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Proceedings Papers

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Yubin Zhang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A011, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64737
https://doi.org/10.1115/ICONE28-64737
View Paper titled, Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel
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Topics: Numerical analysis, Reactor vessels, Thermal shock, Accidents, Computational fluid dynamics, Computer software, Coolants, Flow (Dynamics), Mechanical structures, Nozzles
Proceedings Papers

Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings

Nak-Kyun Cho, Pavitra Bansal, Antony M. Hurst
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16426
https://doi.org/10.1115/ICONE2020-16426
View Paper titled, Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings
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Topics: Boilers, Pressure, Transients (Dynamics), Valves, Pipes, Temperature, Collapse, Engineers, Fatigue, Flow (Dynamics)
Proceedings Papers

Stress Analysis of the Lower Head of Central Measuring Shroud Under Thermal Striping and Thermal Shock Conditions

Shu Zheng, Daogang Lu, Qiong Cao
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A019, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16668
https://doi.org/10.1115/ICONE2020-16668
View Paper titled, Stress Analysis of the Lower Head of Central Measuring Shroud Under Thermal Striping and Thermal Shock Conditions
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Topics: Fatigue analysis, Stress analysis (Engineering), Thermal shock
Proceedings Papers

Thermal Hydraulic Analyses for PTS Evaluation: Comparison of Temperature Fields at RPV Predicted by System TH Code and CFD Code

Pavel Kral, Ladislav Vyskocil
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81007
https://doi.org/10.1115/ICONE26-81007
View Paper titled, Thermal Hydraulic Analyses for PTS Evaluation: Comparison of Temperature Fields at RPV Predicted by System TH Code and CFD Code
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Topics: Computational fluid dynamics, Temperature, Computers, Flow (Dynamics), Nuclear power stations, Testing, Thermal shock
Proceedings Papers

Thermal Hydraulic Analysis of Pressurized Thermal Shock for Loviisa NPP Using Apros Simulation Code

Gintaras Žemulis, Pasi Junninen, Petri Kytömäki
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A051, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81558
https://doi.org/10.1115/ICONE26-81558
View Paper titled, Thermal Hydraulic Analysis of Pressurized Thermal Shock for Loviisa NPP Using Apros Simulation Code
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Topics: Nuclear power stations, Simulation, Thermal shock, Safety, Emergencies, Reactor vessels, Embrittlement, Heat, Boundary-value problems, Cooling
Proceedings Papers

Pressurized Thermal Shock (PTS) Transient Scenarios Screening Analysis With TRACE

Roman Mukin, Ivor Clifford, Hakim Ferroukhi, Markus Niffenegger
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A069, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81749
https://doi.org/10.1115/ICONE26-81749
View Paper titled, Pressurized Thermal Shock (PTS) Transient Scenarios Screening Analysis With TRACE
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Topics: Thermal shock, Transients (Dynamics), Nuclear power stations, Vessels, Cooling, Reactor vessels, Accidents, Emergency core cooling systems, Pressure, Pressurized water reactors
Proceedings Papers

Stress and Fatigue Analysis of Thermal Shock for Cladding of Center Measurement Column Lower Head in the Fast Reactor Under Shutdown Condition

Shu Zheng, Daogang Lu, Qiong Cao, Chao Liu, Yunlong Ding, Yi Huang
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A069, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82596
https://doi.org/10.1115/ICONE26-82596
View Paper titled, Stress and Fatigue Analysis of Thermal Shock for Cladding of Center Measurement Column Lower Head in the Fast Reactor Under Shutdown Condition
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Topics: Cladding systems (Building), Fast neutron reactors, Fatigue analysis, Stress, Thermal shock, Fatigue damage, Temperature, Coolants, Damage, Design
Proceedings Papers

RPV Structure Integrity Assessment With Surface Cracks Under PTS

Wei Lu, Zheng He
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A048, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66447
https://doi.org/10.1115/ICONE25-66447
View Paper titled, RPV Structure Integrity Assessment With Surface Cracks Under PTS
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Topics: Surface cracks, Stress, Transients (Dynamics), Fracture toughness, Cladding systems (Building), Fracture (Materials), Stress concentration, Temperature, Cooling, Finite element methods
Proceedings Papers

Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL

Yinsheng Li, Genshichiro Katsumata, Koichi Masaki, Shotaro Hayashi, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Yasuhiro Kanto
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A050, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66468
https://doi.org/10.1115/ICONE25-66468
View Paper titled, Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL
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Topics: Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure), Light water reactors, Neutrons, Nuclear power, Nuclear power stations, Pressure, Reactor vessels
Proceedings Papers

Neutron Embrittlement Analysis of Qinshan 320MWe RPV on OLE

Tao Hongxin, He Yinbiao, Cao Ming, Shen Rui
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A013, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66361
https://doi.org/10.1115/ICONE25-66361
View Paper titled, Neutron Embrittlement Analysis of Qinshan 320MWe RPV on OLE
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Topics: Embrittlement, Neutrons, Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure), Pressurized water reactors, Safety, Service life (Equipment), Fracture mechanics, High pressure (Physics)
Proceedings Papers

Study on Thermal Characteristics of the Regenerative Heat Exchanger

Junping Si, Mingyan Tong, Wenhua Yang, Gang Huang
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A022, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60380
https://doi.org/10.1115/ICONE24-60380
View Paper titled, Study on Thermal Characteristics of the Regenerative Heat Exchanger
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Topics: Heat exchangers, Heat, Cooling, Design, Temperature, Water, Damage, Flow (Dynamics), Fluids, Heat transfer
Proceedings Papers

