1-20 of 30
ASME Boiler and Pressure Vessel Code
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC

Wang Pei, Chen Dongxu, Yang Shumin
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A007, August 8–12, 2022
Paper No: ICONE29-91363
https://doi.org/10.1115/ICONE29-91363
View Paper titled, Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC
Open the PDF for Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC in another window
Topics: ASME Boiler and Pressure Vessel Code, Boilers, Metals, Welding
Proceedings Papers

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Masaki Morishita, Akihito Otani
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A002, August 8–12, 2022
Paper No: ICONE29-90172
https://doi.org/10.1115/ICONE29-90172
View Paper titled, On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads
Open the PDF for On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads in another window
Topics: Cycles, Earthquake resistant design, Earthquakes, Fatigue, Pipes, Piping systems, Stress, Excitation, ASME Boiler and Pressure Vessel Code, Deformation
Proceedings Papers

Comparison of the ASME, RCC-M and ISO Requirements for Welding Qualifications and Welding Quality

Marcello Consonni, Andrew Wasylyk, Stéphane Leclerc, Walter Sperko, Philippe Malouines
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T08A003, June 26–30, 2016
Paper No: ICONE24-60282
https://doi.org/10.1115/ICONE24-60282
View Paper titled, Comparison of the ASME, RCC-M and ISO Requirements for Welding Qualifications and Welding Quality
Open the PDF for Comparison of the ASME, RCC-M and ISO Requirements for Welding Qualifications and Welding Quality in another window
Topics: Welding, Engineering standards, ASME Boiler and Pressure Vessel Code, Boilers, Japan Society of Mechanical Engineers, Nuclear power stations, Pressure, Pressure vessels, Welding operators
Proceedings Papers

A Study of Axial Compression in the ASME B&PV Code for Pipe Supports and Restraints

Phillip E. Wiseman, Zara Z. Hoch
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, V001T03A033, June 26–30, 2016
Paper No: ICONE24-61101
https://doi.org/10.1115/ICONE24-61101
View Paper titled, A Study of Axial Compression in the ASME B&PV Code for Pipe Supports and Restraints
Open the PDF for A Study of Axial Compression in the ASME B&PV Code for Pipe Supports and Restraints in another window
Topics: Compression, Pipes, Stress, ASME Boiler and Pressure Vessel Code, Buckling, Design, ASME Standards, Elastic analysis, Mechanical engineers, Stability
Proceedings Papers

3D Linear Bifurcation Analysis of Steel Containment Vessel

Jay Schmidt, Bernd Laskewitz
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, V001T03A018, June 26–30, 2016
Paper No: ICONE24-60673
https://doi.org/10.1115/ICONE24-60673
View Paper titled, 3D Linear Bifurcation Analysis of Steel Containment Vessel
Open the PDF for 3D Linear Bifurcation Analysis of Steel Containment Vessel in another window
Topics: Bifurcation, Containment vessels, Steel, Shells, Stability, Buckling, Containment, Stress, ASME Boiler and Pressure Vessel Code, ASME Standards
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview

Tai Asayama, Takayuki Miyagawa, Koji Dozaki, Yoshio Kamishima, Masaaki Hayashi, Hideo Machida
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A004, July 7–11, 2014
Paper No: ICONE22-30567
https://doi.org/10.1115/ICONE22-30567
View Paper titled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview
Open the PDF for Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview in another window
Topics: Japan Society of Mechanical Engineers, Reliability, ASME Boiler and Pressure Vessel Code, Collaboration, Design, Engineering standards, In-service inspection, Liquid metals, Mechanical engineers, Sodium fast reactors
Proceedings Papers

Fatigue Assessment of Class 1 Nuclear Power Piping According to ASME BPV Code: Why Other Alternatives?

Lingfu Zeng, Lennart G. Jansson
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A016, July 7–11, 2014
Paper No: ICONE22-31074
https://doi.org/10.1115/ICONE22-31074
View Paper titled, Fatigue Assessment of Class 1 Nuclear Power Piping According to ASME BPV Code: Why Other Alternatives?
Open the PDF for Fatigue Assessment of Class 1 Nuclear Power Piping According to ASME BPV Code: Why Other Alternatives? in another window
Topics: Fatigue, Nuclear power, Pipes, Finite element analysis, Stress, ASME Boiler and Pressure Vessel Code, Damage, Design, Reliability
Proceedings Papers

Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program

Jianfeng Yang, Paul O’Brien
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A018, July 7–11, 2014
Paper No: ICONE22-31169
https://doi.org/10.1115/ICONE22-31169
View Paper titled, Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program
Open the PDF for Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program in another window
Topics: Coolants, Fatigue life, Light water reactors, Pressurized water reactors, Fatigue, Design, Alloys, Cycles, ASME Boiler and Pressure Vessel Code, Carbon
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (4) Joint Efforts of JSME and ASME

Tai Asayama, Shigeru Takaya, Masaki Morishita, Frank Schaaf
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A006, July 7–11, 2014
Paper No: ICONE22-30572
https://doi.org/10.1115/ICONE22-30572
View Paper titled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (4) Joint Efforts of JSME and ASME
Open the PDF for Elaboration of the System Based Code Concept — Activities in JSME and ASME: (4) Joint Efforts of JSME and ASME in another window
Topics: Japan Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Flow (Dynamics), In-service inspection, Liquid metals, Mechanical engineers, Safety, Sodium fast reactors
Proceedings Papers

Comparison of Different Acceptance Standard for Radiographic Rounded Indications in Welds

Cong Wang, GuoXiang Tang, JiaGuan Zhao, HengLiang Yang
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A011, July 29–August 2, 2013
Paper No: ICONE21-15491
https://doi.org/10.1115/ICONE21-15491
View Paper titled, Comparison of Different Acceptance Standard for Radiographic Rounded Indications in Welds
Open the PDF for Comparison of Different Acceptance Standard for Radiographic Rounded Indications in Welds in another window
Topics: Acceptance criteria, ASME Boiler and Pressure Vessel Code, Testing, Welded joints
Proceedings Papers

Introduction to KEPIC (Korea Electric Power Industry Code)

Myoung-Sung Sohn, Hyun-Jae Joo, Hoon-Seok Byun, Jong-Hae Kim
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A026, July 29–August 2, 2013
Paper No: ICONE21-16827
https://doi.org/10.1115/ICONE21-16827
View Paper titled, Introduction to KEPIC (Korea Electric Power Industry Code)
Open the PDF for Introduction to KEPIC (Korea Electric Power Industry Code) in another window
Topics: Electricity (Physics), Engineering standards, Nuclear power stations, Construction, ASME Boiler and Pressure Vessel Code, Design, Welding, ASTM International, Concretes, Electric fields
Proceedings Papers

Codes Comparison and Analysis of Weld Cladding Ultrasonic Testing in Nuclear Power Plants

Zhimin Zhong, Jian Min, Kai Li
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A002, July 29–August 2, 2013
Paper No: ICONE21-15086
https://doi.org/10.1115/ICONE21-15086
View Paper titled, Codes Comparison and Analysis of Weld Cladding Ultrasonic Testing in Nuclear Power Plants
Open the PDF for Codes Comparison and Analysis of Weld Cladding Ultrasonic Testing in Nuclear Power Plants in another window
Topics: Cladding systems (Building), Nuclear power stations, Ultrasonic testing, Inspection, China, ASME Boiler and Pressure Vessel Code, Nondestructive evaluation, Nuclear power, Pipes, Pressure vessels
Proceedings Papers

Summary and Comparision of Significant Historical Changes in the Design Requirements for Safety Class 2 and 3 Piping Systems in the ASME Boiler and Pressure Vessel Code, Section III, Division 1

Timothy M. Adams, Charles A. Papadelis
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, 63-76, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54243
https://doi.org/10.1115/ICONE20-POWER2012-54243
View Paper titled, Summary and Comparision of Significant Historical Changes in the Design Requirements for Safety Class 2 and 3 Piping Systems in the ASME Boiler and Pressure Vessel Code, Section III, Division 1
Open the PDF for Summary and Comparision of Significant Historical Changes in the Design Requirements for Safety Class 2 and 3 Piping Systems in the ASME Boiler and Pressure Vessel Code, Section III, Division 1 in another window
Topics: ASME Boiler and Pressure Vessel Code, Design, Piping systems, Safety, Stress, Pressure, Safety engineering
Proceedings Papers

ASME Applicability for Small Modular Reactors

Clayton T. Smith, George Beltz, Dennis K. Williams
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, 189-194, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54920
https://doi.org/10.1115/ICONE20-POWER2012-54920
View Paper titled, ASME Applicability for Small Modular Reactors
Open the PDF for ASME Applicability for Small Modular Reactors in another window
Topics: Small modular reactors, Engineering standards, Licensing, Pipes, Pressure vessels, ASME Boiler and Pressure Vessel Code, Design, Engineers, Light water reactors, Lumber
Proceedings Papers

