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Proceedings Papers

Nuclear Graphite Irradiated Material Property Normalization, Interpolation, and Extrapolation Approach

Adam Walker, Kevin Caldwell, Stuart Kellner, Anthony Schroeder
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A043, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123523
https://doi.org/10.1115/PVP2024-123523
View Paper titled, Nuclear Graphite Irradiated Material Property Normalization, Interpolation, and Extrapolation Approach
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Topics: Fluence (Radiation measurement), Graphite, Interpolation, Materials properties, Neutrons
Proceedings Papers

Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project

Frideriki Naziris, Rebeca Hernandez Pascual, Timo Metzler, Ermile Gaganidze, Inge Uytdenhouwen, Murthy Kolluri
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A045, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107254
https://doi.org/10.1115/PVP2023-107254
View Paper titled, Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project
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Topics: ASTM International, Design, Embrittlement, Fluence (Radiation measurement), Fracture toughness, Geometry, Machinery, Machining, Manipulators, Reactor vessels
Proceedings Papers

Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor

Henry Cathcart, James Finley, John Taylor, Alexander Frost
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A055, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84742
https://doi.org/10.1115/PVP2022-84742
View Paper titled, Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor
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Topics: Atoms, Bricks, Carbon, Dimensions, Emissions, Failure, Failure analysis, Finite element analysis, Fluence (Radiation measurement), Fuels
Proceedings Papers

Coupling of Neutron Transport and Probabilistic Fracture Mechanics Codes for Analysis of Embrittled Reactor Pressure Vessels

Benjamin W. Spencer, William M. Hoffman, Benjamin S. Collins, Shane C. Henderson
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A057, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21680
https://doi.org/10.1115/PVP2020-21680
View Paper titled, Coupling of Neutron Transport and Probabilistic Fracture Mechanics Codes for Analysis of Embrittled Reactor Pressure Vessels
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Topics: Embrittlement, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Reactor vessels
Proceedings Papers

Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

Preeti Doddihal, Dennis Kawa, Douglas Scarth, Yu Chen
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A013, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93671
https://doi.org/10.1115/PVP2019-93671
View Paper titled, Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors
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Topics: Annulus, Finite element analysis, Nuclear reactors, Fracture (Materials), Fracture (Process), Strips, Fuels, Irradiation (Radiation exposure), Pressure, Stress
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Chinese RPV Steels

Yupeng Cao, Yinbiao He, Binxi Wang, Yifeng Huang, Hui Li, Yan Yu, Hu Hui
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A028, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93615
https://doi.org/10.1115/PVP2019-93615
View Paper titled, Evaluation of Irradiation Embrittlement of the Chinese RPV Steels
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Topics: Embrittlement, Irradiation (Radiation exposure), Steel, Forging, China, Fluence (Radiation measurement), Fracture toughness, Mechanical properties, Notch testing, Nuclear power stations
Proceedings Papers

Assessment of Structural Integrity on Irradiated Steel Structure: Focusing on Long Column Type Reactor Pressure Vessel Supports

Goeun Han, Sukru Guzey
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A020, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93640
https://doi.org/10.1115/PVP2019-93640
View Paper titled, Assessment of Structural Integrity on Irradiated Steel Structure: Focusing on Long Column Type Reactor Pressure Vessel Supports
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Topics: Reactor vessels, Steel, Fitness-for-service, Neutrons, Irradiation (Radiation exposure), American Petroleum Institute, Coolants, Finite element model, Fluence (Radiation measurement), Fracture toughness
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93043
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
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Topics: Fracture toughness, Reactor vessels, Surveillance, Fracture (Materials), Fluence (Radiation measurement), Neutrons, Vessels, Mechanical properties, Alloys, Damage
Proceedings Papers

Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4

Kai Lu, Jinya Katsuyama, Yinsheng Li, Shinobu Yoshimura
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A057, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93935
https://doi.org/10.1115/PVP2019-93935
View Paper titled, Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4
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Topics: Fracture mechanics, Reactor vessels, Failure, Neutrons, Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Light water reactors, Nondestructive evaluation, Nuclear power
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

Evaluation of Through Wall Fracture Toughness Distribution of IAEA Reference Material JRQ by Mini-C(T) Specimens and the Master Curve Method

Masato Yamamoto, Tomohiro Kobayashi
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A071, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84889
https://doi.org/10.1115/PVP2018-84889
View Paper titled, Evaluation of Through Wall Fracture Toughness Distribution of IAEA Reference Material JRQ by Mini-C(T) Specimens and the Master Curve Method
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Topics: Fracture toughness, Temperature, Fluence (Radiation measurement), Fracture (Materials), Reactor vessels, Regulations, Stress, Thermal shock, Wall thickness
Proceedings Papers

Presentation of DEFI-PROSAFE Project: Probabilistic Methodology to Assess Margin in Deterministic RPV Integrity Assessment and Proposed Benchmark

