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eBook Chapter

Retrospective Dosimetry Analysis of Top Support Plug Samples from Scrap Surveillance Capsule Material for Qualifying Calculations in the Extended Beltline Region of PWRS

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2018
ISBN: 978-0-8031-7661-4
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eBook Chapter

Supplemental Surveillance Capsule Application for Optimized Power Reactor, OPR1000, in Korea

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2018
ISBN: 978-0-8031-7661-4
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eBook Chapter

Methodology Qualification for the 3D RAPTOR-M3G Discrete Ordinates Transport Code on Traditional Beltline

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2018
ISBN: 978-0-8031-7661-4
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eBook Chapter

Korean RPV Surveillance Programs

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2018
ISBN: 978-0-8031-7651-5
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eBook Chapter

Neutron Flux Reduction Programs for Reactor Pressure Vessel of Korea Nuclear Unit 1

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2012
ISBN: 978-0-8031-7536-5
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Journal Articles

Neutron Flux Reduction Programs for Reactor Pressure Vessel of Korea Nuclear Unit 1

Choon Sung Yoo, Byoung Chul Kim
Journal: Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. May 2012, 9(5): 1–10.
https://doi.org/10.1520/JAI104176
Published Online: July 17, 2012
View Article titled, Neutron Flux Reduction Programs for Reactor Pressure Vessel of Korea Nuclear Unit 1
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Proceedings Papers

Fast Neutron Reduction Techniques for Plant Lifetime Extension

Choon Sung Yoo, Byoung Chul Kim, Tae Je Kwon
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 83-87, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25371
https://doi.org/10.1115/PVP2010-25371
View Paper titled, Fast Neutron Reduction Techniques for Plant Lifetime Extension
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Topics: Neutrons, Irradiation (Radiation exposure), Pressurized water reactors, Reactor vessels, Thermal shock, Transients (Dynamics), Vessels, Cycles, Fluence (Radiation measurement), Fracture (Materials)
Proceedings Papers

Crack Growth Analysis in Alloy 82/182 Butt Weld by Using the Finite Element Alternating Method

Maan-Won Kim, Young-Jong Kim, Byoung Chul Kim
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 587-592, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-78039
https://doi.org/10.1115/PVP2009-78039
View Paper titled, Crack Growth Analysis in Alloy 82/182 Butt Weld by Using the Finite Element Alternating Method
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Topics: Finite element analysis, Fracture (Materials), Indium alloys, Alloys, Welded joints, Welding, Nozzles, Pressurized water reactors, Stress, Crack propagation
Proceedings Papers

Effect of Heat-Up Transient Condition on the Thermal Stratification in Nuclear Power Plant Surgeline

Young-Jong Kim, Maan-Won Kim, Eunmi Ko, Jae-Gon Lee, Byoung Chul Kim
Proc. ASME. PVP2009, Volume 4: Fluid-Structure Interaction, 99-104, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-78041
https://doi.org/10.1115/PVP2009-78041
View Paper titled, Effect of Heat-Up Transient Condition on the Thermal Stratification in Nuclear Power Plant Surgeline
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Topics: Heat, Nuclear power stations, Thermal stratification, Transients (Dynamics), Fluid structure interaction, Finite element model, Flow (Dynamics), Surges, Fatigue, Numerical analysis
Proceedings Papers

The Fluence Prediction of Reactor Pressure Vessel Materials Due to Neutron Irradiation by Ultrasonic Characteristic Analysis

Sam Lai Lee, Byoung Chul Kim, Kee Ok Chang
Proc. ASME. PVP2002, Fatigue, Fracture and Damage Analysis, Volume 1, 137-141, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1343
https://doi.org/10.1115/PVP2002-1343
View Paper titled, The Fluence Prediction of Reactor Pressure Vessel Materials Due to Neutron Irradiation by Ultrasonic Characteristic Analysis
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Topics: Fluence (Radiation measurement), Irradiation (Radiation exposure), Neutrons, Reactor vessels, Metals