专题:Materials Challenges in Fusion Energy Research

This cluster of papers focuses on the materials challenges in fusion energy research, including radiation damage, plasma-facing components, irradiation-resistant steels, tungsten alloys, neutron irradiation effects, oxide dispersion-strengthened steels, and the development of interatomic potentials and molecular dynamics simulations for studying material behavior under fusion-relevant conditions.
最新文献
Development of Al-20Sm 2 O 3 -W Composites with Enhanced Gamma-Ray and Neutron Shielding, Mechanical and Corrosion Resistance

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Oxidation and degradation of Cr-coated Zr-based alloy up to 1500°C: Effect of Cr thickness

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Crystal phase transformation controlling crack propagation and interaction between cracks: A molecular dynamics simulation in α -Fe

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Nanostructure and Corrosion Resistance of Plasma-Based Low-Energy Nitrogen Ion Implanted 17-4PH Martensitic Stainless Steel

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Unexpected carbide formation in the FeCoNiCr high-entropy alloy under prolonged high temperature ion irradiation

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A quasi-isodynamic stellarator configuration towards a fusion power plant

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Model for the nanoindentation hardness-depth relationships of ion-irradiated bicrystals with grain boundary effect

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The effect of plasmoid drifts on the pellet rocket effect in magnetic confinement fusion plasmas

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The effect of ZrB2, Y2O3, and/or graphene nanoplatelet incorporation on densification, microstructural evolution, and compressive deformation of W-0.7Ni-0.3Fe alloys

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Alignment of the Thomson Scattering Diagnostic on Globus-M2 Tokamak

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近5年高被引文献
Design of an inertial fusion experiment exceeding the Lawson criterion for ignition

article Full Text OpenAlex 165 FWCI20.4749

Hierarchical microstructures enabled excellent low-temperature strength-ductility synergy in bulk pure tungsten

article Full Text OpenAlex 146 FWCI13.7731

Overview of JET results for optimising ITER operation

article Full Text OpenAlex 131 FWCI15.9496

Excellent high-temperature strength and ductility of the ZrC nanoparticles dispersed molybdenum

article Full Text OpenAlex 128 FWCI11.4006

Divertor of the European DEMO: Engineering and technologies for power exhaust

article Full Text OpenAlex 125 FWCI9.1418

Microstructure understanding of high Cr-Ni austenitic steel corrosion in high-temperature steam

article Full Text OpenAlex 123 FWCI66.2952

Beyond Orowan hardening: Mapping the four distinct mechanisms associated with dislocation-precipitate interaction

article Full Text OpenAlex 116 FWCI11.2334

Avoiding fusion plasma tearing instability with deep reinforcement learning

article Full Text OpenAlex 114 FWCI77.1718

A sustained high-temperature fusion plasma regime facilitated by fast ions

article Full Text OpenAlex 112 FWCI13.0646

Overview of the SPARC physics basis towards the exploration of burning-plasma regimes in high-field, compact tokamaks

article Full Text OpenAlex 109 FWCI13.0475