专题：Nuclear Materials and Properties

This cluster of papers focuses on the development and properties of advanced materials for nuclear fuel, including accident tolerant fuels, fuel cladding, thermophysical properties, oxidation resistance, behavior under high temperature and irradiation, hydrogen embrittlement, and fission product release.
最新文献
Bidirectional degradation of the Mo diffusion barrier in FeCrAl-coated Zircaloy-4 during steam oxidation above the Fe-Zr eutectic temperature

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Stiffness mismatch-induced interfacial delamination governs fretting-corrosion degradation of Cr–Mo coated Zr alloy in simulated PWR water

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Experimental study on fretting wear characteristics of Zr-4 alloy cladding

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Grain boundary–mediated Zr diffusion and Cr2O3 reduction governing steam oxidation degradation in Cr-coated Zr alloy

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High-temperature steam corrosion performance of FeCrAl alloys after long-term service in PWR condition: A reliable evaluation and multiscale microstructural characterization

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Evolution of fatigue-induced cracks in Cr-coated Zr alloy cladding in high-temperature steam environment

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Effect of dissolved oxygen on autoclave grid-to-rod fretting corrosion behavior of Cr coated fuel cladding in simulated primary water

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Conceptual design of an ultra-high flux fast reactor with strong irradiation capability

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Unraveling the influence of redox conditions on corrosion product deposition in Cr-coated cladding

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Micropores governed high-temperature oxidation behavior of Cr coatings: Kinetics analysis and phase-field modeling

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近5年高被引文献
Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

article Full Text OpenAlex 428 FWCI21.8248

Materials for extreme environments

article Full Text OpenAlex 320 FWCI23.7705

Functional nanomaterials for selective uranium recovery from seawater: Material design, extraction properties and mechanisms

article Full Text OpenAlex 298 FWCI23.1698

Review of progress in calculation and simulation of high-temperature oxidation

article Full Text OpenAlex 184 FWCI31.8884

Advanced nuclear energy: the safest and most renewable clean energy

review Full Text OpenAlex 177 FWCI2.41

Phase-field simulation of nano-α′ precipitates under irradiation and dislocations

article Full Text OpenAlex 148 FWCI9.1812

Molten Salt Reactors and Thorium Energy

book Full Text OpenAlex 147 FWCI19.3868

Design considerations for high entropy alloys in advanced nuclear applications

article Full Text OpenAlex 140 FWCI10.7023

Nuclear waste from small modular reactors

article Full Text OpenAlex 133 FWCI12.0129

Superior radiation tolerance via reversible disordering–ordering transition of coherent superlattices

article Full Text OpenAlex 128 FWCI6.7369