Ralf Tiete, Richard Trewin, Sebastien Blasset, Vladislav Pistora, Miroslav Posta, Markus Niffenegger, Guian Qian
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A074, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84615
https://doi.org/10.1115/PVP2018-84615
View Paper titled, Presentation of DEFI-PROSAFE Project: Probabilistic Methodology to Assess Margin in Deterministic RPV Integrity Assessment and Proposed Benchmark
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Topics: Accounting, Failure, Fluence (Radiation measurement), Fracture (Materials), Fracture (Process), Neutrons, Nozzles, Probability, Reactor vessels, Risk
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65317
https://doi.org/10.1115/PVP2017-65317
View Paper titled, Upper Shelf Energy Prediction Model for Irradiated Reactor Vessel Steels
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Topics: Reactor vessels, Steel, ASTM International, Databases, Copper, Embrittlement, Irradiation (Radiation exposure), Light water reactors, Surveillance, Chemistry
Proceedings Papers

Swelling of VVER-1000 Core Baffle: Numerical Modeling and Direct Measurement of its Geometrical Dimensions

Andrii Oryniak, Igor Orynyak
Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A019, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65769
https://doi.org/10.1115/PVP2017-65769
View Paper titled, Swelling of VVER-1000 Core Baffle: Numerical Modeling and Direct Measurement of its Geometrical Dimensions
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Topics: Computer simulation, Dimensions, Gages, Geometry, Nuclear power stations, Stress, Accounting, Boundary-value problems, Brittleness, Coolants
Proceedings Papers

Application of Master Curve Approach to Surveillance Test Data for WWER-1000 Reactor Pressure Vessels

Volodymyr M. Revka, Liudmyla I. Chyrko
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A066, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65518
https://doi.org/10.1115/PVP2017-65518
View Paper titled, Application of Master Curve Approach to Surveillance Test Data for WWER-1000 Reactor Pressure Vessels
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Topics: Reactor vessels, Surveillance, Fracture toughness, Metals, Electromagnetic scattering, Irradiation (Radiation exposure), Temperature, Embrittlement, Neutrons, Radiation (Physics)
Proceedings Papers

Organization of the Independent Safety Review Done by Electrabel for the Safety Assessment of Doel 3 and Tihange 2 RPVs

Arnaud Meert, Jean-Paul De Cock
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A048, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-66216
https://doi.org/10.1115/PVP2017-66216
View Paper titled, Organization of the Independent Safety Review Done by Electrabel for the Safety Assessment of Doel 3 and Tihange 2 RPVs
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Topics: Safety, Teams, Fluence (Radiation measurement), Hydrogen, Irradiation (Radiation exposure), Mechanical testing, Nondestructive evaluation, Reactor vessels
Proceedings Papers

The Master Curve Fracture Toughness Evaluation of Irradiated Plate Material JRQ Using Miniature-C(T) Specimens

Masato Yamamoto
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A071, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-66085
https://doi.org/10.1115/PVP2017-66085
View Paper titled, The Master Curve Fracture Toughness Evaluation of Irradiated Plate Material JRQ Using Miniature-C(T) Specimens
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Topics: Fracture toughness, Steel, Base metals, Cracking (Materials), Dimensions, Fluence (Radiation measurement), Fracture (Process), Machining, Neutrons, Reactor vessels
Proceedings Papers

Embrittlement Trend Curves for Notch and Fracture Toughness of 15Kh2MFAA Type Steel

Milan Brumovsky, Radim Kopřiva, Miloš Kytka
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A063, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65174
https://doi.org/10.1115/PVP2017-65174
View Paper titled, Embrittlement Trend Curves for Notch and Fracture Toughness of 15Kh2MFAA Type Steel
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Topics: Embrittlement, Fracture toughness, Steel, Surveillance, Reactor vessels, Databases, Fluence (Radiation measurement), Temperature effects, Vessels, Copper
Proceedings Papers

Effect of Uncontrolled Hydrogen Injection on SCC Susceptibility of 304L Steel in High Temperature Water

A. L. Medina-Almazán, G. Galicia-Aguilar, J. C. Zenteno-Suárez, C. Arganis-Juárez, N. López-García, M. Marín-Almazo
Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A032, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65040
https://doi.org/10.1115/PVP2017-65040
View Paper titled, Effect of Uncontrolled Hydrogen Injection on SCC Susceptibility of 304L Steel in High Temperature Water
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Topics: High temperature, Hydrogen, Steel, Water, Boiling water reactors, Brittleness, Corrosion, Fatigue cracks, Light water reactors, Nuclear power stations
Proceedings Papers

Irradiation Induced Changes in Mechanical and Microstructural Properties of the High Flux Reactor Vessel: Update of the Results From 2014 and 2015 Surveillance Test Campaigns

M. Kolluri, F. H. E. de Haan-de Wilde, H. S. Nolles, A. J. M. de Jong, F. A. van den Berg
Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A018, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65007
https://doi.org/10.1115/PVP2017-65007
View Paper titled, Irradiation Induced Changes in Mechanical and Microstructural Properties of the High Flux Reactor Vessel: Update of the Results From 2014 and 2015 Surveillance Test Campaigns
Open the PDF for Irradiation Induced Changes in Mechanical and Microstructural Properties of the High Flux Reactor Vessel: Update of the Results From 2014 and 2015 Surveillance Test Campaigns in another window
Topics: Irradiation (Radiation exposure), Reactor vessels, Surveillance, Vessels, Neutrons, Damage, Fluence (Radiation measurement), Mechanical properties, Alloys, Fracture toughness