conference


Application of Nano-Structured Thermal Spray Coatings for Nuclear Power Plants Piping System
  • S. H. Kim, K. J. Choi, T. H. Kim, S. C. Yoo, J. W. Kim and J. H. Kim
  • International Thermal Spray Conference, Long Beach, California, May 11~May 14, 2015.

Impedance response of surface oxidation of zirconium alloy in PWR primary water condition
  • T. H. Kim, S. H. Kim, K. J. Choi, S. C. Yoo and J. H. Kim
  • 2015 Materials Challenges in Alternative & Renewable Energy, Jeju, Korea, Feb. 24 ~ Feb. 27, 2015.

High-temperature Corrosion Characteristics of Nano-particle Enhanced Coatings for Secondary Piping Systems of Nuclear Power Plants
  • S. H. Kim, J. W. Kim and J. H. Kim
  • Materials Challenges in Alternative & Renewable Energy, Jeju, Korea, Feb. 24~Feb. 27, 2015.

In-situ Raman spectroscopic study of oxide films on zirconium alloy in simulated PWR water conditions
  • T. H. Kim, K. J. Choi, S. H. Kim, S. C. Yoo and J. H. Kim
  • 19th International Corrosion Congress, Jeju, Korea, November 2 ~ November 6, 2014.

Effects of Dissolved Hydrogen and Warm Rolling on IASCC in Austenitic Stainless Steel
  • K. J. Choi, S. C. Yoo, T. H. Kim, S. H. Kim and J. H. Kim
  • 19th International Corrosion Congress, Jeju, November 2 ~ November 6, 2014.

Understanding of Early Stage Oxidation Behavior on Ni Surface Using Ab-initio Molecular Dynamics
  • K. B. Ko, J. J. Kim and J. H. Kim
  • 2014 Nuclear Plant Chemistry Conference, Sapporo, Japan, Oct. 26~ Oct. 31, 2014.

In-situ oxide investigation of oxide films on Zr-cladding with varying dissolved hydrogen concentration
  • J. J. Kim, T. H. Kim, S. H. Kim and J. H. Kim
  • 2014 Nuclear Plant Chemistry Conference, Sapporo, Japan, Oct. 26~ Oct. 31, 2014.

Application of Nano-strutured Coatings to Mitigate Flow-Accelerated Corrosion in Secondary Pipe Systems of Nuclear Power Plants
  • S. H. Kim, J. J. Kim, S. C. Yoo and J. H. Kim
  • 2014 Nuclear Plant Chemistry Conference, Sapporo, Japan, Oct. 26~Oct. 31, 2014.

A corrosion model of ferritic-martensitic steel in a high temperature sodium
  •  S. H. Shin, J. H. Kim, S. H. Kim and J. H. Kim
  • NuMat 2014: The Materials Conference, Clearwater Beach, Florida, Oct. 27~Oct. 30, 2014.

Three-dimensional atom probe study of fusion boundary region in the thermally aged dissimilar metal welds of nickel-base alloy and low alloy steel
  • K. J. Choi, S. C. Yoo, B. H. Lee and J. H. Kim
  • Atom Probe Tomography & Microscopy 2014, Stuttgart, Germany, August 31~September 5, 2014.

Investigation of Microstructural changes due to thermal aging in dissimilar metal welds
  • K. J. Choi, S. C. Yoo, C. B. Bahn and J. H. Kim
  • ASME 2014 Pressure Vessels & Piping Conference, Anaheim, California, July 20~July 24, 2014.

Thermal aging effects on microstructures of type-II boundary in dissimilar metal weld joints
  • S. C. Yoo, K. J. Choi and J. H. Kim
  • ASME 2014 Pressure Vessels & Piping Conference, Anaheim, California, July 20~July 24, 2014.

Modeling irradiation growth of zirconium and its alloy in nuclear reactors
  • S. I. Choi, G. G. Lee, J. H. Kwon and J. H. Kim
  • 2014 America Nuclear Society Annual Meeting, Reno, Nevada, June 15~ June 19, 2014.

In-situ X-ray reflectivity study of interfacial structure between the pre-oxidized Ni(110) surface and liquid
  • J. J. Kim, T. H. Kim, S. H. Kim, H. Yang, C. Park and J. H. Kim
  • 2014 ANS Embedded Topical Meeting: Nuclear Fuels & Structural Materials for Next Generation Nuclear Reactors, Reno, Nevada, June 15~June 19, 2014.

Impedance response of pre-oxidized ferritic-martensitic steels in high temperature liquid sodium environment: UCFR application
  • S. H. Shin, J. H. Lee and J. H. Kim
  • 2014 ANS Embedded Topical Meeting: Nuclear Fuels & Structural Materials for Next Generation Nuclear Reactors, Reno, Nevada, June 15~June 19, 2014.

