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Proceedings Papers

Round Robin Analysis of Small Punch Testing on 15Kh2NMFA Reference Material

Romy Welschen, Ferenc Gillemot, Igor Simonovski, Oliver Martin, Marek Adamech, Jana Petzova, Rebeca Hernandez, Radim Kopriva, Frederiki Naziris, Boy Molenaar, Murthy Kolluri
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A046, July 17–22, 2022
Paper No: PVP2022-83811
DOI: https://doi.org/10.1115/PVP2022-83811
View Paper titled, Round Robin Analysis of Small Punch Testing on 15Kh2NMFA Reference Material
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Topics: Steel, Testing, Light water reactors, Manufacturing, Surveillance, Alloys, Brittleness, Creep, Disks, Fracture toughness
Proceedings Papers

Practical Procedure of Test Temperature Selection for Mini-C(T) Master Curve Evaluation

Masato Yamamoto, Seiji Sakuraya, Yuji Kitsunai, Mark Kirk
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A025, July 17–22, 2022
Paper No: PVP2022-82754
DOI: https://doi.org/10.1115/PVP2022-82754
View Paper titled, Practical Procedure of Test Temperature Selection for Mini-C(T) Master Curve Evaluation
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Topics: Reactor vessels, Steel, Temperature, Testing, Low temperature, Plasticity, Surveillance, ASTM International, Fracture toughness, Reliability
Proceedings Papers

Obtaining Low-Cost Estimates of the Master Curve Index Temperature T 0 From Existing Information

Mark Kirk, Naoki Miura, Tomoki Skinko, Masato Yamamoto
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A044, July 17–22, 2022
Paper No: PVP2022-83905
DOI: https://doi.org/10.1115/PVP2022-83905
View Paper titled, Obtaining Low-Cost Estimates of the Master Curve Index Temperature T 0 From Existing Information
Click here to open pdf in another window PDF for Obtaining Low-Cost Estimates of the Master Curve Index Temperature T 0 From Existing Information
Topics: Fracture toughness, Reactor vessels, Temperature, Testing, ASME Standards, Steel, Surveillance, Tension
Proceedings Papers

Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels

Frideriki Naziris, Casper Versteylen, Frederick Frith, Marcel Bregman, Murthy Kolluri
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A064, July 13–15, 2021
Paper No: PVP2021-61027
DOI: https://doi.org/10.1115/PVP2021-61027
View Paper titled, Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels
Click here to open pdf in another window PDF for Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels
Topics: Irradiation (Radiation exposure), Manufacturing, Reactor vessels, Steel, Tension, Testing, Geometry, Stress, ASTM International, Pressurized water reactors
Proceedings Papers

FRACTESUS Project: General Framework of Materials Selection and Testing Processes

Tomasz Brynk, Marlies Lambrecht, Inge Uytdenhouwen, Pentti Arffman, Eberhard Altstadt, Tom Petit
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A066, July 13–15, 2021
Paper No: PVP2021-61906
DOI: https://doi.org/10.1115/PVP2021-61906
View Paper titled, FRACTESUS Project: General Framework of Materials Selection and Testing Processes
Click here to open pdf in another window PDF for FRACTESUS Project: General Framework of Materials Selection and Testing Processes
Topics: Fracture toughness, Reactor vessels, Tension, Testing, Steel, Base metals, Computer simulation, Fracture mechanics, Materials testing, Nuclear power stations
Proceedings Papers

Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs

Maksym Zarazovskii, Volodymyr Revka, Liudmyla Chyrko
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A018, August 3, 2020
Paper No: PVP2020-21748
DOI: https://doi.org/10.1115/PVP2020-21748
View Paper titled, Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs
Click here to open pdf in another window PDF for Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs
Topics: Brittleness, Databases, Embrittlement, Phase transition temperature, Radiation (Physics), Regression analysis, Surveillance, Temperature, Welded joints, Silicon
Proceedings Papers

Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique

Florian Obermeier, Eberhard Altstadt, Hieronymus Hein, Aniruddh Das
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A102, August 3, 2020
Paper No: PVP2020-21481
DOI: https://doi.org/10.1115/PVP2020-21481
View Paper titled, Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique
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Topics: Embrittlement, Fracture mechanics, Fracture toughness, Irradiation (Radiation exposure), Reactor vessels, Steel, Surveillance, Displacement, Brittle fracture, Cracking (Materials)
Proceedings Papers

