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Proceedings Papers

The Effects of Carburisation on Creep Response of Stainless Steel Components

J. Cakstins, R. A. Ainsworth, M. Su
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A033, July 14–19, 2019
Paper No: PVP2019-93189
DOI: https://doi.org/10.1115/PVP2019-93189
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Topics: Carburization, Creep, Stainless steel, Cylinders, Deformation, Steady state, Materials properties, Stress, Transients (Dynamics), Carbon dioxide
Proceedings Papers

Recent Developments in the R5 Procedures for Assessing the High Temperature Response of Structures

Daniel G. J. Hughes, Marc Chevalier, David W. Dean
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A040, July 14–19, 2019
Paper No: PVP2019-93838
DOI: https://doi.org/10.1115/PVP2019-93838
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Topics: High temperature, Creep, Fatigue, Fracture (Materials), Metals, Carburization, Design, Energy generation, Feedback, Gas cooled reactors
Proceedings Papers

Factors Affecting the Oxidation and Carburisation Behaviour of an Austenitic Stainless Steel Used in the UK Advanced Gas-Cooled Reactors

S. Palkó, F. Scenini, R. A. Ainsworth
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A067, July 15–20, 2018
Paper No: PVP2018-84279
DOI: https://doi.org/10.1115/PVP2018-84279
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Topics: Carburization, Gas cooled reactors, Oxidation, Stainless steel, Carbon dioxide, Coolants, Cracking (Materials), Deformation, Fracture (Process), Stress
Proceedings Papers

Creep-Fatigue Crack for a 2¼Cr1Mo and Inconel Transition Weld

Jinhua Shi
Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A046, July 19–23, 2015
Paper No: PVP2015-45018
DOI: https://doi.org/10.1115/PVP2015-45018
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Topics: Creep, Fatigue, Fracture (Materials), Stress, Temperature, Welded joints, Heat, Bending (Stress), Fillers (Materials), Gas cooled reactors
Proceedings Papers

Creep-Fatigue Crack Initiation Assessments of an Instrument Guide Tube Within a Superheater Header

Jinhua Shi, Hassam Dodia
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A040, July 20–24, 2014
Paper No: PVP2014-28022
DOI: https://doi.org/10.1115/PVP2014-28022
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Topics: Creep, Fatigue, Fracture (Materials), Instrumentation, Superheaters, Boilers, Damage, Fatigue damage, Materials properties, Temperature
Proceedings Papers

Degradation of Moderator Graphite in Gas Cooled Reactors

Robert Moskovic
Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 11-17, July 15–19, 2012
Paper No: PVP2012-78046
DOI: https://doi.org/10.1115/PVP2012-78046
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Topics: Gas cooled reactors, Graphite, Bricks, Fracture (Materials), Fracture (Process), Neutrons, Shapes, Temperature, Carbon dioxide, Corners (Structural elements)
Proceedings Papers

Presentation of RCC-MR Code 2007 for High Temperature Reactor and ITER Projects: Improvement of the Creep Fatigue Rules

Marie-Noe¨l Berton, Olivier Ancelet, Odile Gelineau, Morello Sperandio
Proc. ASME. PVP2009, Volume 1: Codes and Standards, 567-572, July 26–30, 2009
Paper No: PVP2009-77120
DOI: https://doi.org/10.1115/PVP2009-77120
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Topics: Creep, Fatigue, High temperature, Cycles, Stress, Temperature, Sodium fast reactors, Construction, Damage, Gas cooled reactors
Proceedings Papers

The Effect of Multiaxial States of Stress on Creep Failure of Type 316H Under Displacement Control

Michael W. Spindler, Michael C. Smith
Proc. ASME. PVP2009, Volume 6: Materials and Fabrication, Parts A and B, 817-823, July 26–30, 2009
Paper No: PVP2009-77963
DOI: https://doi.org/10.1115/PVP2009-77963
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Topics: Creep, Displacement, Failure, Stress, Damage, Relaxation (Physics), Temperature, Welded joints, Cracking (Materials), Finite element analysis
Proceedings Papers

