Search Results | PVP | ASME Digital Collection

1-20 of 95

2 3 4 5

Sort by

Sort Order Select

Proceedings Papers

Evaluation of the Fracture Behavior of Cold-Worked Elbows With Prescribed Cracks

Sureshkumar Kalyanam, Sushma Pothana, Gery Wilkowski, Yunior Hioe, Fabian Orth, Frederick Brust, Steven Gilbert

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A004, July 17–22, 2022

Paper No: PVP2022-84833

DOI: https://doi.org/10.1115/PVP2022-84833

View Paper

Topics: Fracture (Materials), Pipes, Work hardening, Fracture (Process), Stress, Acceptance criteria, Collapse, Failure, Fittings, Fracture toughness

Proceedings Papers

Technical Justification to Extend Girth Weld Examination Intervals

Marvin J. Cohn

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A044, July 17–22, 2022

Paper No: PVP2022-85728

DOI: https://doi.org/10.1115/PVP2022-85728

View Paper

Topics: Creep, Damage, Design, Maintenance, Manufacturing, Mechanical engineers, Nondestructive evaluation, Pipes, Piping systems, Power Piping Code

Proceedings Papers

NuScale Pressure and Temperature Limits Methodology Using Finite Element Analysis

Heqin Xu, Joe Remic, Hongqing Xu

Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A018, July 13–15, 2021

Paper No: PVP2021-61856

DOI: https://doi.org/10.1115/PVP2021-61856

View Paper

Topics: Finite element analysis, Fracture mechanics, Pressure, Temperature, Brittleness, Cylinders, Design, Ductility, Failure, Finite element model

Proceedings Papers

Overview of Revisions to the ASME Boiler and Pressure Vessel Code Section VIII Division 3 for the 2021 Edition and Near Future

Adam P. Maslowski, Melanie Sarzynski, Daniel Peters, Kannan Subramanian

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T05A010, July 13–15, 2021

Paper No: PVP2021-61169

DOI: https://doi.org/10.1115/PVP2021-61169

View Paper

Topics: ASME Boiler and Pressure Vessel Code, High-pressure vessels, Construction, Mechanical engineers

Proceedings Papers

Safety Justification Strategy for the Implementation of Additive Manufacture Small-Bore Globe Valves for Nuclear Plant

Bill Press, Adam Dukes, Dave Poole, Jack Adams, Luke Burling, John Sulley

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A006, July 13–15, 2021

Paper No: PVP2021-62614

DOI: https://doi.org/10.1115/PVP2021-62614

View Paper

Topics: Nuclear power stations, Safety, Valves, Hardening, Pressure testing, Additive manufacturing, Bond strength, Cobalt, Construction, Dynamic testing (Materials)

Proceedings Papers

Technical Basis for Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping With Thermal Fatigue Cracking

Stephen Marlette, Steven L. McCraken, Christopher Lohse

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A097, August 3, 2020

Paper No: PVP2020-21544

DOI: https://doi.org/10.1115/PVP2020-21544

View Paper

Topics: Fatigue cracks, Maintenance, Pipes, Stainless steel, Overlays (Materials engineering), Fatigue, Boiling water reactors, Pressurized water reactors, Stress corrosion cracking, Design

Proceedings Papers

Case Study of the Effect of Combined Axial and Lateral Loadings on the Critical Buckling Capacity of Piping Supports

Phillip Wiseman, Alex Mayes, Shreeya Karnik

Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A078, August 3, 2020

Paper No: PVP2020-21517

DOI: https://doi.org/10.1115/PVP2020-21517

View Paper

Topics: Buckling, Pipes, Deformation, Euler-Bernoulli beam theory, ASME Boiler and Pressure Vessel Code, Bridges (Structures), Design, Finite element analysis, Manufacturing, Mechanical engineers

Proceedings Papers

Structural Analysis Approach for the Defense Programs Package 3 (DPP-3)

Peter J. Sakalaukus, Jr., Nathan P. Barrett, Brian J. Koeppel

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A039, August 3, 2020

Paper No: PVP2020-21259

DOI: https://doi.org/10.1115/PVP2020-21259

View Paper

Topics: ASME Boiler and Pressure Vessel Code, Defense industry, Finite element analysis, Structural analysis, Testing, Design, Computer software, Containment vessels, Damage, Hazardous substances

