[HTML][HTML] Additive manufacturing of FeCrAl alloys for nuclear applications-A focused review
FeCrAl alloys exhibit outstanding high-temperature oxidation resistance and impressive
mechanical strength, rendering them as forefront materials with broad applicability across …
mechanical strength, rendering them as forefront materials with broad applicability across …
[HTML][HTML] Recent progress in analysis of strain-induced phenomena in irradiated metallic materials and advanced alloys using SEM-EBSD in-situ tensile testing
In-situ mechanical testing in a scanning electron microscope (SEM) equipped with an
electron backscatter diffraction (EBSD) system has quickly gained popularity, particularly …
electron backscatter diffraction (EBSD) system has quickly gained popularity, particularly …
Microstructure, deformation and fracture mechanisms in Al-4043 alloy produced by laser hot-wire additive manufacturing
High deposition rate additive manufacturing (AM) processes with minimal feedstock costs
are desirable to reduce part fabrication times and minimize the cost of implementation. Wire …
are desirable to reduce part fabrication times and minimize the cost of implementation. Wire …
Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing
An approach to transform and accelerate nuclear fuel development and qualification is
outlined. The approach exploits advanced modeling and simulation at the outset to inform …
outlined. The approach exploits advanced modeling and simulation at the outset to inform …
In situ micro-pillar compression to examine radiation-induced hardening mechanisms of FeCrAl alloys
Abstract The effects of 5 MeV Fe 2+ ion irradiation at 300° C on the microstructure evolution
and deformation behavior of a FeCrAl C26M alloy are presented. It has been found that …
and deformation behavior of a FeCrAl C26M alloy are presented. It has been found that …
Handbook on the Material Properties of FeCrAl Alloys for Nuclear Power Production Applications (FY18 Version: Revision 1)
FeCrAl alloys are a class of alloys that have seen increased interest for nuclear power
applications including accident tolerant fuel cladding, structural components for fast fission …
applications including accident tolerant fuel cladding, structural components for fast fission …
Performance of a ferritic/martensitic steel for nuclear reactor applications fabricated using additive manufacturing
Ferritic/martensitic (FM) steels are being targeted for use in a range of advanced reactor
concepts as cladding and structural components. FM steels for nuclear reactor applications …
concepts as cladding and structural components. FM steels for nuclear reactor applications …
Evaluation of the continuous dilatometer method of silicon carbide thermometry for passive irradiation temperature determination
Silicon carbide (SiC) is a primary candidate for passive irradiation temperature monitoring,
and continuous dilatometry (CD) has been proposed as the key method for extracting …
and continuous dilatometry (CD) has been proposed as the key method for extracting …
Considerations for hydride moderator readiness in microreactors
The emergence of microreactor technology has helped to drive supporting nuclear materials
qualification and acceptance processes. One essential component in these small reactors is …
qualification and acceptance processes. One essential component in these small reactors is …
A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes
The present work offers and evaluates a correlation-based approach to determine the
tensile properties of nuclear fuel cladding tubes. A set of model materials with known …
tensile properties of nuclear fuel cladding tubes. A set of model materials with known …