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eBook Chapter

Validation of Surveillance Concepts and Trend Curves by the Investigation of Decommissioned Reactor Pressure Vessels

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2018
https://doi.org/10.1520/STP160320160127
ISBN: 978-0-8031-7651-5
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Proceedings Papers

Master Curve Testing of Reactor Pressure Vessel Multilayer Welding Seams

Hans-Werner Viehrig, Mario Houska, Eberhard Altstadt
Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A025, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45279
https://doi.org/10.1115/PVP2015-45279
View Paper titled, Master Curve Testing of Reactor Pressure Vessel Multilayer Welding Seams
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Topics: Reactor vessels, Testing, Welding, Fracture toughness, Fracture (Materials), Crack propagation, Metals, ASTM International, Brittleness, Fatigue cracks
Proceedings Papers

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T 0 Under Various Selections of Temperature Conditions

Masato Yamamoto, Akihiko Kimura, Kunio Onizawa, Kentaro Yoshimoto, Takuya Ogawa, Yasuhiro Mabuchi, Hans-Werner Viehrig, Naoki Miura, Naoki Soneda
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A098, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28898
https://doi.org/10.1115/PVP2014-28898
View Paper titled, A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T 0 Under Various Selections of Temperature Conditions
Open the PDF for A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T 0 Under Various Selections of Temperature Conditions in another window
Topics: Temperature, Fracture toughness, Testing, Electromagnetic scattering, Machinery, Steel, Surveillance, ASTM International, Dimensions, Reliability
eBook Chapter

Fracture Mechanics Characterisation of Forged Base Metal Ring of the Decommissioned Reactor Pressure Vessel of NPP Greifswald WWER-440 Unit 4

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2013
https://doi.org/10.1520/STP104056
ISBN: 978-0-8031-7533-4
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Journal Articles

Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Jan Schuhknecht, Hans-Werner Viehrig, Udo Rindelhardt
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Research Papers
J. Eng. Gas Turbines Power. May 2011, 133(5): 052904.
https://doi.org/10.1115/1.4000891
Published Online: December 9, 2010
View Articletitled, Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
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Topics: Base metals, Metals, Reactor vessels, Temperature, Welding, Electromagnetic scattering, Fracture (Materials), Fracture toughness, Nuclear power stations, Steel
Proceedings Papers

IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Effect of Loading Rate

Hans-Werner Viehrig, Enrico Lucon, William L. Server
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 467-472, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77668
https://doi.org/10.1115/PVP2009-77668
View Paper titled, IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Effect of Loading Rate
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Topics: Fracture toughness, Steel, ASTM International, Brittleness, Dynamic testing (Engineering), Dynamic testing (Materials), Pendulums
Proceedings Papers

IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Final Results of the Experimental Exercise to Support Constraint Effects

Randy K. Nanstad, Milan Brumovsky, Rogelio Herna´ndez Callejas, Ferenc Gillemot, Mikhail Korshunov, Bong Sang Lee, Enrico Lucon, Marc Scibetta, Philip Minnebo, Karl-Fredrik Nilsson, Naoki Miura, Kunio Onizawa, Tapio Planman, William Server, Brian Burgos, Marta Serrano, Hans-Werner Viehrig
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 573-585, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-78022
https://doi.org/10.1115/PVP2009-78022
View Paper titled, IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Final Results of the Experimental Exercise to Support Constraint Effects
Open the PDF for IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Final Results of the Experimental Exercise to Support Constraint Effects in another window
Topics: Fracture toughness, Steel, Carbon reinforced plastics, Temperature, Resolution (Optics), Surveillance, ASTM International, Finite element analysis, Geometry, Modeling
Proceedings Papers

Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Jan Schuhknecht, Hans-Werner Viehrig, Udo Rindelhardt
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 289-295, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75063
https://doi.org/10.1115/ICONE17-75063
View Paper titled, Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
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Topics: Base metals, Reactor vessels, Welding, Metals, Temperature, ASTM International, Irradiation (Radiation exposure), Nuclear power stations, Steel, Testing
Proceedings Papers

