Search Results | ASME Digital Collection

1-15 of 15

Sort by

Sort Order Select

Proceedings Papers

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

Yupeng Cao, Yinbiao He, Yifeng Huang, Binxi Wang, Yan Yu, Hui Li, Hu Hui

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A003, August 4–5, 2020

Paper No: ICONE2020-16261

DOI: https://doi.org/10.1115/ICONE2020-16261

View Paper

Topics: Embrittlement, Irradiation (Radiation exposure), Metals, Forging, Mechanical properties, China, Damage, Design, Fluence (Radiation measurement), Fracture toughness

Proceedings Papers

Evaluation of Irradiation Embrittlement of the Chinese RPV Steels

Yupeng Cao, Yinbiao He, Binxi Wang, Yifeng Huang, Hui Li, Yan Yu, Hu Hui

Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A028, July 14–19, 2019

Paper No: PVP2019-93615

DOI: https://doi.org/10.1115/PVP2019-93615

View Paper

Topics: Embrittlement, Irradiation (Radiation exposure), Steel, Forging, China, Fluence (Radiation measurement), Fracture toughness, Mechanical properties, Notch testing, Nuclear power stations

Proceedings Papers

Creep Evaluation for a PWR Reactor Pressure Vessel Lower Head Under Severe Accident Conditions Considering Sustained Internal Pressure

YongJian Gao, Ming Cao, YinBiao He

Proc. ASME. PVP2018, Volume 3B: Design and Analysis, V03BT03A052, July 15–20, 2018

Paper No: PVP2018-84375

DOI: https://doi.org/10.1115/PVP2018-84375

View Paper

Topics: Accidents, Creep, Pressure, Pressurized water reactors, Reactor vessels, Nuclear power stations, Damage, Failure, Failure mechanisms, Finite element model

Proceedings Papers

Constraint Assessment for Cruciform Specimens With a Semi-Elliptical Crack

Yupeng Cao, Guian Qian, Yinbiao He, Yuh J. Chao

Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A034, July 15–20, 2018

Paper No: PVP2018-84427

DOI: https://doi.org/10.1115/PVP2018-84427

View Paper

Topics: Fracture (Materials), Stress, Fracture toughness, Materials properties, Engineering simulation, Finite element analysis, Finite element model, Hardening, Mechanical properties, Simulation

Journal Articles

Constraint Assessment for Specimens Tested Under Uniaxial and Biaxial Loading Conditions

Yupeng Cao, Guian Qian, Yinbiao He, Markus Niffenegger, Yuh J. Chao

J. Pressure Vessel Technol. June 2018, 140(3): 031401.

Paper No: PVT-17-1150

DOI: https://doi.org/10.1115/1.4039346

Published Online: April 3, 2018

View Article

Topics: Fracture (Materials), Stress, Finite element analysis, Fracture toughness

Proceedings Papers

Constraint Assessment for Specimens Tested Under Uniaxial and Biaxial Loading Conditions

Yupeng Cao, Guian Qian, Yinbiao He, Yuh J. Chao, Markus Niffenegger

Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A049, July 16–20, 2017

Paper No: PVP2017-65979

DOI: https://doi.org/10.1115/PVP2017-65979

View Paper

Topics: Design, Engineering simulation, Finite element analysis, Fracture (Materials), Fracture toughness, Materials properties, Reactor vessels, Simulation, Stress, Tension

Proceedings Papers

Numerical Research of CAP1700 IHP Cooling by Natural Convection

Xingliang Zhang, Hao Yu, Wei Zhang, Yinbiao He

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A074, July 2–6, 2017

Paper No: ICONE25-66942

DOI: https://doi.org/10.1115/ICONE25-66942

View Paper

Topics: Cooling, Natural convection, Design, Temperature, Computational fluid dynamics, Convection, Fans, Flow (Dynamics), High temperature

Proceedings Papers

Further Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Yupeng Cao, Yinbiao He, Hui Hu, Hui Li

Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A039, July 17–21, 2016

Paper No: PVP2016-63799

DOI: https://doi.org/10.1115/PVP2016-63799

View Paper

Topics: Reactor vessels, Thermal shock, Fracture (Materials), Fracture mechanics, Design, Nuclear engineering, Nuclear power stations, Phase transition temperature, Transients (Dynamics)

