1-8 of 8
Keywords: mini-CT
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

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

Available to Purchase

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
... of surveillance specimens for beyond the original design life of 40 years. Thus, testing methods based on small / sub-sized specimens are considered. Experimental programmes on un-irradiated RPV steels have proven that miniature compact tension (∼4*10 *10 mm 3 ) specimens, mini-CT, can successfully be used...
View Paper titled, Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project
Open the PDF for Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project in another window
Topics: ASTM International, Design, Embrittlement, Fluence (Radiation measurement), Fracture toughness, Geometry, Machinery, Machining, Manipulators, Reactor vessels
Proceedings Papers

The Effect of Loss of Constraint on the Initiation of Ductile Fracture in a Mini-CT

Available to Purchase

Meng Li, Rachid Chaouadi, Inge Uytdenhouwen, Thomas Pardoen, Giovanni Bonny
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A035, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-106216
https://doi.org/10.1115/PVP2023-106216
...Proceedings of the ASME 2023 Pressure Vessels & Piping Conference PVP2023 July 16-21, 2023, Atlanta, Georgia PVP2023-106216 THE EFFECT OF LOSS OF CONSTRAINT ON THE INITIATION OF DUCTILE FRACTURE IN A MINI-CT M. Li1,2 R. Chaouadi1, I. Uytdenhowen1, T. Pardoen2, G. Bonny1 1 Belgian Nuclear Research...
View Paper titled, The Effect of Loss of Constraint on the Initiation of Ductile Fracture in a Mini-CT
Open the PDF for The Effect of Loss of Constraint on the Initiation of Ductile Fracture in a Mini-CT in another window
Topics: Ductile fracture, Finite element analysis, Micromechanics (Engineering), Simulation
Proceedings Papers

Fracture Characterization of Structural Steel S275JR Using Conventional CT Specimens, Mini-CT Specimens and Small Punch Specimens: A Comparison

Available to Purchase

Marcos Sánchez, Sergio Cicero, Borja Arroyo
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A029, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105437
https://doi.org/10.1115/PVP2023-105437
... Abstract Miniaturized specimens, such as mini-CT specimens and Small Punch (SP) specimens, are a solid alternative when characterizing the fracture behavior of structural materials but there are restrictions related to the amount of material available, irradiation issues or material...
View Paper titled, Fracture Characterization of Structural Steel S275JR Using Conventional CT Specimens, Mini-CT Specimens and Small Punch Specimens: A Comparison
Open the PDF for Fracture Characterization of Structural Steel S275JR Using Conventional CT Specimens, Mini-CT Specimens and Small Punch Specimens: A Comparison in another window
Topics: Fracture (Materials), Fracture (Process), Structural steel, Temperature
Proceedings Papers

Literature Review on Testing of Mini-CT Specimen to Characterize the Ductile-to-Brittle Transition Range and the Upper Shelf Regime

Available to Purchase

Marcos Sánchez, Sergio Cicero, Sergio Arrieta
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A032, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105596
https://doi.org/10.1115/PVP2023-105596
... the different nuclear components are subjected, with the reactor pressure vessel being one of the most critical. In this sense, the use of the mini-CT specimen (a compact tension 4 mm thick specimen) constitutes a promising alternative that has been widely studied together with the Master Curve approach...
View Paper titled, Literature Review on Testing of Mini-CT Specimen to Characterize the Ductile-to-Brittle Transition Range and the Upper Shelf Regime
Open the PDF for Literature Review on Testing of Mini-CT Specimen to Characterize the Ductile-to-Brittle Transition Range and the Upper Shelf Regime in another window
Topics: Brittleness, Testing, Steel, Geometry, Displacement, Fracture (Materials), Fracture (Process), Fracture toughness, Reactor vessels, Stress
Proceedings Papers

Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld

Available to Purchase

Mikhail A. Sokolov
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A027, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84827
https://doi.org/10.1115/PVP2022-84827
...Proceedings of the ASME 2022 Pressure Vessels & Piping Conference PVP2022 July 17-22, 2022, Las Vegas, Nevada, USA PVP2022-84827 USE OF MINI-CT SPECIMENS FOR FRACTURE TOUGHNESS CHARACTERIZATION OF IRRADIATED HIGHLY EMBRITTLED WELDi Mikhail A. Sokolov1 Oak Ridge National Laboratory, Oak Ridge, TN...
View Paper titled, Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld
Open the PDF for Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld in another window
Topics: Embrittlement, Fracture toughness, Radiation (Physics)
Proceedings Papers

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

Available to Purchase

Frideriki Naziris, Casper Versteylen, Frederick Frith, Marcel Bregman, Murthy Kolluri
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A064, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61027
https://doi.org/10.1115/PVP2021-61027
... Abstract Most standard surveillance programs for pressurized water reactors (PWR), do not contain enough surveillance specimens for their long-term operation (LTO) beyond the original design life of 40 years. The use of testing methods based on small/sub-sized specimen such as mini-CT (0.16 CT...
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
Open the PDF for Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels in another window
Topics: Irradiation (Radiation exposure), Manufacturing, Reactor vessels, Steel, Tension, Testing, Geometry, Stress, ASTM International, Pressurized water reactors
Proceedings Papers

Fracture Toughness Characterization in the Transition and Ductile Regime of an A508 Type Weld Metal With the Mini-CT Geometry Before and After Irradiation

Available to Purchase

Marlies Lambrecht, Rachid Chaouadi, Inge Uytdenhouwen, Robert Gérard
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A038, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21515
https://doi.org/10.1115/PVP2020-21515
... Abstract The mini-CT geometry is being adopted worldwide for application to measure the fracture toughness properties. This geometry is particularly adapted for irradiated materials given the limited space available for irradiation in high flux material test reactors such as the BR2 reactor...
View Paper titled, Fracture Toughness Characterization in the Transition and Ductile Regime of an A508 Type Weld Metal With the Mini-CT Geometry Before and After Irradiation
Open the PDF for Fracture Toughness Characterization in the Transition and Ductile Regime of an A508 Type Weld Metal With the Mini-CT Geometry Before and After Irradiation in another window
Topics: Fracture toughness, Geometry, Irradiation (Radiation exposure), Metals
Proceedings Papers

Effect of Neutron Irradiation on the Mechanical Properties of an A508 Cl.2 Forging Irradiated in a BAMI Capsule

Available to Purchase

Inge Uytdenhouwen, Rachid Chaouadi
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A060, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21513
https://doi.org/10.1115/PVP2020-21513
... the outside to the center of the cylindrical blocks, the latter were limited in size. Only tensile and fracture toughness data could therefore be obtained with mini-tensile and mini-CT specimens. The results show that no influence of the temperature gradient could be found on the tensile and fracture...
View Paper titled, Effect of Neutron Irradiation on the Mechanical Properties of an A508 Cl.2 Forging Irradiated in a BAMI Capsule
Open the PDF for Effect of Neutron Irradiation on the Mechanical Properties of an A508 Cl.2 Forging Irradiated in a BAMI Capsule in another window
Topics: Forging, Fracture toughness, Irradiation (Radiation exposure), Mechanical properties, Neutrons