Ductile Crack Growth Resistance and Rotation Behavior of Miniature C(T) Specimen

Tomoki Shinko, Masato Yamamoto
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A037, August 3, 2020
Paper No: PVP2020-21104
DOI: https://doi.org/10.1115/PVP2020-21104
View Paper titled, Ductile Crack Growth Resistance and Rotation Behavior of Miniature C(T) Specimen
Click here to open pdf in another window PDF for Ductile Crack Growth Resistance and Rotation Behavior of Miniature C(T) Specimen
Topics: Ductile fracture, Fracture toughness, Rotation, Steel, Fracture (Materials), Size effect, Temperature, Deformation, Ductile-brittle transition, Evaluation methods
Proceedings Papers

RPV Irradiation Surveillance Programmes in China

Shuo Zhang, Haisheng Zhang, Kai Sun
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A025, July 14–19, 2019
Paper No: PVP2019-93068
DOI: https://doi.org/10.1115/PVP2019-93068
View Paper titled, RPV Irradiation Surveillance Programmes in China
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Topics: China, Irradiation (Radiation exposure), Surveillance, Pressurized water reactors, Safety, Nuclear power, Nuclear power stations, Construction, Design, Embrittlement
Proceedings Papers

Inconel X-750 Spacer Fitness-for-Service

Winnie Lau, Douglas Scarth, Preeti Doddihal
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A063, July 14–19, 2019
Paper No: PVP2019-93943
DOI: https://doi.org/10.1115/PVP2019-93943
View Paper titled, Inconel X-750 Spacer Fitness-for-Service
Click here to open pdf in another window PDF for Inconel X-750 Spacer Fitness-for-Service
Topics: Fitness-for-service, Annulus, Pressure, Fuels, Cooling, Design, Fatigue life, Leakage, Load bearing capacity, Materials degradation
Proceedings Papers

An Update on the Investigation of Fracture Toughness Properties of the High Flux Reactor Vessel From Surveillance Test Campaign in 2017

M. Kolluri, F. H. E. de Haan – de Wilde, H. S. Nolles, A. J. M. de Jong
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A008, July 14–19, 2019
Paper No: PVP2019-93043
DOI: https://doi.org/10.1115/PVP2019-93043
View Paper titled, An Update on the Investigation of Fracture Toughness Properties of the High Flux Reactor Vessel From Surveillance Test Campaign in 2017
Click here to open pdf in another window PDF for An Update on the Investigation of Fracture Toughness Properties of the High Flux Reactor Vessel From Surveillance Test Campaign in 2017
Topics: Fracture toughness, Reactor vessels, Surveillance, Fracture (Materials), Fluence (Radiation measurement), Neutrons, Vessels, Mechanical properties, Alloys, Damage
Proceedings Papers

Material Properties of Non-Irradiated Zircaloy 4 in Support of ASME Code Acceptance for Pressure Vessel Design

R. K. Nanstad, W. L. Server, B. Kombaiah, J. W. Geringer
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A021, July 14–19, 2019
Paper No: PVP2019-93654
DOI: https://doi.org/10.1115/PVP2019-93654
View Paper titled, Material Properties of Non-Irradiated Zircaloy 4 in Support of ASME Code Acceptance for Pressure Vessel Design
Click here to open pdf in another window PDF for Material Properties of Non-Irradiated Zircaloy 4 in Support of ASME Code Acceptance for Pressure Vessel Design
Topics: ASME Standards, Design, Fatigue, Fracture (Process), Fracture toughness, Materials properties, Pressure vessels, Stress, Surveillance, Vessels
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
Paper No: PVP2019-93964
DOI: https://doi.org/10.1115/PVP2019-93964
View Paper titled, PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution
Click here to open pdf in another window PDF for PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution
Topics: Fracture toughness, Base metals, Fracture (Materials), Belts, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Nuclear research, Probability, Surveillance
Proceedings Papers

Compact Crack Arrest Tests for the Validation of a Finite Element Material Model of the Reactor Pressure Vessel Steel of the Nuclear Power Plant KKG

