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Proceedings Papers

Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals

Dong-Hyeon Kwak, Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui Jang

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A049, July 17–22, 2022

Paper No: PVP2022-84936

DOI: https://doi.org/10.1115/PVP2022-84936

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Topics: Compression, Finite element analysis, Irradiation (Radiation exposure), Reactor vessels, Stainless steel, Dislocation density, Materials properties, Stress-strain curves, Boundary-value problems, Constitutive equations

Journal Articles

EPFM Analyses of a Complex Crack in Dissimilar Metal Welded Pipes

Ji-Hoon Kang, Belal Almomani, Yoon-Suk Chang

J. Pressure Vessel Technol. February 2022, 144(1): 011505.

Paper No: PVT-20-1288

DOI: https://doi.org/10.1115/1.4052398

Published Online: October 8, 2021

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Topics: Finite element analysis, Fracture (Materials), Pipes, Tension, Metals, Pressure, Materials properties, Displacement

Proceedings Papers

Comparative Stress Analyses of Dropped Spent Nuclear Fuel Assembly in a Prototypal Cask

Sae-Han-Sol Kang, Dong-Hyun Kim, Yoon-Suk Chang, Sang-Hwan Lee

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A107, August 3, 2020

Paper No: PVP2020-21510

DOI: https://doi.org/10.1115/PVP2020-21510

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Topics: Finite element analysis, Manufacturing, Spent nuclear fuels, Stress analysis (Engineering)

Proceedings Papers

Mechanical Properties of Ion-Irradiated Stainless Steel Determined by Nanoindentation Tests and Finite Element Analyses

Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui Jang

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A104, August 3, 2020

Paper No: PVP2020-21507

DOI: https://doi.org/10.1115/PVP2020-21507

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Topics: Finite element analysis, Irradiation (Radiation exposure), Mechanical properties, Nanoindentation, Stainless steel

Proceedings Papers

Integrity Assessment of Cables Under Postulated Electrical Fire Accidents in a Zero-Power Research Reactor

Jae-Min Jyung, Yoon-Suk Chang

Proc. ASME. PVP2019, Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Symposium and 27th Annual Student Paper Competition; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD), V005T09A005, July 14–19, 2019

Paper No: PVP2019-93340

DOI: https://doi.org/10.1115/PVP2019-93340

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Topics: Accidents, Cables, Fire, Control rooms, Damage, Engineering standards, Hazard analysis, Heat flux, Nuclear power stations, Safety

Proceedings Papers

Investigation of Blast Wave Effects on Containment Wall and Steam Generator

Tae Jin Kim, Yoon-Suk Chang

Proc. ASME. PVP2018, Volume 5: High-Pressure Technology; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Rudy Scavuzzo Student Paper Symposium and 26th Annual Student Paper Competition, V005T10A005, July 15–20, 2018

Paper No: PVP2018-84325

DOI: https://doi.org/10.1115/PVP2018-84325

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Topics: Boilers, Containment, Waves, Damage, Failure, Finite element analysis, Fluids, High temperature, Nuclear power stations, Pipes

Proceedings Papers

Assessment of Aircraft Crash to Containment and its Effects on Reactor Cavity and Major Components

Jae Min Sim, Yoon-Suk Chang

Proc. ASME. PVP2017, Volume 5: High-Pressure Technology; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); SPC Track for Senate, V005T11A018, July 16–20, 2017

Paper No: PVP2017-65746

DOI: https://doi.org/10.1115/PVP2017-65746

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Topics: Aircraft, Cavities, Containment, Stress, Damage, Nuclear power stations, Reinforced concrete, Cracking (Materials), Earthquakes, Finite element analysis

Proceedings Papers

Structural Integrity Assessment of RPV Under Severe Accident Conditions With Creep Constants Correlation

Tae Hyun Kim, Yoon-Suk Chang, Bong-Sang Lee

Proc. ASME. PVP2016, Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Symposium and 24th Annual Student Paper Competition; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Electric Power Research Institute (EPRI) Creep Fatigue Workshop, V005T09A019, July 17–21, 2016

Paper No: PVP2016-63232

DOI: https://doi.org/10.1115/PVP2016-63232

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Topics: Accidents, Creep, Numerical analysis, Reactor vessels, Cooling, Damage, Deformation, Failure, High temperature, Melting

Proceedings Papers

Reactor Cavity Analysis Under Steam Explosive Conditions by TNT Model

Seung-Huyn Kim, Yoon-Suk Chang, Yong-Jin Cho

Paper No: PVP2016-63224

DOI: https://doi.org/10.1115/PVP2016-63224

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Topics: Cavities, Explosives, Steam, Explosions, Cavity walls, Coolants, Cooling, Finite element analysis, Fracture (Materials), Fuels

