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Robert Swindeman
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Proceedings Papers

The Significance of the Tertiary Creep Criterion in Setting Time-Dependent Allowable Stresses

Robert Swindeman, Weiju Ren, Michael J. Swindeman
Proc. ASME. PVP2015, Volume 6B: Materials and Fabrication, V06BT06A059, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45981
https://doi.org/10.1115/PVP2015-45981
View Paper titled, The Significance of the Tertiary Creep Criterion in Setting Time-Dependent Allowable Stresses
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Topics: Creep, Stress, Rupture, Alloys, Databases, Electromagnetic scattering, Temperature
Journal Articles

Status of Alloy 800 H in Considerations for the Gen IV Nuclear Energy Systems

Weiju Ren, Robert Swindeman
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technology Review
J. Pressure Vessel Technol. October 2014, 136(5): 054001.
Paper No: PVT-11-1075
https://doi.org/10.1115/1.4025093
Published Online: June 24, 2014
View Article titled, Status of Alloy 800 H in Considerations for the Gen IV Nuclear Energy Systems
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Topics: Alloys, Creep, Stress, Temperature, Fatigue, Design, Rupture
Proceedings Papers

A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems

Weiju Ren, Robert Swindeman
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 821-836, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25278
https://doi.org/10.1115/PVP2010-25278
View Paper titled, A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems
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Topics: Alloys, Nuclear power, Design, Industrial research, Mechanical behavior, Nuclear power stations, Temperature
Proceedings Papers

Preliminary Consideration of Alloys 617 and 230 for Generation IV Nuclear Reactor Applications

Weiju Ren, Robert Swindeman
Proc. ASME. PVP2007, Volume 6: Materials and Fabrication, 371-384, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26091
https://doi.org/10.1115/PVP2007-26091
View Paper titled, Preliminary Consideration of Alloys 617 and 230 for Generation IV Nuclear Reactor Applications
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Topics: Alloys, Generation IV reactors, Nuclear reactors, Mechanical behavior, Modeling, Stability, Temperature
Journal Articles

A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers

Weiju Ren, Robert Swindeman
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technology Review
J. Pressure Vessel Technol. August 2009, 131(4): 044002.
https://doi.org/10.1115/1.3121522
Published Online: May 26, 2009
View Article titled, A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers
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Topics: Alloys, Creep, Fatigue, Temperature, Fracture (Materials), Stress, Nuclear reactors, Rupture
Proceedings Papers

A Review of Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications

Weiju Ren, Robert Swindeman
Proc. ASME. PVP2006-ICPVT-11, Volume 6: Materials and Fabrication, 489-500, July 23–27, 2006
Publisher: American Society of Mechanical Engineers
Paper No: PVP2006-ICPVT-11-93128
https://doi.org/10.1115/PVP2006-ICPVT-11-93128
View Paper titled, A Review of Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications
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Topics: Indium alloys, Nuclear reactors, Very high temperature reactors, Alloys, Creep, Fatigue, Fracture (Materials), Fracture toughness, High temperature, Rupture