| Accident tolerant fuel cladding development: Promise, status, and challenges |
74 |
| Primary radiation damage: A review of current understanding and models |
51 |
| Oxide inclusions in laser additive manufactured stainless steel and their effects on impact toughness and stress corrosion cracking behavior |
32 |
| Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors |
28 |
| Recent progress in the development of SiC composites for nuclear fusion applications |
21 |
| Behavior of tungsten under irradiation and plasma interaction |
19 |
| Response of Cr and Cr-Al coatings on Zircaloy-2 to high temperature steam |
16 |
| Fission gas release from UO2 nuclear fuel: A review |
16 |
| The thermo-mechanical behaviour of W-Cu metal matrix composites for fusion heat sink applications: The influence of the Cu content |
15 |
| Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding |
14 |
| Unit mechanisms of fission gas release: Current understanding and future needs |
14 |
| Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels |
14 |
| Hydrogen in zirconium alloys: A review |
14 |
| Response of unalloyed tungsten to mixed spectrum neutrons |
14 |
| U3Si2 behavior in H2O: Part I, flowing steam and the effect of hydrogen |
13 |
| Ferritic-martensitic steels for fission and fusion applications |
13 |
| Defect structures and statistics in overlapping cascade damage in fusion-relevant bcc metals |
13 |
| Historical review of computer simulation of radiation effects in materials |
13 |
| Aggregation and data analysis of corrosion studies in molten chloride and fluoride salts |
13 |
| In situ SEM-EBSD analysis of plastic deformation mechanisms in neutron-irradiated austenitic steel |
13 |
| Uranium extraction by sulfonated mesoporous silica derived from blast furnace slag |
13 |
| Effect of roughness of substrate and sputtering power on the properties of TiN coatings deposited by magnetron sputtering for ATF |
13 |
| CaO-Al2O3 glass-ceramic as a joining material for SiC based components: A microstructural study of the effect of Si-ion irradiation |
12 |
| Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding |
12 |
| On alpha ' precipitate composition in thermally annealed and neutron-irradiated Fe-9-18Cr alloys |
12 |
| Investigation of the thermal and neutron irradiation response of BAM-11 bulk metallic glass |
12 |
| Coated particle fuel: Historical perspectives and current progress |
12 |
| Out-of-pile performance of surface-modified Zr cladding for accident tolerant fuel in LWRs |
11 |
| Study of the oxidation behavior of CrN coating on Zr alloy in air |
11 |
| High-temperature oxidation of thick Cr coating prepared by arc deposition for accident tolerant fuel claddings |
11 |
| Mechanical properties of single-crystal tungsten irradiated in a mixed spectrum fission reactor |
11 |
| Cluster dynamics modeling of Mn-Ni-Si precipitates in ferritic-martensitic steel under irradiation |
11 |
| Evolution of the microstructural and mechanical properties of BAM-11 bulk metallic glass during ion irradiation and annealing |
10 |
| Low cycle fatigue and creep fatigue interaction behavior of 9Cr-0.5Mo-1.8W-V-Nb heat-resistant steel at high temperature |
10 |
| Annealing of radiation-induced defects in tungsten: Positron annihilation spectroscopy study |
10 |
| A chemical composition correction model for nanoclusters observed by APT - Application to ODS steel nanoparticles |
10 |
| Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations |
10 |
| Quantification of hardening contribution of G-Phase precipitation and spinodal decomposition in aged duplex stainless steel: APT analysis and micro-hardness measurements |
10 |
| New interatomic potentials of W, Re and W-Re alloy for radiation defects |
10 |
| HRTEM and chemical study of an ion-irradiated chromium/zircaloy-4 interface |
10 |
| U3Si2 behavior in H2O environments: Part II, pressurized water with controlled redox chemistry |
10 |
| Fabrication of UO2-Mo composite fuel with enhanced thermal conductivity from sol-gel feedstock |
10 |
| High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments |
10 |
| Results on the use of tungsten heavy alloys in the divertor of ASDEX Upgrade |
10 |
| Irradiation effects in high entropy alloys and 316H stainless steel at 300 degrees C |
10 |
| Microstructure and thermal properties of unalloyed tungsten deposited by Wire plus Arc Additive Manufacture |
9 |
| Effects of Ti and Ta addition on microstructure stability and tensile properties of reduced activation ferritic/martensitic steel for nuclear fusion reactors |
9 |
| On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models |
9 |
| Separate effects irradiation testing of miniature fuel specimens |
9 |
| Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn plus Sb as a mixed additive system to bind lanthanides |
9 |