Proceedings Papers

Structural Integrity Research for Reactor Pressure Vessel Under In-Vessel Retention of a Core Melt

Yongjian Gao, Yinbiao He, Ming Cao, Yuebing Li, Shiyi Bao, Zengliang Gao

Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A005, June 26–30, 2016

Paper No: ICONE24-60092

DOI: https://doi.org/10.1115/ICONE24-60092

View Paper

Topics: Reactor vessels, Vessels, Finite element analysis, Creep, Materials properties, Nuclear power stations, Pressure, Accidents, Leakage, Load bearing capacity

eBook Chapter

Application of Nuclear and Non-Nuclear Standards in China

Book: Global Applications of the ASME Boiler & Pressure Vessel Code

Publisher: ASME Press

Published: 2016

DOI: https://doi.org/10.1115/1.861073_ch17

ISBN: 9780791861073

View chapter

PDF

Topics: China

Proceedings Papers

Re-Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Yupeng Cao, Yinbiao He, Hu Hui, Hui Li, Fuzhen Xuan

Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A033, July 19–23, 2015

Paper No: PVP2015-45577

DOI: https://doi.org/10.1115/PVP2015-45577

View Paper

Topics: Reactor vessels, Thermal shock, Accidents, Coolants, Design, Fracture (Materials), Transients (Dynamics), Cladding systems (Building), Nuclear engineering, Nuclear power stations

Proceedings Papers

Structural Integrity of a Reactor Vessel Lower Head Under In-Vessel Steam Explosion Loads

Guohong Xue, Yinbiao He, Ming Cao, Hao Yu, Yongjian Gao

Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T15A013, July 29–August 2, 2013

Paper No: ICONE21-15831

DOI: https://doi.org/10.1115/ICONE21-15831

View Paper

Topics: Blast effect, Reactor vessels, Steam, Vessels, Cooling, Explosions, Explosives, Pressure, Water, Accidents

Proceedings Papers

Proposed Improvements of the ASME B&PV Code and Future Directions of CIWG

Jinquan Yan, Yinbiao He, Gang Li, Hao Yu

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A005, July 29–August 2, 2013

Paper No: ICONE21-15404

DOI: https://doi.org/10.1115/ICONE21-15404

View Paper

Topics: Acceptance criteria, ASME Standards, China, Construction, Design, Fatigue, Hydrostatic testing, Nuclear industry, Nuclear power stations, Power stations

Proceedings Papers

Research and Analysis on Damage of Fretting Wear and Fretting Fatigue for Components in NPPs

Dong Ning, Min Zhang, Yongchen Xie, Yinbiao He, Weida Yao

Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 633-640, May 11–15, 2008

Paper No: ICONE16-48516

DOI: https://doi.org/10.1115/ICONE16-48516

View Paper

Topics: Damage, Fatigue, Nuclear power stations, Wear

Proceedings Papers

R&D and Its Application to NPPs on Aging Management and Lifetime Assessment

Yikang Dou, Yinbiao He, Xuelian Xu, Yongcheng Xie

Proc. ASME. PVP2006-ICPVT-11, Volume 7: Operations, Applications, and Components, 49-55, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-93186

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93186

View Paper

Topics: Nuclear power stations, China, Design, Regulations, Nuclear engineering, Safety

Journal citation

NARROW

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

Evaluation of Irradiation Embrittlement of the Chinese RPV Steels

Creep Evaluation for a PWR Reactor Pressure Vessel Lower Head Under Severe Accident Conditions Considering Sustained Internal Pressure

Constraint Assessment for Cruciform Specimens With a Semi-Elliptical Crack

Constraint Assessment for Specimens Tested Under Uniaxial and Biaxial Loading Conditions

Constraint Assessment for Specimens Tested Under Uniaxial and Biaxial Loading Conditions

Numerical Research of CAP1700 IHP Cooling by Natural Convection

Further Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Structural Integrity Research for Reactor Pressure Vessel Under In-Vessel Retention of a Core Melt

Application of Nuclear and Non-Nuclear Standards in China

Re-Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Structural Integrity of a Reactor Vessel Lower Head Under In-Vessel Steam Explosion Loads

Proposed Improvements of the ASME B&PV Code and Future Directions of CIWG

Research and Analysis on Damage of Fretting Wear and Fretting Fatigue for Components in NPPs

R&D and Its Application to NPPs on Aging Management and Lifetime Assessment

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only