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Proceedings Papers

Formula for Estimation of Effective Applied Load at Cracked Section Considering Compliance Change and its Application Under Dynamic Loading Conditions

Yeji Kim, Young-Jin Oh, Yun-Jae Kim, Il-Soon Hwang
Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A053, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84877
https://doi.org/10.1115/PVP2018-84877
View Paper titled, Formula for Estimation of Effective Applied Load at Cracked Section Considering Compliance Change and its Application Under Dynamic Loading Conditions
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Topics: Dynamic testing (Materials), Stress, Fracture (Materials), Pipes, Piping systems, Accidents, Deformation, Design, Euler-Bernoulli beam theory, Finite element model
Proceedings Papers

Power Maximization of Fully Passive Lead-Bismuth Eutectic Cooled Small Modular Reactor

Jaehyun Cho, Yong-Hoon Shin, Il Soon Hwang
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T16A010, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30995
https://doi.org/10.1115/ICONE22-30995
View Paper titled, Power Maximization of Fully Passive Lead-Bismuth Eutectic Cooled Small Modular Reactor
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Topics: Small modular reactors, Design, Safety, Cooling, Economics , Pressurized water reactors, Combustion, Coolants, Nuclear power stations, Optimization
Proceedings Papers

Cross-Comparison of One-Dimensional Thermal-Hydraulic Codes on Natural Circulation Analysis of NACIE Loop Test for Lead-Alloy Cooled Advanced Nuclear Energy Systems (LACANES)

Yong-Hoon Shin, Il Soon Hwang, Massimiliano Polidori, Paride Meloni, Vincenzo Casamassima, Stephanie Cornet, Luciana Barucca, Davide Balestri, Ming Jin, Mathias Viellieber
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T16A007, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30716
https://doi.org/10.1115/ICONE22-30716
View Paper titled, Cross-Comparison of One-Dimensional Thermal-Hydraulic Codes on Natural Circulation Analysis of NACIE Loop Test for Lead-Alloy Cooled Advanced Nuclear Energy Systems (LACANES)
Open the PDF for Cross-Comparison of One-Dimensional Thermal-Hydraulic Codes on Natural Circulation Analysis of NACIE Loop Test for Lead-Alloy Cooled Advanced Nuclear Energy Systems (LACANES) in another window
Topics: Lead alloys, Nuclear power, Alloys, Collaboration, Errors, Flow (Dynamics), Forced convection, Fukushima nuclear disaster, Japan, 2011, Generation IV reactors, Heat transfer
Journal Articles

A Probabilistic Environmentally Assisted Cracking Model for Steam Generator Tubes

Tae Hyun Lee, Jae Young Yoon, Hyo On Nam, Il Soon Hwang
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2015, 137(2): 021204.
Paper No: PVT-14-1007
https://doi.org/10.1115/1.4027641
Published Online: October 15, 2014
View Article titled, A Probabilistic Environmentally Assisted Cracking Model for Steam Generator Tubes
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Topics: Boilers, Fracture (Materials), Fracture (Process)
Proceedings Papers

On-Line Monitoring of Cracks in Piping Weldment Using Array Probed Direct Current Potential Drop

Jae Young Yoon, Ye Ji Kim, Il Soon Hwang, L. Ayers, M. Short, L. Bromberg, R. G. Ballinger
Proc. ASME. PVP2013, Volume 5: High-Pressure Technology; ASME NDE Division; Rudy Scavuzzo Student Paper Symposium, V005T10A011, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97688
https://doi.org/10.1115/PVP2013-97688
View Paper titled, On-Line Monitoring of Cracks in Piping Weldment Using Array Probed Direct Current Potential Drop
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Topics: Fracture (Materials), Pipes, Finite element analysis, Design, Leakage, Licensing, Nuclear power stations, Probes, Reliability, Signals
Proceedings Papers

URANUS: Korean Lead-Bismuth Cooled Small Modular Fast Reactor Activities

Sungyeol Choi, Il Soon Hwang, Jae Hyun Cho, Chun Bo Shim
Proc. ASME. SMR2011, ASME 2011 Small Modular Reactors Symposium, 107-112, September 28–30, 2011
Publisher: American Society of Mechanical Engineers
Paper No: SMR2011-6650
https://doi.org/10.1115/SMR2011-6650
View Paper titled, URANUS: Korean Lead-Bismuth Cooled Small Modular Fast Reactor Activities
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Topics: Fast neutron reactors, Accidents, Earthquakes, Cooling, Cooling systems, Design, Electricity (Physics), Fuels, Heat, Nuclear power
Proceedings Papers

Inspection of Piping Wall Loss With Flow Accelerated Corrosion Accelerated Simulation Test

Kyung Ha Ryu, Ji Hak Kim, Il Soon Hwang
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 1233-1241, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25501
https://doi.org/10.1115/PVP2010-25501
View Paper titled, Inspection of Piping Wall Loss With Flow Accelerated Corrosion Accelerated Simulation Test
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Topics: Corrosion, Flow (Dynamics), Inspection, Pipes, Simulation, Carbon steel, Nuclear power stations, Piping systems, Temperature, Water chemistry
Journal Articles

A New Technique for Intergranular Crack Formation in Alloy 600 Steam Generator Tubing

Tae Hyun Lee, Il Soon Hwang, Han Sub Chung, Jang Yul Park
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2008, 130(1): 011403.
https://doi.org/10.1115/1.2826423
Published Online: January 17, 2008
View Article titled, A New Technique for Intergranular Crack Formation in Alloy 600 Steam Generator Tubing
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Topics: Boilers, Finite element analysis, Fracture (Materials), Tubing