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Proceedings Papers

LBB Analysis on Nuclear-Class Pipes of Floating Nuclear Power Stations

Fan Bai, Yong Liu, Xingsheng Lao, Qi Xiao, Zhenxing Zhao, Jun Wu, Can Ma, Wang Wei
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A029, July 22–26, 2018
Paper No: ICONE26-82180
DOI: https://doi.org/10.1115/ICONE26-82180
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Topics: Nuclear power stations, Pipes, Fracture (Materials), Leakage, Design, Drilling, Fatigue, Finite element methods, Fracture mechanics, Leak-before-break
Proceedings Papers

Development of a Crack Opening Displacement Assessment Procedure Considering Change of Compliance at a Crack Part in Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Seiji Yanagihara, Ryosuke Suzuki, Masaaki Matsubara
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A035, July 22–26, 2018
Paper No: ICONE26-82619
DOI: https://doi.org/10.1115/ICONE26-82619
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Topics: Displacement, Fracture (Materials), Pipes, Steel, Thin wall structures, Leakage, Sodium fast reactors, Sodium, Work hardening, Coolants
Proceedings Papers

Research on Algorithm of Sump Level Operator Assisted Support Program for PWR Nuclear Power Plant

Liu Qiaofen, Xiao Sanping, Liu Yu, Liu Xichao, Jiang Xulun
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T04A012, July 22–26, 2018
Paper No: ICONE26-81714
DOI: https://doi.org/10.1115/ICONE26-81714
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Topics: Algorithms, Nuclear power stations, Pressurized water reactors, Leakage flows, Computational methods, Leakage, Leak-before-break, Nuclear reactor coolants, Nuclear reactor safety
Proceedings Papers

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A002, July 22–26, 2018
Paper No: ICONE26-81096
DOI: https://doi.org/10.1115/ICONE26-81096
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Topics: Design, Fracture (Materials), Fracture (Process), Boilers, Brittle fracture, Brittleness, Failure, In-service inspection, Leak-before-break, Manufacturing
Proceedings Papers

Penetration Jet Impingement Calculation in Engineering Application

Tong Wu, Ying Zhou, Tao Qi
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A022, July 2–6, 2017
Paper No: ICONE25-67096
DOI: https://doi.org/10.1115/ICONE25-67096
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Topics: Drops, Engineering systems and industry applications, Enthalpy, Flashing, Floods, Flow (Dynamics), Fluids, Hazard analysis, Hot water, Jets
Proceedings Papers

Assessment of Choking Flow Models in RELAP5 for Subcooled Choking Flow Through a Small Axial Crack of a Steam Generator Tube

Mark A. Brown, Hung Nguyen, Shripad T. Revankar, Jovica Riznic
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A046, July 2–6, 2017
Paper No: ICONE25-67371
DOI: https://doi.org/10.1115/ICONE25-67371
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Topics: Boilers, Flow (Dynamics), Fracture (Materials), Subcooling, Nuclear power stations, Coolants, Accidents, Hydraulics, Leakage, Leak-before-break
Proceedings Papers

Choking Flow of Subcooled Liquid in Steam Generator Tube Wall Cracks

Ram Anand Vadlamani, Shripad T. Revankar, Jovica R. Riznic
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A028, July 7–11, 2014
Paper No: ICONE22-30256
DOI: https://doi.org/10.1115/ICONE22-30256
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Topics: Boilers, Flow (Dynamics), Fracture (Materials), Subcooling, Coolants, Rupture, Water, Accidents, Design, Equilibrium (Physics)
Proceedings Papers

A Prediction of the Leakage Through Cracks for Leak Before Break

Jing Zhang, Yingwei Wu, Lei Ding, Hongwei Qiao, Pengzhou Li, Guanghui Su, Suizheng Qiu, Wenxi Tian
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A018, July 7–11, 2014
Paper No: ICONE22-30708
DOI: https://doi.org/10.1115/ICONE22-30708
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Topics: Fracture (Materials), Leakage, Leak-before-break, Flow (Dynamics), Surface roughness, Corners (Structural elements), Displacement, Enthalpy, Fluids, Friction
Proceedings Papers

Analysis of Dynamic Effects Associated With Postulated Breaks of Piping

Manqing Qin, Xinghua Li, Jicheng Zhao
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A016, July 29–August 2, 2013
Paper No: ICONE21-15273
DOI: https://doi.org/10.1115/ICONE21-15273
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Topics: Pipes, Stress, Computer simulation, Defense industry, Energy budget (Physics), Hydrodynamics, Leak-before-break, Nuclear design, Piping systems, Regulations
Proceedings Papers

Fracture Mechanic at Design Level for New Reactors

Claude Faidy
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A049, July 29–August 2, 2013
Paper No: ICONE21-16377
DOI: https://doi.org/10.1115/ICONE21-16377
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Topics: Design, Fracture (Materials), Accidents, Brittleness, Corrosion, Emergencies, Failure mechanisms, Fatigue, Leak-before-break, Phase transition temperature
Proceedings Papers