PERFECT—Prediction of Irradiation Damage Effects in Reactor Components: Update of Progress in RPV Mechanics Sub-Project

David Lidbury, Ste´phane Bugat, Olivier Diard, Elisabeth Keim, Bernard Marini, Hans-Werner Viehrig, Tapio Planman, Kim Wallin
Proc. ASME. PVP2007, Volume 6: Materials and Fabrication, 235-243, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26076
https://doi.org/10.1115/PVP2007-26076
View Paper titled, PERFECT—Prediction of Irradiation Damage Effects in Reactor Components: Update of Progress in RPV Mechanics Sub-Project
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Topics: Damage, Fracture (Materials), Irradiation (Radiation exposure), Multiscale modeling
Proceedings Papers

Round-Robin Exercise on Instrumented Impact Testing of Precracked Charpy Specimens (IAEA Coordinated Research Program Phase 8)

Enrico Lucon, Hans-Werner Viehrig
Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 193-199, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26088
https://doi.org/10.1115/PVP2007-26088
View Paper titled, Round-Robin Exercise on Instrumented Impact Testing of Precracked Charpy Specimens (IAEA Coordinated Research Program Phase 8)
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Topics: ASTM International, Brittleness, Carbon reinforced plastics, Electromagnetic scattering, Fracture toughness, Impact testing, Machinery, Pendulums, Steel, Testing
Proceedings Papers

IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Effect of Loading Rate

Hans-Werner Viehrig, Enrico Lucon
Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 187-192, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26087
https://doi.org/10.1115/PVP2007-26087
View Paper titled, IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Effect of Loading Rate
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Topics: Fracture toughness, Steel, Carbon reinforced plastics, ASTM International, Brittleness, Fracture (Materials), Irradiation (Radiation exposure), Pendulums, Temperature
Proceedings Papers

Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP

Udo Rindelhardt, Hans-Werner Viehrig, Joerg Konheiser, Jan Schuhknecht
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 423-431, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48070
https://doi.org/10.1115/ICONE16-48070
View Paper titled, Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP
Open the PDF for Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP in another window
Topics: Nuclear power stations, Reactor vessels, Fluence (Radiation measurement), Neutrons, Brittleness, Temperature, Cycles, Fracture toughness, Metals, Welded joints
Journal Articles

Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Hans-Werner Viehrig, Jan Schuhknecht, Udo Rindelhardt, Frank-Peter Weiss
Journal: Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. May 2009, 6(5): 1–10.
https://doi.org/10.1520/JAI101925
Published Online: May 1, 2009
View Articletitled, Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
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Journal Articles

Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP

Udo Rindelhardt, Hans-Werner Viehrig, Joerg Konheiser, Jan Schuhknecht
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Research Papers
J. Eng. Gas Turbines Power. March 2009, 131(2): 022904.
https://doi.org/10.1115/1.3032461
Published Online: January 5, 2009
View Articletitled, Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP
Open the PDF for Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP in another window
Topics: Annealing, Fluence (Radiation measurement), Neutrons, Nuclear power stations, Temperature, Fracture toughness, Welded joints, Reactor vessels, Disks
Proceedings Papers

PERFECT — Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project

David Lidbury, Ste´phane Bugat, Olivier Diard, Elisabeth Keim, Bernard Marini, Hans-Werner Viehrig, Kim Wallin
Proc. ASME. PVP2005, Volume 6: Materials and Fabrication, 321-329, July 17–21, 2005
Publisher: American Society of Mechanical Engineers
Paper No: PVP2005-71558
https://doi.org/10.1115/PVP2005-71558
View Paper titled, PERFECT — Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project
Open the PDF for PERFECT — Prediction of Irradiation Damage Effects in Reactor Components: Overview of RPV Mechanics Sub-Project in another window
Topics: Damage, Fracture (Materials), Irradiation (Radiation exposure), Multiscale modeling