Design, Optimization and Performance Testing of Self-Healing Tritium Permeation Barriers

Dawei Liu, Tong Zhou, Yan Wang, Jinping Suo
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T14A006, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30678
https://doi.org/10.1115/ICONE22-30678
View Paper titled, Design, Optimization and Performance Testing of Self-Healing Tritium Permeation Barriers
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Topics: Design, Optimization, Testing performance, Coatings, Adhesives, Thermal shock, Cooling, Cycles, Fracture (Materials), Fusion reactors
Proceedings Papers

Experimental Study of the Wall Boundary Layer “Heavy Liquid-Metal Coolant – Constructional Material” as Applied to Fast Reactors

Kirill Makhov, Aleksander V. Beznosov, Tatyana Bokova, Artem Shumilkov, Aleksei Chernysh, Alexander Vladimirovich Knyazev
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A031, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30269
https://doi.org/10.1115/ICONE22-30269
View Paper titled, Experimental Study of the Wall Boundary Layer “Heavy Liquid-Metal Coolant – Constructional Material” as Applied to Fast Reactors
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Topics: Boundary layers, Coolants, Fast neutron reactors, Liquid metals, Particulate matter, Microhardness, Oxide coatings, Steel, Turbulence, Alloys
Proceedings Papers

The Fracture Behavior of Cylinders With Axial Surface Cracks Under Strong Through-Wall Bending Stresses

Yuebing Li, Zengliang Gao, Yuebao Lei
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A034, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15868
https://doi.org/10.1115/ICONE21-15868
View Paper titled, The Fracture Behavior of Cylinders With Axial Surface Cracks Under Strong Through-Wall Bending Stresses
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Topics: Bending (Stress), Cylinders, Fracture (Materials), Surface cracks, Thermal shock
Proceedings Papers

The Computer Measuring and Controlling System for Temperature Field of the Thermal-Shock Test at R1/R2 Test Section in ESPRESSO Loop

Fei Zhao, Chunliang Wu, Fengyang Shen, Chunxing Gu
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A014, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15643
https://doi.org/10.1115/ICONE21-15643
View Paper titled, The Computer Measuring and Controlling System for Temperature Field of the Thermal-Shock Test at R1/R2 Test Section in ESPRESSO Loop
Open the PDF for The Computer Measuring and Controlling System for Temperature Field of the Thermal-Shock Test at R1/R2 Test Section in ESPRESSO Loop in another window
Topics: Computers, Temperature, Thermal shock, Displacement, Shapes, Sodium
Proceedings Papers

Comparison of PTS Guides for Reactor Pressure Vessel Integrity Assessment

Milan Brumovsky
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A007, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15419
https://doi.org/10.1115/ICONE21-15419
View Paper titled, Comparison of PTS Guides for Reactor Pressure Vessel Integrity Assessment
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Topics: Reactor vessels, Fracture mechanics, ASME Standards, Cooling, Emergencies, Materials degradation, Materials properties, Nuclear power stations, Safety, Testing
Proceedings Papers

Effect of Initial and Boundary Conditions on the Formation of Reactor Vessel Pressurized Thermal Shock

Maksym Vyshemirskyi, Aleksander Mazurok, Anatoliy Nosovskyy
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A023, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15992
https://doi.org/10.1115/ICONE21-15992
View Paper titled, Effect of Initial and Boundary Conditions on the Formation of Reactor Vessel Pressurized Thermal Shock
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Topics: Boundary-value problems, Reactor vessels, Thermal shock, Leakage, Nuclear power stations, Boilers, Brittle fracture, Flow (Dynamics), Fluids, Nuclear power
Proceedings Papers

Multi-Scale Thermalhydraulic Analyses Performed in NURESIM and NURISP Projects

D. Bestion, D. Lucas, H. Anglart, B. Niceno, L. Vyskocil
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 581-590, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54891
https://doi.org/10.1115/ICONE20-POWER2012-54891
View Paper titled, Multi-Scale Thermalhydraulic Analyses Performed in NURESIM and NURISP Projects
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Topics: Accidents, Boiling, Bubbly flow, Computational fluid dynamics, Computer simulation, Condensation, Coolants, Flow (Dynamics), Large eddy simulation, Nucleate boiling
Proceedings Papers

Application of Large-Eddy Simulation to Pressurized Thermal Shock Problem

M. S. Loginov, E. M. J. Komen, A. K. Kuczaj
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 649-658, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75894
https://doi.org/10.1115/ICONE17-75894
View Paper titled, Application of Large-Eddy Simulation to Pressurized Thermal Shock Problem
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Topics: Large eddy simulation, Thermal shock, Flow (Dynamics), Computational fluid dynamics, Coolants, Buoyancy, Engineering simulation, Reynolds-averaged Navier–Stokes equations, Scalars, Simulation
Proceedings Papers

COSI Test Case Simulation With CFX Code

Tony Glantz
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 659-666, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75923
https://doi.org/10.1115/ICONE17-75923
View Paper titled, COSI Test Case Simulation With CFX Code
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Topics: Simulation, Fluids, Computational fluid dynamics, Pressurized water reactors, Water, Condensation, Temperature, Thermal shock, Accidents, Coolants