Presentations

(International Conferences only)

Effect of TiN and ZrN Coatings on CRUD Deposition Behavior of a Pressurized Water Reactor Fuel Cladding

- J. Ham, and J. H. Kim*

- The Minerals, Metals & Materials Society 2020 Annual meeting, San Diego, CA, USA, Feb. 23 ~ Feb. 27, 2020

Effect of TiN and ZrN Coatings on CRUD Deposition Behavior of a Pressurized Water Reactor Fuel Cladding

- J. Ham, and J. H. Kim*

- Global/Top Fuel 2019, Seattle, WA, USA, Sep. 22 ~ Sep. 26, 2019

Porosity and Chemistry Change of CRUD with Different Heat Flux Conditions

- Y. Lee, and J. H. Kim*

- The 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, Boston, MA, USA, Aug. 18 ~ Aug. 22, 2019

A Study on Microstructure and Corrosion Properties of Alumina Foaming Austenitic Stainless Steel on Liquid Metal Corrosion Resistance for Lead-bismuth cooled Fast Reactor Cladding Application

- J. Lee, and J. H. Kim*

- Structural Materials for Innovative Nuclear Systems, Kyoto, Japan, Jul. 8 ~ Jul. 11, 2019

Investigation of Microstructure and Corrosion Properties of Aluminum Containing Super Austenitic Stainless Steel on Chloride Induced Stress Corrosion Cracking resistance for dry storage canister

- J. Lee, and J. H. Kim*

- Structural Materials for Innovative Nuclear Systems, Kyoto, Japan, Jul. 8 ~ Jul. 11, 2019

Degradation Behavior of Fluoroelastomer under Simulated Severe Accident Environment

- I. Y. Song, and J. H. Kim*

- 2019 ANS Annual Meeting, Minneapolis, MN, USA, Jun. 9 ~ Jun. 13, 2019

In-situ PWSCC initiation measurement of nickel-based alloy under triaxial stress state in simulated PWR water environment

- S. C. Yoo, and J. H. Kim*

- 2019 ANS Annual Meeting, Minneapolis, MN, USA, Jun. 9 ~ Jun. 13, 2019

Effect of heat flux condition on structure and chemistry of crud

- Y. Lee, and J. H. Kim*

- 27th International Conference on Nuclear Engineering, Tsukuba, Japan, May 19 ~ May 24, 2019

Effect of triaxial stress state on PWSCC initiation behavior of nickel-based alloy

- S. C. Yoo, and J. H. Kim*

- 2019 ICG-EAC, Tainan, Taiwan, May 12 ~ May 19, 2019

Investigation of Flow Accelerated Corrosion Behavior of Carbon Steels and Low Alloy Steels via Synchrotron Scanning Tunneling X-ray Microscopy

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

- 2018 ANS Winter Meeting and Nuclear Technology Expo., Orlando, Fl, USA, Nov. 11 ~ Nov. 15, 2018

Evaluation of Pilgering Process of Functionally Graded Composite tube for Lead-Bismuth Eutectic cooled fast reactor through Finite Element Analysis

- T. Kim, and J. H. Kim*

- 2018 Generation IV International Forum symposium, Paris, France, Oct. 16 ~ Oct. 17, 2018

Effects of uniaxial stress on 1D migrating self-interstitial clusters in production bias method

- S. I. Choi, and J. H. Kim*

- The Nuclear Materials Conference (NuMat 2018), Seattle, WA, USA, Oct. 14 ~ Oct. 18, 2018

Study on Q-value about Pilgering Process of Functionally Graded Composite Cladding for Liquid Metal Fast Cooled Reactor Application

- T. Kim, and J. H. Kim*

- Heavy Liquid Metal Coolants in Nuclear Technologies, Moscow, Russia, Oct. 8, 2018

Synchrotron X-ray Study on Determination of Zirconium Oxide Stoichiometry in Hydrogenated Water

- T. Kim, and J. H. Kim*

- Top Fuel 2018, Prague, Czech Republic, Sep. 30 ~ Oct. 4, 2018

Effects of Minor Element on Corrosion Characteristic of Zr Alloy in Simulated Primary Water

- Y. Lee, and J. H. Kim*

- 21st International Conference on Water Chemistry in Nuclear Reactor Systems, San Francisco, CA, USA, Sep. 9 ~ Sep. 14, 2018

Effects of Surface Coating on CRUD Deposition Behavior of Fuel Cladding in Simulated Primary Water

- J. Ham, and J. H. Kim*

- 21st International Conference on Water Chemistry in Nuclear Reactor Systems, San Francisco, CA, USA, Sep. 9 ~ Sep. 14, 2018