Simulation of Ni-63 Nuclear Micro Battery Using Monte Carlo Modeling
  • T. H. Kim and J. H. Kim
  • 2014 American Nuclear Society Annual Meeting, Reno, Nevada, June 15~June 19, 2014.

Study on compatibility on ferritic-martensitic steels with high-temperature sodium for SFR application
  • S. H. Shin, J. H. Kim and J. H. Kim
  • 2014 ANS Embedded Topical Meeting: Nuclear Fuels & Structural Materials for Next Generation Nuclear Reactors, Reno, Nevada, June 15~June 19, 2014. 

Investigation of atomistic structure of Ni(110)/NiO-water interface using high resolution X-ray reflectivity
  • J. J. Kim, C. B. Bahn, H. Yang, C. Park and J. H. Kim
  • 2014 International cooperative group on Environmentally Assisted Cracking, Prague, Czech, Apr. 6~Apr. 11, 2014. 

In-situ spectroscopy analysis of surface oxide films on nickel-base alloy/low alloy steel dissimilar metal weld interface in PWR primary water condition
  • J. J. Kim, K. J. Choi, S. H. Kim and J. H. Kim
  • 2013 International Symposium on Radiation Safety Management, Daejeon, Korea, Nov. 6~Nov.8, 2013. 

Radiation induced growth of zirconium alloy in research reactor
  • S. I. Choi, G. G. Lee, J. H. Kwon and J. H. Kim
  • IGORR 2013 & IAEA Technical Meeting, Daejeon, Korea, Oct. 13~Oct. 18, 2013. 

Potentiometric oxygen sensor based on gadolinia doped ceria (GDC) for use in SFR application
  • S. H. Shin and J. H. Kim
  • Third International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-3), Idaho Falls, USA, Oct. 7~Oct. 10, 2013. 

A study on influence of liquid sodium on the mechanical properties of ferritic/martensitic steel (Gr.92)
  • S. H. Shin, J. H. Kim and J. H. Kim
  • Third International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-3), Idaho Falls, USA, Oct. 7~Oct. 10, 2013. 

In-situ Raman spectroscopic analysis of aging effect of surface oxide films on Ni-base alloy/LAS dissimilar metal weld interfaces
  • J. J. Kim, C. B. Bahn and J. H. Kim
  • 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Asheville, North Carolina, August 11~August 15, 2013.

A study of thermal aging effect on microstructures of dissimilar metal weldment
  • K. J. Choi, J. J. Kim and J. H. Kim
  • 21th International Conference on Nuclear Engineering, Chengdu, China, July 29~August 2, 2013.

A study of thermal aging effect on microstructures of dissimilar metal weldment
  • K. J. Choi, S. H. Shin, J. J. Kim and J. H. Kim
  • 2013 International cooperative group on Environmentally Assisted Cracking, Karuizawa, Japan, May 19 ~ May 24, 2013.

In-situ analysis of aging effect on surface oxide films on Ni- base alloy/LAS dissimilar metal weld interfaces using Raman spectroscopy
  • J. J. Kim, K. J. Choi and J. H. Kim
  • 2013 International cooperative group on Environmentally Assisted Cracking, Karuizawa, Japan, May 19~May 24, 2013.

Feasibility study of fuel cladding performance for application in ultra-long cycle fast reactor
  • J. A. Jung, S. H. Kim, S. H. Shin, J. J. Kim, K. J. Choi, S. I. Choi and J. H. Kim
  • 2013 International Congress on Advances in Nuclear Power Plants, Jeju Island, Korea, April 14~April 18, 2013.

Electrochemical impedance spectroscopy analysis of HT9, Gr.92 and SiC in liquid sodium environment for UCFR application
  • S. H. Shin, J. J. Kim, K. J. Choi, S. I. Choi, S. H. Kim
  • A. Y. Choi and J. H. Kim, 2013 International Congress on Advances in Nuclear Power Plants, Jeju Island, Korea, April 14~April 18, 2013. 

Development of electrochemical oxygen sensor and experimental system for materials compatibility test for ultra-long cycle fast reactor (UCFR)
  • S. H. Shin, J. J. Kim, J. A. Jung, K. J. Choi, S. I. Choi and J. H. Kim
  • International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), Paris, France, March 4~March 7, 2013. 

Effect of thermal aging to microstructure in the interface of dissimilar metal weld
  • K. J. Choi, S. H. Shin, J. J. Kim, S. I. Choi and J. H. Kim
  • NuMat 2012: The Materials Conference, Osaka, Oct. 21~Oct. 25, 2012.

A study on performance evaluation of fuel claddings for ultra-long cycle fast reactors
  • J. A. Jung, S. H. Shin, J. J. Kim, K. J. Choi, S. I. Choi and J. H. Kim
  • NuMat 2012: The Materials Conference, Osaka, Japan, Oct. 21~Oct. 25, 2012.

