubic Zirconia (110)-Water Interface with Sub-Ångström Resolution
- B. Hou, S. Kim, T. Kim, J. Kim, S. Hong, C. B. Bahn, C. Park* and J. H. Kim*
- Scientific Reports, Vol 6, Article number 27916, 2016.06

Effects of dissolved hydrogen on the crack-initiation and oxidation behavior of nickel-based alloys in high-temperature water
- T. Kim, K. J. Choi, S. C. Yoo and J. H. Kim*
- Corrosion Science, Vol 106, Pages 260-270, 2016.05

Experimental study on a novel liquid metal fin concept preventing boiling critical heat flux for advanced nuclear power reactors
- S. D. Park, J. H. Kim and I. C. Bang*
- Applied Thermal Engineering, Vol 98, Pages 743-755, 2016.04

Fusion boundary precipitation in thermally aged dissimilar metal welds studied by atom probe tomography and nanoindentation
- K. J. Choi, T. Kim, S. C. Yoo, S. Kim, J. H. Lee and J. H. Kim*
- Journal of Nuclear Materials, Vol 471, Pages 8-16, 2016.04

Enhancement of energy performance in betavoltaic cells by optimizing self-absorption of beta particles
- T. Kim, N. H. Lee, H. K. Jung and J. H. Kim*
- International Journal of Energy Research, Vol40, Pages 522-528, 2016.03

Corrosion Behavior of Surface Treated Steel in Liquid Sodium Negative Electrode of Liquid Metal Battery
- J. Lee, S. H. Shin, J. K. Lee, S. Choi and J. H. Kim*
- Journal of Power Sources, Vol 307, Pages 526-537, 2016.03

Modeling of sink-induced irradiation growth of single-crystal and polycrystal zirconiums in nuclear reactors
- S. I. Choi, G. -G. Lee, J. Kwon and J. H. Kim*
- Journal of Nuclear Materials, Vol 468, Pages 56-70, 2016.01

Correlation between carbon activity and carbon content in α-iron in liquid sodium negative electrode of liquid metal battery
- S. H. Shin, J. H. Lee, J. K. Lee and J. H. Kim*
- Journal of Power Sources, Vol 297, Pages 105-112, 2015.11

Phase transformation of oxide film in zirconium alloy in high temperature hydrogenated water
- T. Kim, J. Kim, K. J. Choi, S. C. Yoo, S. Kim and J. H. Kim*
- Corrosion Science, Vol 99, Pages 134-144, 2015.10

Corrosion behavior and microstructural evolution of ASTM A182 Grade 92 steel in liquid sodium at 650C
- S.H. Shin, J. H. Kim and J. H. Kim*
- Corrosion Science, Vol 97, Pages 172-182, 2015.08

Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation
- Y. H. Shin, J. Cho, J. H. Kim, I. S. Hwang and S. Choi*
- Progress in Nuclear Energy, Vol 83, Pages 433-442, 2015.08

Effects of aging temperature on microstructural evolution at dissimilar metal weld interfaces
- K. J. Choi, S. C. Yoo, T. Kim, C. B. Bahn and J. H. Kim*
- Journal of Nuclear Materials, Vol 462, Pages 54-63, 2015.07

Effects of thermal aging on the microstructure of Type-II boundaries in dissimilar metal weld joints
- S. C. Yoo, K. J. Choi, C. B. Bahn, S. H. Kim, J. Y. Kim and J. H. Kim*
- Journal of Nuclear Materials, Vol 459, Pages 5-12, 2015.04

Measurement of Emf in Liquid Sodium Using a Gadolinia-Doped Ceria Solid Electrolyte
- S. H. Shin, J. H. Lee, J. K. Lee, J. Lim, S. Choi, G. Kim and J. H. Kim*
- Journal of The Electrochemical Society, Vol 162, Pages B152-B158, 2015.04

Techniques for intergranular crack formation and assessment in alloy 600 base and alloy 182 weld metals
- T. H. Lee, I. S. Hwang, H. D. Kim and J. H. Kim*
- Nuclear Engineering and Technology, Vol 47, Pages 102-114, 2015.02