Uwe Mayer, Alexander Mutz, Tomas Nicak
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A065, July 15–20, 2018
Paper No: PVP2018-84068
DOI: https://doi.org/10.1115/PVP2018-84068
View Paper titled, Compact Crack Arrest Tests for the Validation of a Finite Element Material Model of the Reactor Pressure Vessel Steel of the Nuclear Power Plant KKG
Click here to open pdf in another window PDF for Compact Crack Arrest Tests for the Validation of a Finite Element Material Model of the Reactor Pressure Vessel Steel of the Nuclear Power Plant KKG
Topics: Finite element analysis, Fracture (Materials), Nuclear power stations, Reactor vessels, Steel, Brittleness, Crack propagation, Failure, Thermal shock, Accidents
Proceedings Papers

Assessment of Passively Actuated In-Situ Cyclic Surveillance Test Specimens for Advanced Non-Light Water Reactors

M. C. Messner, V.-T. Phan, R. I. Jetter, T.-L. Sham
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A018, July 15–20, 2018
Paper No: PVP2018-84793
DOI: https://doi.org/10.1115/PVP2018-84793
View Paper titled, Assessment of Passively Actuated In-Situ Cyclic Surveillance Test Specimens for Advanced Non-Light Water Reactors
Click here to open pdf in another window PDF for Assessment of Passively Actuated In-Situ Cyclic Surveillance Test Specimens for Advanced Non-Light Water Reactors
Topics: Surveillance, Water, Creep, Damage, Fatigue, Design, Mechanical engineers, Mechanical testing, Rupture, Secondary ion mass spectrometry
Proceedings Papers

Master Curve Testing on Reconstituted Surveillance Charpy Specimens

Ferenc Gillemot, Márta Horváth, Ákos Horváth, Ildikó Szenthe, Attila Kovács
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A069, July 15–20, 2018
Paper No: PVP2018-84749
DOI: https://doi.org/10.1115/PVP2018-84749
View Paper titled, Master Curve Testing on Reconstituted Surveillance Charpy Specimens
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Topics: Surveillance, Testing, Fracture toughness, Embrittlement, Fracture (Materials), Radiation (Physics), Chain, Displacement, Evaluation methods, Fracture mechanics
Proceedings Papers

Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld Using Mini-C(T) Specimens

Michael R. Ickes, J. Brian Hall, Robert G. Carter
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A074, July 15–20, 2018
Paper No: PVP2018-84967
DOI: https://doi.org/10.1115/PVP2018-84967
View Paper titled, Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld Using Mini-C(T) Specimens
Click here to open pdf in another window PDF for Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld Using Mini-C(T) Specimens
Topics: Fracture toughness, Reactor vessels, ASTM International, Displacement, Geometry, Irradiation (Radiation exposure), Metals, Surveillance
Proceedings Papers

Reconstituted Mini Tensile Specimens

Attila Kovács, Ákos Horváth, Márta Horváth, Ildikó Szenthe, Ferenc Gillemot
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A065, July 15–20, 2018
Paper No: PVP2018-84760
DOI: https://doi.org/10.1115/PVP2018-84760
View Paper titled, Reconstituted Mini Tensile Specimens
Click here to open pdf in another window PDF for Reconstituted Mini Tensile Specimens
Topics: Clamps (Tools), Cutting, Fracture (Materials), Fracture (Process), Fracture toughness, Interpolation, Lasers, Machinery, Microscopes, Molybdenum
Proceedings Papers

Upper Shelf Energy Prediction Model for Irradiated Reactor Vessel Steels

Takuya Ogawa, J. Brian Hall, Benjamin E. Mays, Timothy C. Hardin
Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A009, July 16–20, 2017
Paper No: PVP2017-65317
DOI: https://doi.org/10.1115/PVP2017-65317
View Paper titled, Upper Shelf Energy Prediction Model for Irradiated Reactor Vessel Steels
Click here to open pdf in another window PDF for Upper Shelf Energy Prediction Model for Irradiated Reactor Vessel Steels
Topics: Reactor vessels, Steel, ASTM International, Databases, Copper, Embrittlement, Irradiation (Radiation exposure), Light water reactors, Surveillance, Chemistry
Proceedings Papers

Interim Safe Storage of Radioactive Materials at the Savannah River Site

Lucas L. Kyriazidis, Steve J. Hensel, Jeff M. Jordan
Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A032, July 16–20, 2017
Paper No: PVP2017-65064
DOI: https://doi.org/10.1115/PVP2017-65064
View Paper titled, Interim Safe Storage of Radioactive Materials at the Savannah River Site
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Topics: Radioactive substances, Rivers, Storage, Containers, Bearings, Surveillance, Containment, Metals, Packaging, Transport packages