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Proceedings Papers

Fatigue Crack Growth Prediction of a Pipe With a Circumferential Surface Flaw Using Δ J and Reference Stress Method

Kiminobu Hojo, Satoshi Kumagai
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A018, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84555
https://doi.org/10.1115/PVP2022-84555
View Paper titled, Fatigue Crack Growth Prediction of a Pipe With a Circumferential Surface Flaw Using Δ J and Reference Stress Method
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Topics: Fatigue cracks, Pipes, Stress, Engineering standards, Computational methods, Cycles, Failure, Finite element analysis, Fitness-for-service, Fracture (Materials)
Proceedings Papers

UK Programme on Codes, Standards and Procedure Needs for SMR and Gen IV Reactors: Phase 1 Output

P. M. James, N. J. Underwood, J. K. Sharples
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A084, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93861
https://doi.org/10.1115/PVP2019-93861
View Paper titled, UK Programme on Codes, Standards and Procedure Needs for SMR and Gen IV Reactors: Phase 1 Output
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Topics: Carbon, Design, Emissions, Energy resources, Engineering standards, Governments, Heat, Nuclear research, Small modular reactors, Transportation systems
Proceedings Papers

PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution

Masato Yamamoto, Masaki Nagai
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A037, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93964
https://doi.org/10.1115/PVP2019-93964
View Paper titled, PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution
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Topics: Fracture toughness, Base metals, Fracture (Materials), Belts, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Nuclear research, Probability, Surveillance
Proceedings Papers

Material Properties of Reactor Pressure Vessel Shells Affected by Hydrogen Flaking

Robert Gérard, Michel De Smet, Rachid Chaouadi
Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A066, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63901
https://doi.org/10.1115/PVP2016-63901
View Paper titled, Material Properties of Reactor Pressure Vessel Shells Affected by Hydrogen Flaking
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Topics: Hydrogen, Materials properties, Reactor vessels, Shells, Safety, Irradiation (Radiation exposure), Fracture toughness, Accidents, Cycles, Embrittlement
Proceedings Papers

Overview of Recent NUGENIA Activities Particularly in Relation to Structural Integrity

John Sharples, Elisabeth Keim
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A062, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45217
https://doi.org/10.1115/PVP2015-45217
View Paper titled, Overview of Recent NUGENIA Activities Particularly in Relation to Structural Integrity
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Topics: Innovation, Nuclear power, Nuclear research, Power stations, Safety
Proceedings Papers

Over Limit Oxygen Effect on Crack Propagation of WWER 440 RPV Steel in Primary Circuit Water

Miroslava Ernestova, Anna Hojna
Proc. ASME. PVP2009, Volume 6: Materials and Fabrication, Parts A and B, 767-774, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77237
https://doi.org/10.1115/PVP2009-77237
View Paper titled, Over Limit Oxygen Effect on Crack Propagation of WWER 440 RPV Steel in Primary Circuit Water
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Topics: Circuits, Crack propagation, Oxygen, Steel, Water, Fracture (Materials), Corrosion, Failure, Fatigue, High temperature
Proceedings Papers

New PLIM Program for Czech NPPs

Petr Kadecˇka
Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 537-544, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77980
https://doi.org/10.1115/PVP2009-77980
View Paper titled, New PLIM Program for Czech NPPs
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Topics: Nuclear power stations, Databases, Design, Nuclear research
Proceedings Papers

Assessment of the Integrity of the Channel Shelter of the Experimental Nuclear Reactor LVR 15

Miroslav Svrcek, Ivan Krasny, Jan Lestina
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 739-744, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77306
https://doi.org/10.1115/PVP2009-77306
View Paper titled, Assessment of the Integrity of the Channel Shelter of the Experimental Nuclear Reactor LVR 15
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Topics: Absorption, Fracture (Materials), Neutrons, Nuclear reactors, Nuclear research, Stability, Water
Proceedings Papers

Cleavage Fracture Analysis of Cladded Beams With an Embedded Flaw Under Four-Point Bending

Shengjun Yin, Paul T. Williams, B. Richard Bass
Proc. ASME. PVP2008, Volume 6: Materials and Fabrication, Parts A and B, 103-110, July 27–31, 2008
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61388
https://doi.org/10.1115/PVP2008-61388
View Paper titled, Cleavage Fracture Analysis of Cladded Beams With an Embedded Flaw Under Four-Point Bending
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Topics: Failure, Fracture (Materials), Fracture (Process), Fracture mechanics, Fracture toughness, Hydrostatics, Nuclear research, Probability, Reactor vessels, Shapes
Proceedings Papers

Testing of Fracture Toughness Under Biaxial Loading

Milan Brumovsky, Dana Lauerova, Jiri Palyza
Proc. ASME. PVP2005, Volume 6: Materials and Fabrication, 183-186, July 17–21, 2005
Publisher: American Society of Mechanical Engineers
Paper No: PVP2005-71479
https://doi.org/10.1115/PVP2005-71479
View Paper titled, Testing of Fracture Toughness Under Biaxial Loading
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Topics: Fracture toughness, Testing, Fracture (Materials), Reactor vessels, Testing equipment, Deflection, Displacement, Finite element methods, Finite element model, Fracture mechanics