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Proceedings Papers

FRACTESUS Project: Final Selection of RPV Materials for Unirradiated and Irradiated Round Robins

Tomasz Brynk, Inge Uytdenhouwen, Pentti Arffman, Eberhard Altstadt, Radim Kopriva, Florian Obermeier, Marta Serrano
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A026, July 17–22, 2022
Paper No: PVP2022-83871
DOI: https://doi.org/10.1115/PVP2022-83871
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Topics: Base metals, Databases, Fracture toughness, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Notch testing, Reactor vessels, Temperature, Tension
Proceedings Papers

Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys

Xiang (Frank) Chen, Kevin G. Field, Richard Howard, Caleb P. Massey, Andrew T. Nelson
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A019, July 17–22, 2022
Paper No: PVP2022-84517
DOI: https://doi.org/10.1115/PVP2022-84517
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Topics: Accidents, Alloys, Cladding systems (Building), Embrittlement, Fracture toughness, Fuels, Hardening, Irradiation (Radiation exposure)
Proceedings Papers

Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals

Dong-Hyeon Kwak, Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui Jang
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A049, July 17–22, 2022
Paper No: PVP2022-84936
DOI: https://doi.org/10.1115/PVP2022-84936
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Topics: Compression, Finite element analysis, Irradiation (Radiation exposure), Reactor vessels, Stainless steel, Dislocation density, Materials properties, Stress-strain curves, Boundary-value problems, Constitutive equations
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
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Topics: Irradiation (Radiation exposure), Manufacturing, Reactor vessels, Steel, Tension, Testing, Geometry, Stress, ASTM International, Pressurized water reactors
Proceedings Papers

Effect of Neutron Irradiation on the Mechanical Properties of an A508 CL2 and 15Kh2NMFA Irradiated in the NOMAD_3 Rig in the BR2 Cooling Water

Inge Uytdenhouwen, Rachid Chaouadi
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A024, July 13–15, 2021
Paper No: PVP2021-61969
DOI: https://doi.org/10.1115/PVP2021-61969
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Topics: Cooling, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Water
Proceedings Papers

NuScale Pressure and Temperature Limits Methodology Using Finite Element Analysis

Heqin Xu, Joe Remic, Hongqing Xu
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A018, July 13–15, 2021
Paper No: PVP2021-61856
DOI: https://doi.org/10.1115/PVP2021-61856
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Topics: Finite element analysis, Fracture mechanics, Pressure, Temperature, Brittleness, Cylinders, Design, Ductility, Failure, Finite element model
Proceedings Papers

An Application of the Brittle Fracture Criterion Gp Method to a RPV Type Geometry – Towards the Industrialization of the Method

Bin Zheng, Han Liu, Samuel Jules, Hai Xie, Kaikai Shi
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A045, July 13–15, 2021
Paper No: PVP2021-61636
DOI: https://doi.org/10.1115/PVP2021-61636
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Topics: Brittle fracture, Geometry, Fracture (Materials), China, Computer software, Damage, Energy conservation, Finite element analysis, Irradiation (Radiation exposure), Life extension
Proceedings Papers

Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles

Osama Elbanhawy, Marwan Hassan, Atef Mohany, Hossam Kishawy
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A007, July 13–15, 2021
Paper No: PVP2021-62412
DOI: https://doi.org/10.1115/PVP2021-62412
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Topics: Dynamics (Mechanics), Fuel rods, Irradiation (Radiation exposure), Fuels, Flow (Dynamics), Constitutive equations, Coolants, Dynamic response, Mechanical properties, Pressure
Proceedings Papers

NOMAD: Non-Destructive Evaluation (NDE) System for the Inspection of Operation-Induced Material Degradation in Nuclear Power Plants — Overview of the Neutron Irradiation Campaigns

Inge Uytdenhouwen, Rachid Chaouadi
Proc. ASME. PVP2020, Volume 7: Non-Destructive Examination, V007T07A003, August 3, 2020
Paper No: PVP2020-21512
DOI: https://doi.org/10.1115/PVP2020-21512
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Topics: Inspection, Irradiation (Radiation exposure), Materials degradation, Neutrons, Nondestructive evaluation, Nuclear power stations
Proceedings Papers

High Flux Reactor Continued Safe Operation: Time Limited Ageing Analyses

L. Stefanini, F. H. E. de Haan - de Wilde
Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A010, August 3, 2020
Paper No: PVP2020-21032
DOI: https://doi.org/10.1115/PVP2020-21032
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Topics: Biomedicine, Equipment qualification, Fatigue, Irradiation (Radiation exposure), Isotopes, Leak-before-break, Manufacturing, Nuclear reactors, Reactor vessels
Proceedings Papers