In-situ investigation of thermal aging effect on oxide formation in Ni-base alloy/low ally steel dissimilar metal weld interfaces
- J. Kim, S. H. Kim, K. J. Choi, C. B. Bahn, I. S. Hwang and J. H. Kim*
- Corrosion Science, Vol 86, Pages 295-303, 2014.09

Model of liquid gallium corrosion with austenitic stainless steel at a high temperature
- S. H. Shin, S. H. Kim and J. H. Kim*
- Journal of Nuclear Materials, Vol 450, Pages 314-321, 2014.07

In situ Raman spectroscopic analysis of surface oxide films on Ni-base alloy/low alloy steel dissimilar metal weld interfaces in high-temperature water
- J. Kim, K. J. Choi, C. B. Bahn and J. H. Kim*
- Journal of Nuclear Materials, Vol 450, Pages 314-321, 2014.06

Enhancement of seawater corrosion resistance in copper using acetone-derived graphene coating
- J. H. Huh, S. H. Kim, J. H. Chu, S. Y. Kim, J. H. Kim* and S. Y. Kwon*
- Nanoscale, Vol. 6, pp. 4379-4386, 2014.04

Subchannel analysis of a small ultra-long cycle fast reactor core
- S. Han, J. H. Kim and I. C. Bang*
- Nuclear Engineering and Design, v.270, pp.389 – 395, 2014.04

Monolithic graphene oxide sheets with controllable composition
- J. H. Chu, J. Kwak, S. D. Kim, M. J. Lee, J. J. Kim, S. D. Park, J. K. Choi, G. H. Ryu, K. Park, S. Y. Kim, J. H. Kim, Z. Lee, Y. W. Kim and S. Y. Kwon*
- Nature Communications, Vol. 5, 2014.02

Development of wall thinning screening system and its application to a commercial nuclear power plant
- K. H. Ryu, I. S. Hwang and J. H. Kim*
- Nuclear Engineering and Design, Vol. 265, Pages 591-598, 2013.12

An experimental study on natural convection heat transfer of liquid gallium in a rectangular loop
- S. Kang, K. S. Ha, H. T. Kim, J. H. Kim and I. C. Bang*
- International Journal of Heat and Mass Transfer, Vol 66, Pages 192-199, 2013.11

A first-principles study of the diffusion of atomic oxygen in nickel
- H. O. Nam, I. S. Hwang, K. H. Lee* and J. H. Kim*
- Corrosion Science, Vol 75, Pages 248-255, 2013.10

Effects of thermal aging on microstructures of low alloy steel-Ni base alloy dissimilar metal weld interfaces
- K. J. Choi, J. J. Kim, B. H. Lee, C. B. Bahn and J. H. Kim*
- Journal of Nuclear Materials, Vol 441, Pages 493-502, 2013.10

Design of Alumina Forming FeCrAl Steels for Lead or Lead-Bismuth Cooled Fast Reactors
- J. Lim, I. S. Hwang and J. H. Kim*
- Journal of Nuclear Materials, Vol 441(1-3), Pages 650-660, 2013.10

Feasibility study of fuel cladding performance for application in ultra-long cycle fast reactor
- J. A. Jung, S. H. Kim, S. H. Shin, I. C. Bang and J. H. Kim*
- Journal of Nuclear Materials, Vol 440, Pages 596-605, 2013.09

Radiation-induced dislocation and growth behavior of zirconium and zirconium alloys- A review
- S. I. Choi and J. H. Kim*
- Nuclear Engineering and Technology, Vol. 45, Pages 385-392, 2013.06

Feasibility study on molten gallium with suspended nanoparticles for nuclear coolant applications
- S. W. Lee, S. D. Park, S. Kang, S.H. Shin, J. H. Kim* and I. C. Bang
- Nuclear Engineering and Design, Vol 247, Pages 147-159, 2012.06

Nano-structural and Nano-chemical analysis of Ni-base alloy/low alloy steel dissimilar metal weld Interfaces
- K. J. Choi, S. H. Shin, J. J. Kim, J. A. Jung and J. H. Kim*
- Nuclear Engineering and Technology, Vol 44, Pages 491-500, 2012.06

Three dimensional atom probe study of Ni-base alloy/low alloy steel dissimilar metal weld interfaces
- K. J. Choi, S. H. Shin, J. J. Kim, J. A. Jung and J. H. Kim*
- Nuclear Engineering and Technology, Vol 44, Pages 673-682, 2012.04