Proposals of Improvements of RCC-MR Creep-Fatigue Rules

Marie-Noe¨l Berton, Olivier Ancelet, Marie The´re`se Cabrillat, Ste´phane Chapuliot
Proc. ASME. PVP2007, Volume 1: Codes and Standards, 395-401, July 22–26, 2007
Paper No: PVP2007-26564
DOI: https://doi.org/10.1115/PVP2007-26564
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Topics: Creep, Fatigue, Cycles, Stress, Temperature, Sodium fast reactors, Damage, Gas cooled reactors, High temperature, Relaxation (Physics)
Proceedings Papers

Analysis of the Creep Rupture Data of Alloy 617 for a High Temperature Gas Cooled Reactor

Woo Gon Kim, Song Nan Yin, Woo Seog Ryu, Jong Hwa Jang
Proc. ASME. PVP2007, Volume 9: Eighth International Conference on Creep and Fatigue at Elevated Temperatures, 439-444, July 22–26, 2007
Paper No: CREEP2007-26834
DOI: https://doi.org/10.1115/CREEP2007-26834
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Topics: Alloys, Creep, Gas cooled reactors, High temperature, Rupture, Design, Very high temperature reactors, ASME Boiler and Pressure Vessel Code, Failure, Heat exchangers
Proceedings Papers

Determination and Modeling of the Creep Propagation on High Chromium Steel

Olivier Ancelet, Ste´phane Chapuliot
Proc. ASME. PVP2007, Volume 9: Eighth International Conference on Creep and Fatigue at Elevated Temperatures, 99-107, July 22–26, 2007
Paper No: CREEP2007-26192
DOI: https://doi.org/10.1115/CREEP2007-26192
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Topics: Creep, Modeling, Steel, Fatigue, Design, Design engineering, Fast neutron reactors, Finite element model, Fracture (Materials), Gas cooled reactors
Proceedings Papers

A Review of Haynes® 230 and Haynes 617 Alloys for High Temperature Gas Cooled Reactors

Michael Katcher, Dwaine L. Klarstrom
Proc. ASME. PVP2007, Volume 6: Materials and Fabrication, 425-430, July 22–26, 2007
Paper No: PVP2007-26656
DOI: https://doi.org/10.1115/PVP2007-26656
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Topics: Alloys, Gas cooled reactors, High temperature, Creep, Ductility, Cooling, Grain boundaries, Precipitation, Fatigue life, Fatigue strength
Proceedings Papers

R&D and Pre-Normative Needs for Generation IV Nuclear Reactors

Andrea Tonti, Claude Renault, Morello Sperandio, Guy Baylac, Corrado Delle Site, Frank Carre´
Proc. ASME. PVP2008, Volume 1: Codes and Standards, 657-665, July 27–31, 2008
Paper No: PVP2008-61681
DOI: https://doi.org/10.1115/PVP2008-61681
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Topics: Generation IV reactors, Fast neutron reactors, Fluence (Radiation measurement), Gas cooled reactors, Irradiation (Radiation exposure), Neutrons, Nuclear reactors, Operating temperature, Pressure, Temperature
Proceedings Papers

Creep Fatigue Behavior and Damage Assessment for Mod 9 Cr 1 Mo Steel

Marie-The´re`se Cabrillat, Lucien Allais, Michel Mottot, Bernard Riou, Claude Escaravage
Proc. ASME. PVP2006-ICPVT-11, Volume 6: Materials and Fabrication, 511-520, July 23–27, 2006
Paper No: PVP2006-ICPVT-11-93238
DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93238
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Topics: Creep, Damage assessment, Fatigue, Steel, Cycles, Damage, Design, Fatigue design, Gas cooled reactors, Nuclear design