Publications | UNIMAT

Microstructure response and sodium corrosion behavior of ferritic-martensitic steel after proton irradiation

– J. Lee, T. Kim, T. Kim, J. H. Kim*

– Nuclear Engineering and Technology, Volume 56, Issue 12, Pages 5028-5036 (2024)

Effects of Metal Ion Concentration on Deposition Chemistry of Corrosion Related Unidentified Deposits in PWR Fuel Cladding

– Y. Lee, J. Ham, S. C. Yoo, I. Song, J. H. Kim*

– Corrosion Science, Volume 236, 112268 (2024)

Design and construction of fluid-to-fluid scaled-down small modular reactor platform: As a testbed for the nuclear-based hydrogen production

– J. Y. Kim, S. C. Yoo, J. H. Seo, J. H. Kim, I. C. Bang*

– Nuclear Engineering and Technology, Volume 56, Issue 3, Pages 1037-1051, (2024)

Development of Fe–Cr–Si deposited layer manufactured by laser directed energy deposition process

– G. Kim, H. Nam, T. Hwang, S. Kim, Ji Hyun Kim, S. W. Song*

– Journal of Materials Research and Technology, Volume 28, Pages 1611-1619, (2024)

The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation

– J. Y. Kim, Y. Lee, J. H. Kim, I. C. Bang*

– Nuclear Engineering and Technology, Volume 55, Issue 9, Pages 3164-3182, (2023)

Robust 2D layered MXene matrix–boron carbide hybrid films for neutron radiation shielding

– J. H. Han, S. H. Seok, Y. H. Jin, J. Park, Y. Lee, H. U. Yeo, J. H. Back, Y. Sim, Y. Chae, J. Wang, G. Y. Oh, W. Lee, S. H. Park, I. C. Bang, J. H. Kim, S. Y. Kwon*

– Nature Communications, 14, Article number: 6957 (2023)

Effects of Cr and Mo contents on the flow-accelerated corrosion behavior of low alloy steels in the secondary side of pressurized water reactors

– S. Kim, G. Kim, S. W. Song, J. H. Kim*

– Journal of Nuclear Materials, Volume 585, 154652, (2023)

Effects of yttrium on the oxidation behavior of Fe13Cr6AlY alloys under 1200 °C steam

– S. Kim, C. H Lee, T. Kim, J. H. Jang, J. Moon, D. F. Falaakh, J. H. Kim, C. B. Bahn*

– Journal of Alloys and Compounds, Volume 960, 170642, (2023)

The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation

– J. Y. Kim, Y. Lee, J. H. Kim I. C. Bang*

– Nuclear Engineering and Technology, Volume 55, Issue 9, Pages 3164-3182, (2023)

Stability of Cr oxide formed on Fe-20Cr-2Si alloy in 1200 °C steam or oxygen

– J. Moon, S. Kim, Michael P. Short, J. H. Kim, C. B. Bahn*

– Corrosion Science Volume 220, 111236, (2023)

Fatigue residual useful life estimation of Ni-base alloy weld with time-series data

– J. P. Park, J. Ham, J. H. Kim, Y. J. Oh, C. B. Bahn*

– Journal of Mechanical Science and Technology, Volume 37, pages 2353–2362, (2023)

Statistical analysis of S N type environmental fatigue data of Ni-base alloy welds using weibull distribution

– J. P. Park, J. Ham, S. Mohanty, D. F. Falaakh, J. H. Kim, C. B. Bahn*

– Nuclear Engineering and Technology, Volume 55, Issue 5, Pages 1924-1934, (2023)

High-temperature steam oxidation of (Ti, Mo)C-forming FeCrAlY alloy

- S. Kim, C. H. Lee, J. H. Jang, J. Moon, J. H. Kim*

- Journal of Nuclear Materials, Volume 574, 154220, (2023)

Effects of Heat and Gamma Radiation on the Degradation Behaviour of Fluoroelastomer in a Simulated Severe Accident Environment

- I. Song, T. Lee, K, Ryu, Y. J. Kim, M. S. Kim, J, W, Parkand J. H. Kim*

- Nuclear Engineering and Technology, Volume 54, Issue 12, Pages 4514-4521, (2022)

Effect of TiN Coating on the Fouling Behavior of Crud on Pressurized Water Reactor Fuel Cladding

- J. Ham, Y. Lee, S. C. Yoo, M. P. Short, C. B. Bahn and J. H. Kim*

- Journal of Nuclear Materials, Vol. 549, pp. 152870, 2021.06

Development of probabilistic primary water stress corrosion cracking initiation model for alloy 182 welds considering thermal aging and cold work effects

- J. P. Park, S. C. Yoo, J. H. Kim and C. B. Bahn*

- Nuclear Engineering and Technology, Vol. 53, pp. 1909-1923, 2021.06

Using rate theory to better understand the stress effect of irradiation creep in iron and its based alloy

- S. I. Choi, M. J. Banisalman, G. -G. Lee, J. Kwon, E. Yoon and J. H. Kim*

- Journal of Nuclear Materials, Vol. 536, pp. 152-198, 2020.08

In-situ electrochemical study of zirconium alloy in high temperature hydrogenated Water conditions