First-principles study of interstitial diffusion of oxygen in nickel chromium binary alloy
- J. J. Kim, S. H. Shin, J. A. Jung, K. J. Choi and J. H. Kim*
- Applied Physics Letters, Vol 100, 2012.03

A study on corrosion behavior of austenitic stainless steel in liquid metals at high temperature
- S. H. Shin, J. J. Kim, J. A. Jung, K. J. Choi, I. C. Bang and J. H. Kim*
- Journal of Nuclear Materials, Vol 422, Pages 92-102, 2012.03

Investigation of viscosity and thermal conductivity of SiC nanofluids for heat transfer applications
- S. W. Lee, S. D. Park, S. Kang, I. C. Bang* and J. H. Kim
- International Journal of Heat and Mass Transfer, Vol 54, Pages 433-438, 2011.01

Viscosity measurements on colloidal dispersions (nanofluids) for heat transfer applications
- Venerus D.C., Buongiorno J., Christianson R., Townsend J., Bang I.C., Chen G., Chung S.J., Chyu M., Chen H., Ding Y., Dubois F., Dzido G., Funfschilling D., Galand Q., Gao J., Hong H., Horton M., Hu L., Iorio C.S., Jarzebski A.B., Jiang Y., Kabelac S., Kedzierski M.A., Kim C., Kim J.-H., Kim S., McKrell T., Ni R., Philip J., Prabhat N., Song P., Van Vaerenbergh S., Wen D., Witharana S., Zhao X.-Z., Zhou S.-Q.
- Applied Rheology, Vol 20, 2010.12

A study of early corrosion behaviors of FeCrAl alloys in liquid lead-bismuth eutectic environments
- J. Lim, H. O. Nam, I. S. Hwang and J. H. Kim*
- Journal of Nuclear Materials, Vol 422, Pages 92-102, 2010.12

Effects of nanofluids containing graphene/graphene-oxide nanosheets on critical heat flux
- S. D. Park, S. W. Lee, S. Kang, I. C. Bang*, J. H. Kim, H. S. Shin, D. W. Lee, W. L. Dong
- Applied Physics Letters, Vol 97, 2010.07

Thermal-fluid characterizations of zno and sic nanofluids for advanced nuclear power plants
- I. C. Bang*, J. H. Kim
- Nuclear Technology, Vol 170, Pages 16-27, 2010.04

Online monitoring method using Equipotential Switching Direct Current potential drop for piping wall loss by flow accelerated corrosion
- K. H. Ryu*, T. H. Lee, J. H. Kim, I. S. Hwang, N. Y. Lee, J. H. Kim, J. H. Park, C. H. Sohn
- Nuclear Engineering and Design, Vol 240, Pages 468-472, 2010.03

- J. K. Benz, J. H. Kim and R. G. Ballinger
- Journal of Engineering for Gas Turbines and Power, Vol 132, 2010.01

A benchmark study on the thermal conductivity of nanofluids
- J. Buongiorno*, D. C. Venerus, N. Prabhat, T. McKrell, J. Townsend, R. Christianson, Y. V. Tolmachev, P. Keblinski, L. W. Hu, J. L. Alvarado, I. C. Bang, S. W. Bishnoi, M. Bonetti, F. Botz, A. Cecere, Y. Chang, G. Chen, H. Chen, S. J. Chung, M. K. Chyu, S. K. Das, R. D. Paola, Y. Ding, F. Dubois, G. Dzido, J. Eapen, W. Escher, D. Funfschilling, Q. Galand, J. Gao, P. E. Gharagozloo, K. E. Goodson, J. G. Gutierrez, H. Hong, M. Horton, K. S. Hwang, C. S. Iorio, S. P. Jang, A. B. Jarzebski, Y. Jiang, L. Jin, S. Kabelac, A. Kamath, M. A. Kedzierski, L. G. Kieng, C. Kim, J. H. Kim, S. Kim, S. H. Lee, K. C. Leong, I. Manna, B. Michel, R. Ni, H. E. Patel, J. Philip, D. Poulikakos, C. Reynaud, R. Savino, P. K. Singh, P. Song, T. Sundararajan, E. Timofeeva, T. Tritcak, A. N. Turanov, S. V. Vaerenbergh, D. Wen, S. Witharana, C. Yang, W. H. Yeh, X. Z. Zha
- Journal of Applied Physics, Vol 106, 2009.11