Experiments on Choking Flow of Subcooled Liquid Through a Simulated Steam Generator Tube Crack

Brian Wolf, Shripad T. Revankar, Jovica R. Riznic
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 41-50, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54080
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54080
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Topics: Boilers, Flow (Dynamics), Fracture (Materials), Subcooling, Flashing, Lasers, Leakage, Leak-before-break, Pressure, Tubing
Proceedings Papers

Effect of Hydrogen Isotope and Concentration on Delayed Hydride Crack Growth Rates in Zr-2.5Nb Pressure Tubes

Gordon K. Shek, Harry Seahra
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 559-569, May 17–21, 2010
Paper No: ICONE18-29786
DOI: https://doi.org/10.1115/ICONE18-29786
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Topics: Fracture (Materials), Hydrogen, Isotopes, Pressure, Zirconium, Temperature, Fracture (Process), Cracking (Materials), Diffusion (Physics), Leakage
Proceedings Papers

Development of Leak Rate Model for Helium Flow in Elliptically Converging Through Wall Crack

Sheng Zhou, Zhengming Zhang, Pierre Lamagnere, Thierry Cadiou, Jean-luc Berton, Marc Grandotto-Biettoli
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 571-576, May 17–21, 2010
Paper No: ICONE18-29814
DOI: https://doi.org/10.1115/ICONE18-29814
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Topics: Flow (Dynamics), Fracture (Materials), Helium, Leakage, Computational fluid dynamics, Geometry, Pressure, Very high temperature reactors, Leak-before-break, Nuclear power stations
Proceedings Papers

VERLIFE - Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs During Operation: Updating and Further Development

Milan Brumovsky
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 463-467, May 17–21, 2010
Paper No: ICONE18-30256
DOI: https://doi.org/10.1115/ICONE18-30256
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Topics: Nuclear power stations, Pipes, Corrosion, Damage, Design, Erosion, Fracture mechanics, In-service inspection, Leak-before-break, Manufacturing
Proceedings Papers

Construction Aspects of the Doel 1 and 2 SGR Projects

Bert Kroes, Edmond Gobert, Xavier Delhaye, Peter Devolder, Michel Sonville
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 111-117, July 12–16, 2009
Paper No: ICONE17-75671
DOI: https://doi.org/10.1115/ICONE17-75671
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Topics: Construction, Containment, Boilers, Pipes, Pressurized water reactors, Coolants, Leak-before-break, Licensing, Manufacturing, Nuclear power stations
Proceedings Papers

French Codes Used for EPR and Comparison With ASME Practices

Claude Faidy
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, 1077-1084, May 11–15, 2008
Paper No: ICONE16-48959
DOI: https://doi.org/10.1115/ICONE16-48959
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Topics: Design, Leak-before-break, Manufacturing, Nuclear power stations, Pressure equipment, Radiation (Physics), Risk, Safety
Proceedings Papers

Considerations for Probabilistic Analyses to Assess Potential Changes to Large-Break LOCA Definition for ECCS Requirements

G. Wilkowski, P. Scott, S. Rahman, D. Rudland, R. Wolterman, P. Krishnaswamy, C. Fairbanks
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 575-582, April 14–18, 2002
Paper No: ICONE10-22659
DOI: https://doi.org/10.1115/ICONE10-22659
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Topics: Emergency core cooling systems, Failure, Pipes, Probability, Pressure, Regulations, Acceptance criteria, Boilers, Containment buildings, Cracking (Materials)
Proceedings Papers

Effects of Dynamic Strain-Aging and Cyclic Loading on Fracture Behavior of Ferritic Steels

K. Linga Murty, Chang-Sung Seok
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 513-518, April 14–18, 2002
Paper No: ICONE10-22151
DOI: https://doi.org/10.1115/ICONE10-22151
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Topics: Fracture (Materials), Steel, Stress, Fracture toughness, Displacement, Radiation (Physics), Work hardening, Ductility, Iron, Light water reactors
Proceedings Papers

Application of a Piping Failure Database to Some Nuclear Safety Issues in Korea

Sun Yeong Choi, Young Hwan Choi, Yeon Ki Chung
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 175-179, April 25–29, 2004
Paper No: ICONE12-49572
DOI: https://doi.org/10.1115/ICONE12-49572
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Topics: Databases, Failure, Pipes, Safety, Fatigue, Feedwater, Inspection, Piping systems, Cooling systems, Corrosion
Proceedings Papers

New French Regulation for NPPs and Code Consequences

Claude Faidy
Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 745-749, July 17–20, 2006
Paper No: ICONE14-89616
DOI: https://doi.org/10.1115/ICONE14-89616
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Topics: Nuclear power stations, Pressure equipment, Design, Leak-before-break, Manufacturing, Radiation (Physics), Risk, Safety