Proceedings Papers

Technical Basis for Weld Overlay Repair to Address Thermal Fatigue Cracking in Class 1, 2, and 3 Nuclear Reactor Piping

Stephen Marlette, Steven L. McCracken, David Segletes

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A089, July 14–19, 2019

Paper No: PVP2019-93360

DOI: https://doi.org/10.1115/PVP2019-93360

View Paper

Topics: Fatigue cracks, Maintenance, Nuclear reactors, Overlays (Materials engineering), Pipes, Fatigue, Stainless steel, Stress corrosion cracking, ASME Standards, Boiling water reactors

Proceedings Papers

The Application of NUPACK to the Design of a Type B Packaging Containment Vessel

Kathryn Karius, Kurt R. Eberl, Charles A. McKeel, Glenn A. Abramczyk

Proc. ASME. PVP2019, Volume 7: Operations, Applications, and Components, V007T07A030, July 14–19, 2019

Paper No: PVP2019-94071

DOI: https://doi.org/10.1115/PVP2019-94071

View Paper

Topics: Containment vessels, Design, Packaging, ASME Boiler and Pressure Vessel Code, Construction, Concrete construction, Containment, Mechanical engineers, Metals, Transportation systems

Proceedings Papers

Consideration of Thermal Embrittlement in Alloy 316H for Advanced Non-Light Water Reactor Applications

Weiju Ren, Lianshan Lin

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A016, July 14–19, 2019

Paper No: PVP2019-93431

DOI: https://doi.org/10.1115/PVP2019-93431

View Paper

Topics: Embrittlement, Indium alloys, Water, Alloys, Light water reactors, Temperature, Mechanical engineers, Mechanical properties, Safety

Proceedings Papers

A Development of the Technical Basis for the New Code Case “Mitigation of PWSCC and CISCC in ASME Section III Components by the Advanced Surface Stress Improvement Technology”

S. W. Cho, W. G. Yi, N. Mohr, A. Amanov, C. Stover, J. Tatman, V. Vasudevan, Y. S. Kim, Y. S. Pyun, H. Naralasetty, K. T. Kim

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A088, July 14–19, 2019

Paper No: PVP2019-93330

DOI: https://doi.org/10.1115/PVP2019-93330

View Paper

Topics: Stress, Stress corrosion cracking, Corrosion, Shot peening, Testing, Water, Cavitation, Chemistry, Construction, Density

Proceedings Papers

Overview of Revisions to the ASME Boiler and Pressure Vessel Code Section VIII Division 3 for the 2019 Edition and Near Future

Adam P. Maslowski, Gregory Mital, Daniel Peters, Kannan Subramanian

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), V005T05A014, July 14–19, 2019

Paper No: PVP2019-93102

DOI: https://doi.org/10.1115/PVP2019-93102

View Paper

Topics: ASME Boiler and Pressure Vessel Code, High-pressure vessels, Construction, Mechanical engineers

Proceedings Papers

Reactor Vessel Nozzle Inner Radius Fracture Analyses Using Elastic-Plastic Fracture Mechanics

S. E. Marlette

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A059, July 15–20, 2018

Paper No: PVP2018-85130

DOI: https://doi.org/10.1115/PVP2018-85130

View Paper

Topics: Fracture mechanics, Nozzles, Radius fractures, Reactor vessels, Design, ASME Standards, Fracture (Materials), Fracture (Process), Inspection, Mechanical engineers

Proceedings Papers

NTD ASI, Section IV: Evaluation of Residual Lifetime of Components and Piping in WWER Type NPPs

Milan Brumovsky

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A050, July 15–20, 2018

Paper No: PVP2018-84139

DOI: https://doi.org/10.1115/PVP2018-84139

View Paper

Topics: Nuclear power stations, Pipes, Reactor vessels, Corrosion, Failure, Pressurized water reactors, Safety, Water, Damage, Design

Proceedings Papers

Assessment of Passively Actuated In-Situ Cyclic Surveillance Test Specimens for Advanced Non-Light Water Reactors

M. C. Messner, V.-T. Phan, R. I. Jetter, T.-L. Sham

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A018, July 15–20, 2018

Paper No: PVP2018-84793

DOI: https://doi.org/10.1115/PVP2018-84793

View Paper

Topics: Surveillance, Water, Creep, Damage, Fatigue, Design, Mechanical engineers, Mechanical testing, Rupture, Secondary ion mass spectrometry