Screening method for piping wall loss by flow accelerated corrosion
- K. H. Ryu*, I. S. Hwang, N. Y. Lee, Y. J. Oh, J. H. Kim, J. H. Park, C. H. Sohn
- Nuclear Engineering and Design, Vol 236, Pages 3263-3268, 2008.12

Electroless nickel-plating for the PWSCC mitigation of nickel-base alloys in nuclear power plants
- J. H. Kim* and I. S. Hwang
- Nuclear Engineering and Design, Vol 238, Pages 2529-2535, 2008.12

Stress corrosion cracking crack growth behavior of type 316L stainless steel weld metals in boiling water reactor environments
- J. H. Kim* and R. G. Ballinger
- Corrosion, Vol 64, Pages 645-656, 2008.08

Verification of the Viability of Equipotential Switching Direct Current Potential Drop Method for Piping Wall Loss Monitoring with Signal Sensitivity Analysis
- K. H. Ryu*, I. S. Hwang and J. H. Kim
- Journal of the Korean Society for Nondestructive Testing, Vol. 28, Pages 191-198, 2008.01

Superconducting magnet and conductor research activities in the US fusion program
- P. Michael*, J. H. Schultz, T. Antaya, R. G. Ballinger, L. Chiesa, J. Feng, C-Y. Gung, D. Harris, J.H. Kim, P. Lee, N. Martovetsky, J. V. Minervini, A. Radovinsky, M. Salvetti, M. Takayasu, P. Titus
- Fusion Engineering and Design, Vol. 81, Pages 2381-2388, 2006.11

Development of In situ Raman Spectroscopic System of Surface Oxide Films of Metals and Alloys in High Temperature Water Conditions
- J. H. Kim* and I. S. Hwang
- Nuclear Engineering and Design, Vol. 235, Pages 1029-1040, 2005.04

Dynamic Loading Fracture Tests of Ferritic Steel Using the Direct Current Potential Drop Method
- Y. J. Oh, J.H. Kim*, I. S. Hwang
- Journal of Testing and Evaluation, Vol. 30, Pages 221-227, 2002.05

Fracture behavior of heat affected zone in low alloy steels
- J. H. Kim*, Y. J. Oh, I. S. Hwang, D. J. Kim, J. T. Kim
- Journal of Nuclear Materials, Vol. 299, Pages 132-139, 2001.11

Crack Shape Evolution of Surface Flaws under Fatigue Loading of Austenitic Pipes
- J. H. Kim and I. S. Hwang*
- Nuclear Engineering and Design, Vol. 174, Pages 17-24, 1997.10






Mechanical properties of JK2LB at 4K
- J. Feng, J.H. Kim, R.G. Ballinger, J.V. Minervini*
- Advances in Cryogenic Engineering, Vol. 52, Pages 192-199, 2006.03

Development of an on-line ultrasonic system to monitor flow-accelerated corrosion of piping in nuclear power plants
- N. Y. Lee, C. B. Bahn, S. G. Lee, J. H. Kim, I. S. Hwang, J. H. Lee, J. T. Kim, V. Luk*
- Key Engineering Materials, Vol. 270-273, Pages 2232-2238, 2004.08

An Intraspecimen Method for the Statistical Characterization of Stress Corrosion Crack Initiation Behavior
- S. G. Lee, S. U. Kwon, J. H. Kim and I. S. Hwang*
- Corrosion, Vol. 57, Pages 787-793, 2001.09

New Failure Prediction Model for a Ni-Fe Superalloy Sheath of Superconducting Fusion Magnets
- J. H. Kim, I. S. Hwang and R. L. Tobler*
- Advances in Cryogenic Engineering (Materials), Vol. 44, Pages 33-40, 1998.

Fracture mechanics behavior of a Ni-Fe superalloy sheath for superconducting fusion magnets. Part 2. magnet life analysis model
- J. H. Kim, I. S. Hwang and R.L. Tobler*
- Fusion Engineering and Design, Vol. 36, Pages 269-279, 1997.05
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