Proceedings Papers

Structural Assessment of Main Steam Line and Containment Building Under Steam Explosion Conditions

Seung-Huyn Kim, Yoon-Suk Chang, Sungchu Song, Yong-Jin Cho

Proc. ASME. PVP2015, Volume 3: Design and Analysis, V003T03A014, July 19–23, 2015

Paper No: PVP2015-45169

DOI: https://doi.org/10.1115/PVP2015-45169

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Topics: Containment buildings, Explosions, Steam, Failure, Stress, Boilers, Cavities, Concretes, Containment, Coolants

Proceedings Papers

Crack Initiation and Growth Simulation for CRDM Nozzles by eXtended Finite Element Method

Sung-Jun Lee, Yoon-Suk Chang

Proc. ASME. PVP2015, Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Competition and 23rd Annual Student Paper Competition; ASME NDE Division, V005T09A002, July 19–23, 2015

Paper No: PVP2015-45172

DOI: https://doi.org/10.1115/PVP2015-45172

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Topics: Finite element methods, Fracture (Materials), Nozzles, Simulation, Damage, Metals, Nuclear power stations, Stress, Stress corrosion cracking, Uncertainty

Proceedings Papers

Structural Assessment of Reactor Pressure Vessel Under Core Melting Conditions

Seung-Hyun Kim, Yoon-Suk Chang

Proc. ASME. PVP2013, Volume 5: High-Pressure Technology; ASME NDE Division; Rudy Scavuzzo Student Paper Symposium, V005T11A015, July 14–18, 2013

Paper No: PVP2013-97407

DOI: https://doi.org/10.1115/PVP2013-97407

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Topics: Melting, Reactor vessels, Stress, Accidents, Cooling, Countermeasures, Damage, Numerical analysis, Power stations, Safety

Proceedings Papers

Assessment of J-Integrals for Surface Cracks in a Weld Metal

Young-Chul Park, Jae-Uk Jeong, Jae-Boong Choi, Yoon-Suk Chang, Sung-Woo Kim, Hong-Pyo Kim

Proc. ASME. PVP2012, Volume 3: Design and Analysis, 13-16, July 15–19, 2012

Paper No: PVP2012-78441

DOI: https://doi.org/10.1115/PVP2012-78441

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Topics: Metals, Surface cracks, Stress, Fracture (Materials), Stress corrosion cracking, Water, Finite element analysis, Nuclear power stations, Reactor vessels, Shapes

Proceedings Papers

Helical Steam Generator Tubes Containing Crack Under External Pressure: A Review of Applicability for Existing Integrity Evaluation Method

Tae-Young Ryu, Han-Beom Seo, Jong-Min Kim, Jae-Boong Choi, Young-Jin Kim, Yoon-Suk Chang, Jong-Wook Kim, Sang-Yun Park

Proc. ASME. PVP2011, Volume 5: High-Pressure Technology; Nondestructive Evaluation; Nuclear Engineering, 347-352, July 17–21, 2011

Paper No: PVP2011-57588

DOI: https://doi.org/10.1115/PVP2011-57588

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Topics: Boilers, Evaluation methods, External pressure, Fracture (Materials), Fracture mechanics, Pipes, Pressure, Stress, Design, Failure

Proceedings Papers

Assessment of Interaction Effect Between Two Aligned Surface Cracks in Elbows Subjected to Internal Pressure

Han-Beom Seo, Jae-Boong Choi, Young-Jin Kim, Yoon-Suk Chang, Hyun-Su Kim

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 113-118, July 18–22, 2010

Paper No: PVP2010-25604

DOI: https://doi.org/10.1115/PVP2010-25604

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Topics: Pressure, Surface cracks, Fracture (Materials), Fitness-for-service, Pipes, ASME Standards, Engineering standards, Finite element analysis, Plates (structures), Power stations

Proceedings Papers

A Numerical Study on Mock-Up Downsizing to Predict Residual Stresses at CRDM Welds

Ik-Joong Kim, Jae-Uk Jeong, Jae-Boong Choi, Young-Jin Kim, Sung-Woo Kim, Hong-Pyo Kim, Yoon-Suk Chang

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 107-112, July 18–22, 2010

Paper No: PVP2010-25596

DOI: https://doi.org/10.1115/PVP2010-25596

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Topics: Residual stresses, Welded joints, Finite element analysis, Stress, Welding, Geometry, Nuclear power stations, Piping systems, Process simulation, Stress corrosion cracking

