Page 1 | Search Results | ASME Digital Collection

1-4 of 4

Sort by

Sort Order Select

Journal Articles

Effective Stress Factor Correlation Equations for Piping Branch Junctions Under Internal Pressure Loading

D. G. Moffat, J. Mistry, S. E. Moore

Publisher: ASME

J. Pressure Vessel Technol. May 1999, 121(2): 121–126.

https://doi.org/10.1115/1.2883674

Published Online: May 1, 1999

View Article titled, Effective Stress Factor Correlation Equations for Piping Branch Junctions Under Internal Pressure Loading

Topics: Junctions, Pipes, Pressure, Stress, Finite element analysis, Design

Journal Articles

Background for Changes in the 1981 Edition of the ASME Nuclear Power Plant Components Code for Controlling Primary Loads in Piping Systems

S. E. Moore, E. C. Rodabaugh

Publisher: ASME

J. Pressure Vessel Technol. November 1982, 104(4): 351–361.

https://doi.org/10.1115/1.3264228

Published Online: November 1, 1982

View Article titled, Background for Changes in the 1981 Edition of the ASME Nuclear Power Plant Components Code for Controlling Primary Loads in Piping Systems

Topics: Nuclear power stations, Piping systems, Stress, Pipes, Deformation, ASME Boiler and Pressure Vessel Code, Bending (Stress), Design, Pressure

Journal Articles

Experimental Stress Analysis for Four 24-in. ANSI Standard B16.9 Tees

J. K. Hayes, S. E. Moore

Publisher: ASME

J. Pressure Vessel Technol. November 1977, 99(4): 537–552.

https://doi.org/10.1115/1.3454572

Published Online: November 1, 1977

View Article titled, Experimental Stress Analysis for Four 24-in. ANSI Standard B16.9 Tees

Topics: Stress analysis (Engineering), Pipes, Pressure, Stress, Low cycle fatigue, Carbon steel, Design, Manufacturing, Nuclear power stations, Strain gages

Journal Articles

Contributions of the ORNL Piping Program to Nuclear Piping Design Codes and Standards

S. E. Moore

Publisher: ASME

J. Pressure Vessel Technol. February 1977, 99(1): 224–230.

https://doi.org/10.1115/1.3454513

Published Online: February 1, 1977

View Article titled, Contributions of the ORNL Piping Program to Nuclear Piping Design Codes and Standards

Topics: Engineering standards, Pipes, Piping design, Stress, Experimental analysis, Manufacturing industry, Nuclear power stations

Journal citation

NARROW

Effective Stress Factor Correlation Equations for Piping Branch Junctions Under Internal Pressure Loading

Background for Changes in the 1981 Edition of the ASME Nuclear Power Plant Components Code for Controlling Primary Loads in Piping Systems

Experimental Stress Analysis for Four 24-in. ANSI Standard B16.9 Tees

Contributions of the ORNL Piping Program to Nuclear Piping Design Codes and Standards

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

Effective Stress Factor Correlation Equations for Piping Branch Junctions Under Internal Pressure Loading

Background for Changes in the 1981 Edition of the ASME Nuclear Power Plant Components Code for Controlling Primary Loads in Piping Systems

Experimental Stress Analysis for Four 24-in. ANSI Standard B16.9 Tees

Contributions of the ORNL Piping Program to Nuclear Piping Design Codes and Standards

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only