In-situ Raman spectroscopic analysis of surface oxide films on Ni- base alloy/LAS dissimilar metal weld interfaces
  • J. J. Kim, S. H. Shin, K. J. Choi, S. I. Choi and J. H. Kim
  • NuMat 2012: The Materials Conference, Osaka, Japan, Oct. 21~Oct. 25, 2012.

Development of electrochemical oxygen sensor for the use in high temperature sodium environment
  • S. H. Shin, J. J. Kim, K. J. Choi, S. I. Choi and J. H. Kim
  • NuMat 2012: The Materials Conference, Osaka, Japan, Oct. 21~Oct. 25, 2012.

Nanostructural characterization of Ni-base alloy/low alloy steel dissimilar metal weld (DMW) interface
  • K. J. Choi, S. H. Shin, J. J. Kim, J. A. Jung, S. I. Choi and J. H. Kim
  • 20th International Conference on Nuclear Engineering, Anaheim, California, July 30~ Aug. 3, 2012.

Atomistic modeling of interstitial diffusion of oxygen in nickel chromium binary alloy
  • J. J. Kim, K. J. Choi and J. H. Kim
  • 20th International Conference on Nuclear Engineering, Anaheim, California, July 30~ Aug. 3, 2012.

Development of experimental system for materials compatibility test for ultra-long cycle fast reactor
  • S. H. Shin, J. J. Kim, J. A. Jung, K. J. Choi, S. I. Choi and J. H. Kim
  • 2012 American Nuclear Society Annual Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Chicago, Illinois, June 24~28, 2012.

A study of fuel cladding design parameters for ultra-long cycle fast reactor
  • J. A. Jung, S. H. Shin, J. J. Kim, K. J. Choi, S. I. Choi and J. H. Kim
  • 2012 American Nuclear Society Annual Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Chicago, Illinois, June 24~28, 2012.

In-situ raman spectroscopic analysis of Ni-base alloy/LAS dissimilar metal weld interface
  • J. J. Kim, S. H. Shin, J. A. Jung, K. J. Choi, S. I. Choi and J. H. Kim
  • 2012 American Nuclear Society Annual Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, Chicago, Illinois, June 24~28, 2012.

Advanced instrumental science-based study on dissimilar metal weld ageing and its effect on cracking in PWRs
  • K. J. Choi, S. H. Shin, J. J. Kim, J. A. Jung, S. I. Choi and J. H. Kim
  • 3rd International Conference on NPP Life Management for Long Term Operation, Salt Lack City, UT, May. 14~18, 2012.

Ab-initio calculation of diffusion of atomic oxygen in nickel and Ni-Cr
  • J. J. Kim, H. Y. Nam and J. H. Kim
  • 2011 American Nuclear Society Winter Meeting, Washington D. C, Oct. 30~ Nov. 3, 2011.

An Experimental study on corrosion behavior of SS 316L in liquid gallium and gallium alloys
  • S. H. Shin, J. J. Kim, I. C. Bang and J. H. Kim
  • 2011 American Nuclear Society Winter Meeting,  Washington D. C, Oct. 30~ Nov. 3, 2011.

Study on natural convection capability of liquid gallium for PDRC
  • S.D. Park, S.W. Lee, S. Kang, I.C. Bang and J. H. Kim
  • 2010 American Nuclear Society Winter Meeting, Washington D. C, Oct. 30~ Nov. 3, 2011.

Evaluation of the oxygen diffusion coefficient in nickel-base alloys
  • J. J. Kim, S. H. Shin, J. A. Jung, K. J. Choi and J. H. Kim
  • 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-water reactors, Colorado Springs, Colorado, Aug. 7~11, 2011.

Enhancement of thermal margin for in-vessel retension by external reactor vessel cooling using graphene/graphene-oxide nanofluids
  • S.D. Park, S.W. Lee, S. Kang, I.C. Bang and J. H. Kim
  • 2011 International Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, France, May. 2~ 5, 2011.

Corrosion behavior of structural materials in liquid gallium environments
  • S. H. Shin, J. J. Kim, J. S. Park, I. C. Bang and J. H. Kim
  • 2011 International Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, France, May. 2~ 5, 2011.

Highly enhanced CHF of nanofluids containing graphene and graphene-oxide nanosheets without improved surface wettability
  • S.D. Park, S.W. Lee, S. Kang, I.C. Bang and J. H. Kim
  • 2010 American Nuclear Society Annual Meeting, San Diego, California, June. 13~ 17, 2010.

Experimental evaluation of natural convection loop for liquid gallium
  • S.D. Park, S.W. Lee, S. Kang, I.C. Bang and J. H. Kim
  • 2010 American Nuclear Society Winter Meeting, Las Vegas. Nevada, Nov. 7~ 11, 2010.