Electronic Structure and Hybridization Effects of Zirconium Alloy in High Temperature Water

- T. Kim, and J. H. Kim*

- 21st International Conference on Water Chemistry in Nuclear Reactor Systems, San Francisco, CA, USA, Sep. 9 ~ Sep. 14, 2018

Characterization of Mechanical and Corrosion Properties of Mo-free Low Alloy Steels for Pipeline Application

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

- The US-KOREA Conference on Science, Technology and Entrepreneurship, New York City, NY, USA, Aug. 1 ~ Aug. 4, 2018

PWSCC Initiation Behavior of Nickel-based Alloy after Long-term Aging

- S. C. Yoo, and J. H. Kim*

- 26th International Conference on Nuclear Engineering, London, UK, Jul. 22 ~ Jul.28, 2018

Irradiation creep behavior of iron base alloy at high temperature condition

- S. I. Choi, and J. H. Kim*

- 2018 ANS Annual Meeting, Philadelphia, PA, USA, Jun. 17 ~ Jun. 21, 2018

Electronic Structure and Hybridization Effects of Zirconium Alloy in High Temperature Water

- T. Kim, and J. H. Kim*

- Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2018), Philadelphia, PA, USA, Jun. 17 ~ Jun. 21, 2018

Electronic structure characterization of oxide films on zirconium alloy in high temperature water

- T. Kim, and J. H. Kim*

- AISTech 2018 Iron and Steel Technology Conference and Exposition, Philadelphia, PA, USA, May 7 ~ May 10, 2018

Stress Corrosion Cracking Initiation Behavior of Alloy 600 with the Consideration of Long-term Thermal Aging and Triaxial Stress State

- S. C. Yoo, and J. H. Kim*

- 2018 ICG-EAC, Knoxville, TN, USA, Apr. 12 ~ Apr. 16, 2018

Evaluation of degradation effect on fluoroelastomer in simulated severe accident environment of nuclear power plants

- I. Y. Song, and J. H. Kim*

- 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018, Charlotte, NC, USA, Apr. 8 ~ Apr. 11, 2018

Effects of TiO2 Nanoparticles on Oxygen Evolution Reaction of Ni-P Electrodes in KOH Solution

- S. Kim, T. Kim, I. C. Bang and J. H. Kim*

- 5th Nano Today Conference, Hawaii, USA, Dec. 6 ~ Dec. 10, 2017

PWSCC Behavior of Alloy 600 under Long-term Thermal Aging and Triaxial Stress

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

- 4th International Conference on Nuclear Power Plant Life Management, Lyon, France, Oct. 23 ~ Oct. 27, 2017

In-situ Investigation of Zirconium Oxide Alloy in Primary Water with Different Dissolved Hydrogen Concentration

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

- Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia - 2017 & 5th International Symposium on Materials and Reliability in Nuclear Power Plants, Shenyang, China, Sep. 26 ~ Sep. 28, 2017

Microstructure and Chemical Analysis on Carbon Steels and Fe-2.2Cr-1Mo Alloys in Simulated Flow-accelerated Corrosion Environment using XAS and XPS

- S. Kim, T. Kim, Y. Lee and J. H. Kim*

- Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia - 2017 & 5th International Symposium on Materials and Reliability in Nuclear Power Plants, Shenyang, China, Sep. 26 ~ Sep. 28, 2017

In-situ Investigation of Oxide on Zirconium Alloy in Primary Water

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

- 2017 Water Reactor Fuel Performance Meeting, Jeju, Korea, Sep. 10 ~ Sep. 14, 2017

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

- J. Lee, G. H. Ryu, T. H. Lee and J. H. Kim*

- Global Symposium on Lead and Lead Alloy Cooled Nuclear Energy Science and Technology, Seoul, Korea, Sep. 07 ~ Sep. 08, 2017

Stress Corrosion Cracking Initiation Behavior of Alloy 600 with the Consideration of Long-term Thermal Aging and Triaxial Stress State

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

- 24th International Conference Structural Mechanics in Reactor Technology, Busan, Korea, Aug. 20 ~ Aug. 25, 2017

Verification of simplified modelling method for thermal lag analysis

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

- 24th International Conference Structural Mechanics in Reactor Technology, Busan, Korea, Aug. 20 ~ Aug. 25, 2017

PWSCC initiation of Alloy 600: Effect of Long-term Thermal Aging and Triaxial Stress

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

- 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Partland, Oregon, USA, Aug. 13 ~ Aug. 17, 2017

Investigation of flow accelerated corrosion models to predict the corrosion behavior of coated carbon steels in secondary piping systems

- S. Kim and J. H. Kim*

- 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Partland, Oregon, USA, Aug. 13 ~ Aug. 17, 2017

Electronic Structure and Hybridization Effects of Zirconium Alloy in High Temperature Water

- T. Kim, S. Kim, Y. Lee and J. H. Kim*

- 4th Asian Zirconium Workshop, Jeju, Korea, May. 17 ~ May 19, 2017

Microstructure and Corrosion Evolution of Fusion Boundary between Low Alloy Steel and Ni-base Weld Metal

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

- Asian Conference on Experimental Mechanics 2016, Jeju, Korea, Nov. 13 ~ Nov. 16, 2016.