Proceedings Papers

Fracture Toughness Estimation of Miniature Specimens by Considering Geometry Effects

Shin-Beom Choi, Young-Jin Kim, Yoon-Suk Chang

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 5, 521-525, July 18–22, 2010

Paper No: PVP2010-25588

DOI: https://doi.org/10.1115/PVP2010-25588

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Topics: Fracture toughness, Geometry, Finite element analysis, Fracture (Materials), Stress, Carbon steel, Reactor vessels, Safety, Surveillance, Temperature

Proceedings Papers

FSI-Based Assessment of FAC-Caused Wall Thinned Piping

Sun-Hye Kim, Yoon-Suk Chang, Young-Jin Kim

Proc. ASME. PVP2009, Volume 5: High Pressure Technology; Nondestructive Evaluation Division; Student Paper Competition, 359-363, July 26–30, 2009

Paper No: PVP2009-77353

DOI: https://doi.org/10.1115/PVP2009-77353

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Topics: Fluid structure interaction, Pipes, Flow (Dynamics), Stress, Failure, Accidents, Computational fluid dynamics, Corrosion, Geometry, Nuclear power stations

Proceedings Papers

A Residual Stress Analysis of a Corner Crack in Pressurizer Vent Nozzle Penetration Weld

Sang-Min Lee, Jeong-Soon Park, Young-Hwan Choi, Hae-Dong Chung, Doo-Ho Cho, Yoon-Suk Chang, Young-Jin Kim

Proc. ASME. PVP2009, Volume 1: Codes and Standards, 317-322, July 26–30, 2009

Paper No: PVP2009-77613

DOI: https://doi.org/10.1115/PVP2009-77613

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Topics: Corners (Structural elements), Fracture (Materials), Nozzles, Stress analysis (Engineering), Vents, Stress, Welding, Metals, Alloy steel, Electricity (Physics)

Proceedings Papers

The Pressure-Temperature Limit Curve of System-Integrated Modular Advanced Reactor Against Nonductile Failure

Yoon-Suk Chang, Hyuk-Soo Chang, Sang-Min Lee, Jae-Boong Choi, Young-Jin Kim, Jin-Su Kim, Hae-Dong Chung, Kwang-Won Seul

Proc. ASME. PVP2007, Volume 3: Design and Analysis, 381-388, July 22–26, 2007

Paper No: PVP2007-26837

DOI: https://doi.org/10.1115/PVP2007-26837

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Topics: Failure, Pressure, Temperature, Design, ASME Standards, Finite element analysis, Nuclear reactor coolants, Seawater, Surface cracks

Journal citation

NARROW

Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals

EPFM Analyses of a Complex Crack in Dissimilar Metal Welded Pipes

Comparative Stress Analyses of Dropped Spent Nuclear Fuel Assembly in a Prototypal Cask

Mechanical Properties of Ion-Irradiated Stainless Steel Determined by Nanoindentation Tests and Finite Element Analyses

Integrity Assessment of Cables Under Postulated Electrical Fire Accidents in a Zero-Power Research Reactor

Investigation of Blast Wave Effects on Containment Wall and Steam Generator

Assessment of Aircraft Crash to Containment and its Effects on Reactor Cavity and Major Components

Structural Integrity Assessment of RPV Under Severe Accident Conditions With Creep Constants Correlation

Reactor Cavity Analysis Under Steam Explosive Conditions by TNT Model

Structural Assessment of Main Steam Line and Containment Building Under Steam Explosion Conditions

Crack Initiation and Growth Simulation for CRDM Nozzles by eXtended Finite Element Method

Structural Assessment of Reactor Pressure Vessel Under Core Melting Conditions

Assessment of J-Integrals for Surface Cracks in a Weld Metal

Helical Steam Generator Tubes Containing Crack Under External Pressure: A Review of Applicability for Existing Integrity Evaluation Method

Assessment of Interaction Effect Between Two Aligned Surface Cracks in Elbows Subjected to Internal Pressure

A Numerical Study on Mock-Up Downsizing to Predict Residual Stresses at CRDM Welds

Fracture Toughness Estimation of Miniature Specimens by Considering Geometry Effects

FSI-Based Assessment of FAC-Caused Wall Thinned Piping

A Residual Stress Analysis of a Corner Crack in Pressurizer Vent Nozzle Penetration Weld

The Pressure-Temperature Limit Curve of System-Integrated Modular Advanced Reactor Against Nonductile Failure

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