In-situ Micromechanical Testing of Neutron Irradiated FeCrAl Alloys (original) (raw)

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

Yukinori Yamamoto

Journal of Nuclear Materials, 2017

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Database on Performance of Neutron Irradiated FeCrAl Alloys

Yukinori Yamamoto

2016

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Evaluation on the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys

Yukinori Yamamoto

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

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Microstructure and mechanical behavior of neutron irradiated ultrafine grained ferritic steel

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Neutron Irradiation Effects on Mechanical and Magnetic Properties of Pre-deformed Iron-based Model Alloys

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Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy

paul wady

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Deformation Behavior in Neutron Irradiated Generation II FeCrAl Alloys for Accident Tolerant Fuel Cladding

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Microstructural analysis of deformation in neutron-irradiated fcc materials

Naoyuki Hashimoto

Journal of Nuclear Materials, 2006

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Mechanical properties of neutron-irradiated nickel-containing martensitic steels: I. Experimental study

David McClintock

Journal of Nuclear Materials, 2006

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Experimental Plan and Irradiation Target Design for FeCrAl Embrittlement Screening Tests Conducted Using the High Flux Isotope Reactor

Yukinori Yamamoto

2015

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Small scale mechanical testing of irradiated materials

Daniel Kiener

Journal of Materials Research, 2015

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Deformation mode maps for tensile deformation of neutron-irradiated structural alloys

Naoyuki Hashimoto

Journal of Nuclear Materials, 2004

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Effect of Neutron Flux on an Irradiation-Induced Microstructure and Hardening of Reactor Pressure Vessel Steels

Bertrand Radiguet

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TEM Observation of Loops Decorating Dislocations and Resulting Source Hardening of Neutron-Irradiated Fe-Cr Alloys

Mercedes Hernandez

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Stability of Model Fe-Cr-Al Alloys Under The Presence of Neutron Radiation

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Mechanical properties and microstructure of certain construction materials after neutron irradiation

Burak Karadağ

The Soviet Journal of Atomic Energy, 1961

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NEUTRON-INDUCED MICROSTRUCTURAL EVOLUTION OF Fe-15Cr-16Ni ALLOYS AT~ 400 C DURING NEUTRON IRRADIATION IN THE FFTF FAST REACTOR-T. Okita

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2001

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Microstructural investigation of swelling dependence on nickel content in fast neutron-irradiated Fe-Cr-Ni austenitic ternaries

F. Garner

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Thermomechanical treatment for improved neutron irradiation resistance of austenitic alloy (Fe–21Cr–32Ni)

Heather Chichester

Journal of Nuclear Materials, 2013

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Effect of Irradiation and Temperature on Microstructural Characteristic of FeCrAl Alloys

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Development of an in situ neutron-scattering facility for research and education in the mechanical behavior of materials

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Preliminary Analysis of the General Performance and Mechanical Behavior of Irradiated FeCrAl Base Alloys and Weldments

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An evaluation of low temperature radiation embrittlement mechanisms in ferritic alloys

Roger E. Stoller

Journal of Nuclear Materials, 1994

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Effect of neutron irradiation on microstructure and tensile properties of TZM and Mo-5% Re alloys

Andy Horsewell

Journal of Nuclear Materials, 1994

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Handbook on the Material Properties of FeCrAl Alloys for Nuclear Power Production Applications (FY18 Version: Revision 1)

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Nanomechanical measurements of irradiated layers: Methodology, possibilities and pitfalls

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Microstructural Stability of M5™ Alloy Irradiated up to High Neutron Fluences

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Mechanical behavior of AISI 304SS determined by miniature test methods after neutron irradiation to 28dpa

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Gamma-ray (electron) irradiation effects on tensile properties of ferritic alloys

Roger E. Stoller

Journal of Nuclear Materials, 1996

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Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys

Yukinori Yamamoto

Journal of Nuclear Materials, 2015

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An alternative neutron diffractometer performance for strain/stress measurements

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Microstructure and mechanical behaviour of TZM and Mo-5% Re alloys irradiated with fission neutrons

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Microstructural evolution of neutron-irradiated Fe-Cr-Ni ternary alloys at high helium generation rates

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Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250–450°C

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