Microstructure and Corrosion Evolution of Fusion Boundary between Low Alloy Steel and Ni-base Weld Metal

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

- Asian Conference on Experimental Mechanics 2016, Jeju, Korea, Nov. 13 ~ Nov. 16, 2016.

PWSCC initiation susceptibility of thermally aged Alloy 600 under triaxial stress state

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

- Asian Conference on Experimental Mechanics 2016, Jeju, Korea, Nov. 13 ~ Nov. 16, 2016.

Hydration structures and water chemistry at zirconia-water interface

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

- Pacific Rim Meeting on Electrochemical and Solid-state Science 2016, Honolulu, USA, Oct. 02 ~ Oct. 07, 2016.

A study of high temperature stability of zirconia surface in pressurized water with high resolution X-ray reflectivity

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

- Pacific Rim Meeting on Electrochemical and Solid-state Science 2016, Honolulu, USA, Oct. 02 ~ Oct. 07, 2016.

Electrochemical properties of Fe-based amorphous metallic coatings in aqueous media

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

- Pacific Rim Meeting on Electrochemical and Solid-state Science 2016, Honolulu, USA, Oct. 02 ~ Oct. 07, 2016.

Enhancement of corrosion resistance in carbon steels using Fe-based amorphous metallic coatings under high-temperature flowing water

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

- Pacific Rim Meeting on Electrochemical and Solid-state Science 2016, Honolulu, USA, Oct. 02 ~ Oct. 07, 2016.

Effects of zinc injection and dissolved hydrogen concentration on ZIRLOTM oxidation

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

- Nuclear Plant Chemistry Conference 2016, Brighton, UK, Oct. 02 ~ Oct. 07, 2016.

Ion adsorption at zirconia-water interface

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

- Nuclear Plant Chemistry Conference 2016, Brighton, UK, Oct. 02 ~ Oct. 07, 2016.

Hydration structures at zirconia-water interface

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

- Nuclear Plant Chemistry Conference 2016, Brighton, UK, Oct. 02 ~ Oct. 07, 2016.

Corrosion behavior and microstructural evolution of fusion boundary between low-alloy steel and Ni-base weld metal

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

- Asia-Pacific Conference on Fracture and Strength 2016, Toyama, Japan, Sep. 19 ~ Sep. 22, 2016.

Stress corrosion cracking initiation behavior of thermally aged Alloy 600 under triaxial stress condition

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

- Asia-Pacific Conference on Fracture and Strength 2016, Toyama, Japan, Sep. 19 ~ Sep. 22, 2016.

Microstructural characteristics of Alloy 600 in long-term thermal aging

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

- Atom Probe Tomography & Microscopy 2016, Gyeongju, Korea, Jun. 12 ~ Jun. 15, 2016.

Electrochemical properties of Ni-TiO2/NiO Nanocomposite in Amine-containing solutions at the elevated temperature

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

- 229th Electrochemical Society Meeting, San Diego, USA, May. 29 ~ Jun. 02, 2016.

PWSCC initiation behavior of Alloy 600 under long-term thermal aging and triaxial stress state

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

- International Cooperative Group on Environmentally Assisted Cracking 2016, Qingdao, China, May. 15 ~ May. 20, 2016.

Three-dimensional finite element analysis of pilgering process of hybrid-layer cladding for advanced small modular fast reactor application

- J. Lee, J. H. Lee, J. H. Kim*, Y.H. Shin, I. S. Hwang and R. G. Ballinger

- 2016 International Congress on Advances in Nuclear Power Plants, San Francisco, USA, Apr. 17 ~ Apr. 20, 2016.

In situ investigation of oxide films on zirconium alloy in simulated primary water condition

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

- 2016 International Congress on Advances in Nuclear Power Plants, San Francisco, USA, Apr. 17 ~ Apr. 20, 2016.

Simplified and generalized model of irradiation sink development of aluminum in research reactors

- S. I. Choi, G. -G. Lee, J. Kwon and J. H. Kim*

- 2015 Advances in Materials and Processing Technologies, Madrid, Spain, Dec. 14 ~ Dec. 27, 2015.