Interpretive Comparison of the Requirements Relating to Welding and Non-Destructive Examination in the French and US Codes for Nuclear Components

Marcello Consonni, Peter Mudge
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, 35-49, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54190
https://doi.org/10.1115/ICONE20-POWER2012-54190
View Paper titled, Interpretive Comparison of the Requirements Relating to Welding and Non-Destructive Examination in the French and US Codes for Nuclear Components
Open the PDF for Interpretive Comparison of the Requirements Relating to Welding and Non-Destructive Examination in the French and US Codes for Nuclear Components in another window
Topics: Nondestructive evaluation, Welding, Pressurized water reactors, Construction, ASME Boiler and Pressure Vessel Code, Design, Manufacturing, Nuclear construction, Welded joints
Proceedings Papers

PWROG Buried Pipe Degradation Evaluation Handbook

Mark A. Moenssens
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, 121-128, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54474
https://doi.org/10.1115/ICONE20-POWER2012-54474
View Paper titled, PWROG Buried Pipe Degradation Evaluation Handbook
Open the PDF for PWROG Buried Pipe Degradation Evaluation Handbook in another window
Topics: Pipes, Stress, Fitness-for-service, Leakage, Soil, ASME Boiler and Pressure Vessel Code, Bending (Stress), Cast iron, Corrosion, Finite element analysis
Proceedings Papers

Basis of the Fatigue Capacities, Stress Intensification Factors, and Flexibility Factors for High Density Polyethylene Pipe in the ASME Boiler and Pressure Vessel Code, Section III, Division 1

Timothy M. Adams, Douglas Munson
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, 77-95, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54244
https://doi.org/10.1115/ICONE20-POWER2012-54244
View Paper titled, Basis of the Fatigue Capacities, Stress Intensification Factors, and Flexibility Factors for High Density Polyethylene Pipe in the ASME Boiler and Pressure Vessel Code, Section III, Division 1
Open the PDF for Basis of the Fatigue Capacities, Stress Intensification Factors, and Flexibility Factors for High Density Polyethylene Pipe in the ASME Boiler and Pressure Vessel Code, Section III, Division 1 in another window
Topics: ASME Boiler and Pressure Vessel Code, Density, Fatigue, Polyethylene pipes, Stress, Pipes, Safety, Carbon steel, Piping systems, Water
Proceedings Papers

Structural Integrity of HDPE Piping and Joints in Nuclear Safety-Related Applications

S. Kalyanam, P. Krishnaswamy, D.-J. Shim, Y. Hioe, E. Focht
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, 51-62, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54192
https://doi.org/10.1115/ICONE20-POWER2012-54192
View Paper titled, Structural Integrity of HDPE Piping and Joints in Nuclear Safety-Related Applications
Open the PDF for Structural Integrity of HDPE Piping and Joints in Nuclear Safety-Related Applications in another window
Topics: Pipes, Safety, Stress, Nuclear power stations, Service life (Equipment), ASME Boiler and Pressure Vessel Code, ASTM International, Fracture mechanics, Pressure, Rupture
Proceedings Papers

Expansion of the ASME Certification Process to Provide a NQA-1 Quality Certification

John G. Adkins, Joseph Pang
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, 97-101, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54249
https://doi.org/10.1115/ICONE20-POWER2012-54249
View Paper titled, Expansion of the ASME Certification Process to Provide a NQA-1 Quality Certification
Open the PDF for Expansion of the ASME Certification Process to Provide a NQA-1 Quality Certification in another window
Topics: ASME Boiler and Pressure Vessel Code, ASME Standards, Construction, Nuclear industry, Pressure, Quality control, Supply chains
Proceedings Papers

Stratified Flows in Pipes: A Parametric Study Towards Fatigue Relevance

Leon Cizelj, Igor Simonovski
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 653-659, May 17–21, 2010
Paper No: ICONE18-30122
https://doi.org/10.1115/ICONE18-30122
View Paper titled, Stratified Flows in Pipes: A Parametric Study Towards Fatigue Relevance
Open the PDF for Stratified Flows in Pipes: A Parametric Study Towards Fatigue Relevance in another window
Topics: Fatigue, Pipes, Stratified flow, Hot water, Stress, ASME Boiler and Pressure Vessel Code, Design, Finite element analysis, Fluids, Heat transfer