Crack Propagation Modeling in a PWR Under PTS Using XFEM

Diego F. Mora, Markus Niffenegger, Roman Mukin
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A001, August 3, 2020
Paper No: PVP2020-21026
DOI: https://doi.org/10.1115/PVP2020-21026
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Topics: Crack propagation, Modeling, Pressurized water reactors, Fracture (Materials), Damage, Finite element analysis, Fracture toughness, Accidents, Cooling, Simulation
Proceedings Papers

Fabrication and Assembly of the First Accident Tolerant Fuel Concept for TREAT Testing

Connor Woolum, D. Devin Imholte, Austin Fleming, David Kamerman, Korbin Tritthart
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A078, August 3, 2020
Paper No: PVP2020-21620
DOI: https://doi.org/10.1115/PVP2020-21620
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Topics: Accidents, Fuels, Irradiation (Radiation exposure), Manufacturing, Testing, Cladding systems (Building), Pressurized water reactors, Transients (Dynamics), Design, Fuel systems
Proceedings Papers

Cracking Behavior of a Decommissioned Material in Light Water Reactor Environment

Y. Chen, B. Alexandreanu, A. S. Rao
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A071, August 3, 2020
Paper No: PVP2020-21141
DOI: https://doi.org/10.1115/PVP2020-21141
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Topics: Embrittlement, Fracture (Materials), Fracture (Process), Fracture toughness, Irradiation (Radiation exposure), Light water reactors, Stress corrosion cracking
Proceedings Papers

Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316L Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition

Masato Koshiishi, Hitoshi Seto, Shigeaki Tanaka, Ryoji Obata
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A073, August 3, 2020
Paper No: PVP2020-21332
DOI: https://doi.org/10.1115/PVP2020-21332
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Topics: Boiling water reactors, Irradiation (Radiation exposure), Neutrons, Stainless steel, Stress corrosion cracking, Fracture (Materials), Grain boundaries, Mechanical properties
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
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Topics: Embrittlement, Fracture mechanics, Fracture toughness, Irradiation (Radiation exposure), Reactor vessels, Steel, Surveillance, Displacement, Brittle fracture, Cracking (Materials)
Proceedings Papers

Estimation of Uniaxial Material Properties by Miniature Small Punch Testing to Support Post-Irradiation Examination of RPV Steels

Stefan Holmström, Oliver Martin, Theo Bakker, Murthy Kolluri, Matthias Bruchhausen
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A103, August 3, 2020
Paper No: PVP2020-21490
DOI: https://doi.org/10.1115/PVP2020-21490
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Topics: Irradiation (Radiation exposure), Materials properties, Steel, Testing
Proceedings Papers

Estimation of Charpy Index Temperature of SA 508 Mn-Mo-Ni Low Alloy Steels at 41J Using Small Punch Tests

Jongmin Kim, Seokmin Hong, Taekyoung Lee, Minchul Kim
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A074, August 3, 2020
Paper No: PVP2020-21360
DOI: https://doi.org/10.1115/PVP2020-21360
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Topics: Alloy steel, Temperature, Displacement, Fracture (Materials), Fracture (Process), Fracture toughness, Stress, Failure mechanisms, Irradiation (Radiation exposure), Mechanical properties
Proceedings Papers

Mechanical Properties of Ion-Irradiated Stainless Steel Determined by Nanoindentation Tests and Finite Element Analyses

Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui Jang
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A104, August 3, 2020
Paper No: PVP2020-21507
DOI: https://doi.org/10.1115/PVP2020-21507
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Topics: Finite element analysis, Irradiation (Radiation exposure), Mechanical properties, Nanoindentation, Stainless steel
Proceedings Papers

Bayesian Uncertainty Evaluation of Charpy Ductile-to-Brittle Transition Temperature for Reactor Pressure Vessel Steels

Hisashi Takamizawa, Yutaka Nishiyama, Takashi Hirano
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A065, August 3, 2020
Paper No: PVP2020-21698
DOI: https://doi.org/10.1115/PVP2020-21698
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Topics: Brittleness, Embrittlement, Irradiation (Radiation exposure), Notch testing, Phase transition temperature, Reactor vessels, Statistics, Steel, Uncertainty
Proceedings Papers

A52M/SA502 Dissimilar Metal RPV Repair Weld: Evaluation of Different Techniques

Heikki Keinänen, Pekka Nevasmaa, Juha Kuutti, Caitlin Huotilainen, Iikka Virkkunen, Mikko Peltonen, Henrik Sirén
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A109, August 3, 2020
Paper No: PVP2020-21233
DOI: https://doi.org/10.1115/PVP2020-21233
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Topics: Maintenance, Metals, Welding, Cladding systems (Building), Alloys, Reactor vessels, Steel, Filler metals, Heat treating (Metalworking), Nickel