Proceedings Papers

ASME ANDE-1: A Completely New Approach to Personnel Qualification

Tomáš Zavadil, Michael L. Turnbow

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A007, July 15–20, 2018

Paper No: PVP2018-85161

DOI: https://doi.org/10.1115/PVP2018-85161

View Paper

Topics: Mechanical engineers, Nondestructive evaluation, Quality control

Proceedings Papers

Normative Technical Documentation of Association of Mechanical Engineers, Czech National Code of Equipment and Piping of Nuclear Power Plants of WWER Type

Lubomír Junek

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A055, July 15–20, 2018

Paper No: PVP2018-85155

DOI: https://doi.org/10.1115/PVP2018-85155

View Paper

Topics: Mechanical engineers, Nuclear power stations, Pipes, Damage, Failure, Reliability, Brakes, Construction, Failure analysis, Fracture mechanics

Proceedings Papers

Evaluation of Reactor Internals Integrity and Lifetime According to the NTD ASI

Milan Brumovsky

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A056, July 15–20, 2018

Paper No: PVP2018-84140

DOI: https://doi.org/10.1115/PVP2018-84140

View Paper

Topics: Control systems, Cracking (Materials), Creep, Design, Dimensions, Embrittlement, Failure, Ferrites (Magnetic materials), Fracture (Process), Fracture mechanics

Proceedings Papers

Retracted: “Comparison of Different Bolt Elongation Load Control Methods” [ASME 2018 Pressure Vessels and Piping Conference, Volume 3A: Design and Analysis, Prague, Czech Republic, July 15–20, 2018, Conference Sponsors: Pressure Vessels and Piping Division, ISBN: 978-0-7918-5162-3, Copyright © 2018 by ASME. Paper No. PVP2018-85004, pp. V03AT03A017; 16 pages; doi:10.1115/PVP2018-85004]

ASME

Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A017, July 15–20, 2018

Paper No: PVP2018-85004

DOI: https://doi.org/10.1115/PVP2018-85004

View Paper

Topics: Design, Elongation, Mechanical engineers, Pipes, Pressure vessels, Stress

2 3 4 5

NARROW

Evaluation of the Fracture Behavior of Cold-Worked Elbows With Prescribed Cracks

Technical Justification to Extend Girth Weld Examination Intervals

NuScale Pressure and Temperature Limits Methodology Using Finite Element Analysis

Overview of Revisions to the ASME Boiler and Pressure Vessel Code Section VIII Division 3 for the 2021 Edition and Near Future

Safety Justification Strategy for the Implementation of Additive Manufacture Small-Bore Globe Valves for Nuclear Plant

Technical Basis for Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping With Thermal Fatigue Cracking

Case Study of the Effect of Combined Axial and Lateral Loadings on the Critical Buckling Capacity of Piping Supports

Structural Analysis Approach for the Defense Programs Package 3 (DPP-3)

Technical Basis for Weld Overlay Repair to Address Thermal Fatigue Cracking in Class 1, 2, and 3 Nuclear Reactor Piping

The Application of NUPACK to the Design of a Type B Packaging Containment Vessel

Consideration of Thermal Embrittlement in Alloy 316H for Advanced Non-Light Water Reactor Applications

A Development of the Technical Basis for the New Code Case “Mitigation of PWSCC and CISCC in ASME Section III Components by the Advanced Surface Stress Improvement Technology”

Overview of Revisions to the ASME Boiler and Pressure Vessel Code Section VIII Division 3 for the 2019 Edition and Near Future

Reactor Vessel Nozzle Inner Radius Fracture Analyses Using Elastic-Plastic Fracture Mechanics

NTD ASI, Section IV: Evaluation of Residual Lifetime of Components and Piping in WWER Type NPPs

Assessment of Passively Actuated In-Situ Cyclic Surveillance Test Specimens for Advanced Non-Light Water Reactors

ASME ANDE-1: A Completely New Approach to Personnel Qualification

Normative Technical Documentation of Association of Mechanical Engineers, Czech National Code of Equipment and Piping of Nuclear Power Plants of WWER Type

Evaluation of Reactor Internals Integrity and Lifetime According to the NTD ASI

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only