- T. Kim, A. Couet, S. Kim, Y. Lee, S. C. Yoo and J. H. Kim*

- Corrosion Science, Vol. 173, pp. 108745, 2020.08

Effects of Heat and Radiation on the Degradation Behaviour of Fluoroelastomer

- T. H. Lee, I. Y. Song, K. H. Ryu, D. C. Baek, J. W. Park and J. H. Kim*

- 신뢰성응용연구 제19권 제4호, 2019.12

A Study on the Relationship between Electronic Structure and Corrosion Characteristics of Zirconium Alloy in High-temperature Hydrogenated Water

- T. Kim, S. Kim, Y. Lee, N. Kim, C. B. Bahn, A. Couet and J. H. Kim*

- Corrosion Science, Vol 157, Pages 180-188, 2019.08

Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing

- T. H. Lee, K. H. Ryu, H. D. Kim, I. S. Hwang, J. H. Kim, M. H. Lee, S. Choi*

- Nuclear Engineering and Technology, Vol 51, Pages 1381-1389, 2019.08

Microstructural evolution and corrosion behaviour of thermally aged dissimilar metal welds of low-alloy steel and nickel-based alloy

- K. J. Choi, S. C. Yoo, S. Kim, T. Kim, J. Ham, J. Lee and J. H. Kim*

- Corrosion Science, Vol 153, Pages 138-149, 2019.06

Initial oxidation behavior of Fe-Cr-Si alloys in 1200 degrees C steam

- J. Moon, S. Kim, W. D. Park, T. Y. Kim, S. W. McAlpine, M. P. Short, J. H. Kim and C. B. Bahn*

- Journal of Nuclear Materials, Vol 513, Pages 297-308. 2019.01

Fatigue behavior of AISI 8620 steel exposed to magnetic field

- K. J. Choi, S. C. Yoo, J. Ham, J. H. Kim*, S. Y. Jeong and Y. S. Choi*

- Journal of Alloys and Compounds, Vol 764, Pages 73-79, 2018.10

Natural circulation characteristics under various conditions on heavy liquid metal test loop

- K. Ryu, B. M. Ban, T. H. Lee, J. Lee, S. H. Lee, J. H. Cho, S. Ko and and J. H. Kim*

- International Journal of Thermal Sciences, Vol 132, Pages 316-321, 2018.10

Survivability assessment of Viton in safety-related equipment under simulated severe accident environments

- K. Ryu, I. Song, T. Lee, S. Lee, Y. Kim and J. H. Kim*

- Nuclear Engineering and Technology, Vol 50, Pages 683-689, 2018.6

Microscopic characterization of pretransition oxide formed on Zr–Nb–Sn alloy under various Zn and dissolved hydrogen concentrations

- S. Kim, T. Kim, J. H. Kim and C. B. Bahn*

- Nuclear Engineering and Technology, Vol 50, Pages 416-424, 2018.4

Influence of dissolved hydrogen on the early stage corrosion behavior of zirconium alloys in simulated light water reactor coolant conditions

- T. Kim, K. J. Choi, S. C. Yoo, Y. Lee and J. H. Kim*

- Corrosion Science, Vol 131, Pages 235-244, 2018.2

Statistical analysis of parameter estimation of a probabilistic crack initiation model for Alloy 182 weld considering right-censored data and the covariate effect

- J. P. Park, C. PArk, Y.-J Oh, J. H. Kim and C. B. Bahn*

- Nuclear Engineering and Technology, Vol 50, Pages 107-115, 2018.2

Formation of 3D graphene–Ni foam heterostructures with enhanced performance and durability for bipolar plates in a polymer electrolyte membrane fuel cell

- Y. Sim, J. kwak, S.-Y. Kim, Y. Jo, S. kim, S.Y. kim, J. H. Kim, C.-S. Lee, J. H. Jo and S.-Y. Kwon*

- Journal of Materials Chemistry A, Vol 6, Pages 1504-1512, 2017.12

Reply to discussion on “Microstructural evolution and stress-corrosion-cracking behavior of thermally aged Ni-Cr-Fe alloy” by S.C. Yoo, K.J. Choi, T. Kim, S.H. Kim, J.Y. Kim, J.H. Kim [Corros. Sci. 111 (2016) 39]

- S. C. Yoo, K. J. Choi, T. Kim, S. H. Kim, J. Y. Kim and J. H. Kim*

- Corrosion Science, Vol 128, Pages 267-269, 2017.11

Zinc Adsorption and Hydration Structures at Yttria-Stabilized Zirconia Surfaces

- B. Hou, T. Kim, S. Kim, C. Park, C. B. Bahn, J. Kim, S. Hong, and J. H. Kim*

- Journal of Physical Chemistry C, Vol 121, Pages 21305-21310, 2017.10

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

Enhancement of corrosion resistance in carbon steels using nickel-phosphorous/titanium dioxide nanocomposite coatings under high-temperature flowing water

- S. Kim, J. W. Kim and J. H. Kim*

- Journal of Alloys and Compounds, Vol 698, Pages 267-275, 2017.03

Effect of defects on reaction of NiO surface with Pb-contained solution

- 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

Crack growth behavior of warm-rolled 316L austenitic stainless steel in high-temperature hydrogenated water

- 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

Effect of oxygen potential on crack growth in alloys for advanced energy systems

- 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

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 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

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

Dynamic Loading Fracture Tests of Ferritic Steel Using the Direct Current Potential Drop Method

- Y. J. Oh, J.H. Kim*, I. S. Hwang