A miniaturized test method for the mechanical characterization of structural materials for fusion reactors (original) (raw)

High temperature indentation tests on fusion reactor candidate materials

R. Montanari

Journal of Nuclear Materials, 2007

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Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors

David Frazer

Nuclear Materials and Energy, 2018

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Influence of Specimen Geometry and Strain Rate on Ductile-Brittle Transition Characterisation of Reactor Pressure Vessel Steels Using the Small Punch Technique

Martin Bache

Volume 6B: Materials and Fabrication, 2015

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FT/P2-2 Microstructure and tensile properties in reduced activation 8-9% Cr steels at fusion relevant He/dpa ratios, dpa rates and irradiation temperatures

Edeltraud Materna-Morris

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On determination of the constitutive behavior of tempered martensitic steels from micro-indentations: Application to Eurofer97 steel

Philippe Spatig

Journal of Nuclear Materials, 2013

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ICONE15-10394 Structural Materials for Fusion Technologies Studied by Non Destructive Techniques

V. Krsjak

The Proceedings of the International Conference on Nuclear Engineering (ICONE), 2007

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Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation

Max Doebeli

Journal of Materials Engineering and Performance

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Small punch test application for evaluation of the initial mechanical properties of VVER-440 / 213 type reactor pressure vessel materials

Michal Kapusňák

2017

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Characterization of Reactor Pressure Vessel Steel by ABI Testing

Jan Siegl

Procedia Materials Science, 2016

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Mechanical Properties in Nuclear Installation and the Relevant Measurement Methods

Parashuram Sahoo

Science and Technology of Nuclear Installations, 2016

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Effect of specimen size on the impact properties of neutron irradiated A533B steel

aravind kumar

Journal of Nuclear Materials, 1995

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Advanced materials characterization and modeling using synchrotron, neutron, TEM, and novel micro-mechanical techniques—A European effort to accelerate fusion materials development

Christian Linsmeier

Journal of Nuclear Materials, 2013

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Effect of hydrogen on tensile properties of martenistic steels for fusion application

M. Beghini

Journal of Nuclear Materials, 1998

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Neutron damage in reduced activation martensitic alloys in inertial and magnetic fusion reactors: Comparison with fission reactors*1

J. Manuel Perlado

Journal of Nuclear Materials, 1991

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Low temperature embrittlement behaviour of different ferritic-martensitic alloys for fusion applications

Michael Rieth

Journal of Nuclear Materials, 1996

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Influence of microstructure on impact properties of 9–18%Cr ODS steels for fusion/fission applications

J.-l. Béchade

Journal of Nuclear Materials, 2011

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Microstructural characterization of Eurofer-ODS RAFM steel in the normalized and tempered condition and after thermal aging in simulated fusion conditions

Alberto Armas

Fusion Engineering and Design, 2005

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Small scale mechanical testing of irradiated materials

Daniel Kiener

Journal of Materials Research, 2015

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Comparative study of the mechanical properties of different tungsten materials for fusion applications

K. Mergia

Physica Scripta, 2017

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Analytical determination of the constitutive behavior from micro-pillar testing: Application to a tempered martensitic steel

Philippe Spatig

AIP Advances, 2014

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Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications

Enrico Lucon, sofia paulina

Journal of Nuclear Materials, 2009

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Investigation into Irradiation Effects in ODS Steels Using Ion Implantation and Micromechanical Testing

Eleanor M Grieveson

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Design and Manufacture of Industrially Representative Weld Mock-ups for the Quantification of Residual Stresses in a Nuclear Pressure Vessel Steel

John Francis

2017

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Characterisation of the fracture properties in the ductile to brittle transition region of the weld material of a reactor pressure vessel

Diego Ferreño

Journal of Nuclear Materials, 2011

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Considerations for design with cyclic softening materials in fusion reactor applications

J Stubbins

Journal of Nuclear Materials, 1986

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Small angle neutron scattering (SANS) investigation of irradiated manet steel

F. Carsughi

Applied Radiation and Isotopes, 1995

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Evaluation of Microstructure and Mechanical Properties in a Thick Plate of G91 Steel and its Weld for High Temperature Nuclear System

Milan Brandt

Current Nanoscience, 2014

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Tailoring mechanical properties of nano-structured Eurofer 97 steel for fusion applications

Mariusz Kulczyk

physica status solidi (c), 2010

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Small-scale nondestructive stress-strain and creep tests feasible during irradiation

Andrea Sili

Journal of Nuclear Materials, 1994

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Analysis of displacement damage in materials in nuclear fusion facilities (DEMO, IFMIF and TechnoFusion)

Rafael Vila

Fusion Engineering and Design, 2011

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Revealing the residual stress distribution in laser welded Eurofer97 steel by neutron diffraction and Bragg edge imaging

Saurabh Kabra

Journal of Materials Science & Technology, 2022

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Effects of implantation treatments on micromechanical properties of M2 steel

Fernando Alonso

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 1993

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