Electrocatalytic Activation Behavior of a Ni-P/TiO2 nanocomposite thin film in high-temperature alkaline water

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

- 4th Nano Today Conference, Dubai, UAE, Dec. 6 ~ Dec. 10, 2015.

Crack Growth Rate Measurement of As-received and Warm-rolled 316L Austenitic Stainless Steel in Primary Water Condition of Pressurized Water Reactor

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

- 3rd International Conference on Materials and Reliability, Jeju, Korea, Nov. 23 ~ Nov. 25, 2015.

Effects of thermal aging on PWSCC initiation susceptibility of Alloy 600

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

- 3rd International Conference on Materials and Reliability, Jeju, Korea, Nov. 23 ~ Nov. 25, 2015.

In situ Raman Spectroscopic Analysis of Oxidation Behavior of Zirconium Alloy in Primary Water Condition

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

- 3rd International Conference on Materials and Reliability, Jeju, Korea, Nov. 23 ~ Nov. 25, 2015.

Multi-scale modeling of irradiation effect on iron based alloy as structural materials

- K. B. Ko, S. I. Choi and J. H. Kim*

- The 12th International Symposium on Fusion Nuclear Technology, Jeju, Korea, Sep. 14 ~ Sep. 18, 2015.

The Analysis of microstructure and grain orientation of thermally-aged Alloy 600

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

- 2015 Environmental Degradation of Materials in Nuclear Power Plants - Water Reactors, Ottawa, Ontario, Canada, Aug. 9 ~ Aug. 13, 2015.

In-situ Raman Spectroscopic Analysis of Oxidation Behavior of Alloy 182 in Primary Water Condition

- T. Kim, K.J. Choi, S.C. Yoo, J-D. Hong, C. Chang, J. Xu, T. Shoji and J. H. Kim*

- 2015 Environmental Degradation of Materials in Nuclear Power Plants - Water Reactors, Ottawa, Ontario, Canada, Aug. 9 ~ Aug. 13, 2015.

High-temperature Corrosion Characteristics of Nano-structured Coatings in Secondary System of Nuclear Power Plants

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

- 2015 Environmental Degradation of Materials in Nuclear Power Plants - Water Reactors, Ottawa, Ontario, Canada, Aug. 9 ~ Aug. 13, 2015.

Crack growth rate measurement of warm rolled F316L austenitic stainless steel in primary water condition

- K. J. Choi, S. C. Yoo, S. Kim, M. J. Choi, S. S. Hwang and J. H. Kim*

- ASME 2015 Pressure Vessels & Piping Conference, Boston, Massachusetts, USA, Jul. 19 ~ Jul. 23, 2015.

High-temperature Corrosion Characteristics of Nano-structured Coatings in Secondary System of Nuclear Power Plants

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

- 22th ECS Meeting, Chicago, Illinois, US, May 24 ~ May 28, 2015.

Carbon Activity Measurement by using Ferrite iron Foil and Carburization/ Decarburization Modeling of FMS in Liquid Sodium Environment at 550℃

- S. H. Shin, J. H. Lee, J. K. Lee and J. H. Kim

- 2015 International Congress on Advances in Nuclear Power Plants, Nice, France, May 3 ~ May 6, 2015.

Corrosion Behavior of Surface Treated Ferritic/Martensitic Steel in Liquid Sodium Environment

- J. H. Lee, S. H. Shin, J. K. Lee and J. H. Kim

- 2015 International Congress on Advances in Nuclear Power Plants, Nice, France, May 3 ~ May 6, 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.

Effect of alloy element on the irradiation hardening in aluminum structure materials

- S. I. Choi 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, Nov. 2 ~ Nov. 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, Nov. 2 ~ Nov. 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-structured 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, Aug. 31 ~ Sep. 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, Jul. 20 ~ Jul. 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, Jul. 20 ~ Jul. 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, Jun. 15 ~ Jun. 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, Jun. 15 ~ Jun. 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, Jun. 15 ~ Jun. 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, Jun. 15 ~ Jun. 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, Jun. 15 ~ Jun. 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, Aug. 11 ~ Aug. 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, Jul. 29 ~ Aug. 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, Apr. 14 ~ Apr. 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, Apr. 14 ~ Apr. 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, Mar. 4 ~ Mar. 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, Jul. 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, Jul. 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, Jun. 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, Jun. 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, Jun. 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, Jun. 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, Jun. 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, Jun. 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, Jul. 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, Jun. 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, Apr. 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, Nov. 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, Aug. 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., Nov. 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., Nov. 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, Jul. 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, Jul. 27 ~ Aug. 1, 1997.