Corrosion behavior of structural materials in liquid gallium environments
  • S. H. Shin, J. J. Kim, J. S. Park, Y. Kim, I. C. Bang and J. H. Kim
  • 2010 American Nuclear Society Winter Meeting,  Las Vegas. Nevada, Nov. 7~ 11, 2010.

Investigation of thermal conductivity of nanofluids with liquid gallium as base fluid for nuclear application
  • I. C. Bang and J. H. Kim
  • International Congress on Advances in Nuclear Power Plants (ICAPP 2010), San Diego, California, June. 13~ 17, 2010.

Design of alumina forming FeCrAl steels for lead or lead-bismuth
  • J. Lim, I.S. Hwang and J. H. Kim
  • 2010 American Nuclear Society Annual Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, San Diego, California, June 13~ 17, 2010.

Rod-type quench performance of nanofluids towards developments of advanced PWR nanofluids-engineered safety features
  • S.D. Park, S.W. Lee, S. Kang, I.C. Bang and J. H. Kim
  • International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century, Vienna, Austria, Oct. 27~ 30, 2009.

Environmentally assisted cracking related research at UNIST
  • J. H. Kim
  • International Cooperative Group on Environmentally Assisted Cracking in Nuclear Power Plant (ICG-EAC 2009), Boston, MA, Apr. 19~ 24, 2009.

Effect of Thermal Aging on SCC and Mechanical Properties of Stainless Steel Weld Metals
  • J. Hixon, J. H. Kim and R. G. Ballinger
  • 13th International Conference on Environmental Degradation of Materials in Nuclear Systems-Water Reactors, Whistler, Canada, Aug. 19~23, 2007.

The 4K mechanical properties of modified SS316LN for jacket materials in superconducting fusion magnets
  • J.H. Kim and J Feng
  • 2007 CEC-ICMC, Chattanooga, TN, July 16-20, 2007.

The ITER Central Solenoid Conductor
  • J.H. Schultz, J.V. Minervini, T. Antaya, J. Feng, V. Fishman, C-Y. Gung, J.H. Kim, N. Martovetsky, P. Michael, A. Radovinsky, M. Takayasu, P. Titus
  • 19th International Conference on Magnet Technology (MT-19), Genova, Italy, Sep. 18~23, 2005.

Mechanical properties of JK2LB at 4K
  • J. Feng, J.H. Kim, R.G. Ballinger and J.V. Minervini
  • CEC-ICMC 05, Keystone, CO, Aug. 29~ Sep. 2, 2005.

Development of Intraspecimen Method for the Application to Life Prediction
  • H.S. Choi, C.B. Bahn, J.H. Kim and I.S. Hwang
  • 12th International Conference on Environmental Degradation of Materials in Nuclear Systems-Water Reactors, Salt Lake City, UT, Aug. 15~18, 2005.

Mechanistic Understanding of Primary Water Stress Corrosion Cracking of Alloy 600 in PWR Water
  • J.H. Kim and I.S. Hwang
  • 2004 American Nuclear Society Annual Meeting, Pittsburgh, PA, June 13-17, 2004.

Mechanistic Understanding of Primary Water Stress Corrosion Cracking in Nickel-base Alloys
  • J.H. Kim and I.S. Hwang
  • 26th International Cooperative Group-Environmental Assisted Cracking Meeting, Yumebutai, Japan, April 19-23, 2004.

Mitigation of primary water stress corrosion cracking by nickel plating methodology
  • J.H. Kim, S. Oh, and I. S. Hwang
  • 2003 ANS/ENS International Winter Meeting, New Orleans, November 16-20, 2003.

In-situ Raman Spectroscopic Study of Oxide Films on Alloy 600 in simulated PWR Water Conditions
  • J.H. Kim and I.S. Hwang
  • 11th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Stevenson, WA, August 11-14, 2003.

Fracture behavior of heat affected zone in low alloy steels
  • J.H. Kim, Y.J. Oh and I.S. Hwang
  • ANS/ENS 2000 International Winter Meeting, Washington D. C., November 12-16, 2000.

Dynamic Fracture Testing of Ferritic Steels using the DCPD Method
  • Y.J. Oh, J.H. Kim and I.S. Hwang
  • ANS/ENS 2000 International Winter Meeting, Washington D. C., November 12-16, 2000.

Elastic plastic fracture mechanics behavior of a part-through crack in nuclear piping
  • J.H. Kim and I.S. Hwang
  • ASME/JSME Joint Pressure Vessels and Piping Conference, San Diego, CA, USA, July 26-30, 1998.

New Failure Prediction Model for a Ni-Fe Superalloy Sheath for Superconducting Fusion Magnets
  • J.H. Kim, I. S. Hwang, and R. L. Tobler
  • CEC-ICMC 97, Portland, July 27-Aug. 1, 1997.