Mukesh Bachhav

Idaho National Laboratory — United States

Materials Science · Physical Sciences

19h-index1.4kcitations89works2.72yr avg
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Research Topics

Nuclear Materials and Properties(58), Fusion materials and technologies(51), Advanced Materials Characterization Techniques(43), Nuclear reactor physics and engineering(19), Hydrogen embrittlement and corrosion behaviors in metals(15)

Publications89 total

Entrapment Behavior of Solid Surrogate Fission Products at Engineered UN Nano‐Hetero‐Interfaces Within Metallic Nuclear Fuels
Advanced Materials Interfaces·2025Open Access
Nanoscale clustering and fission product segregation in irradiated annular U-10Zr fuel
Journal of Nuclear Materials·2025
High resolution microstructural, chemical studies and localized burnup analysis in an irradiated U 10Zr metallic fuel
Materials Characterization·2025· 1 cited
Enhancing Cluster Identification in Atom Probe Tomography Data Using a Density-Based Framework
Microscopy and Microanalysis·2025Open Access
Advanced Characterization and Modeling of Microstructure in Irradiated UO2
Microscopy and Microanalysis·2025
Precision Local Burnup Assessment Through Dynamic Peak Fitting in Atom Probe Tomography for Depleted, Enriched, and Irradiated Metallic and Ceramic Fuels
Microscopy and Microanalysis·2025· 1 cited
The role of excess vacancies in stabilizing solute clusters in low-alloy steels
Scripta Materialia·2025· 2 cited
Xenon–metal pair formation in UO2 investigated using DFT + <i>U</i>
Journal of Applied Physics·2025· 1 citedOpen Access
Irradiation-induced formation of G-phase precipitates and M2X carbides in self-ion irradiated HT-9
Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms·2025· 3 cited
Local chemical ordering of a neutron-irradiated CrFeMnNi compositionally complex alloy
Acta Materialia·2025· 6 citedOpen Access
Discerning the effect of various irradiation modes on the corrosion of Zircaloy-4
Journal of Nuclear Materials·2024· 4 citedOpen Access
Advanced Characterization of Irradiated Silicon Carbide Claddings [Slides]
2024Open Access
Formation of uranium nitride nanoparticles via mechanical alloying of uranium-molybdenum alloy fuels in gaseous nitrogen
Journal of Nuclear Materials·2024· 3 citedOpen Access
Advanced Characterization of Metallic Fuels by Atom Probe Tomography
Microscopy and Microanalysis·2024· 3 cited
Automated Burnup Analysis from Metallic, Ceramic, and Amorphous Fuels using Atom Probe Tomography
Microscopy and Microanalysis·2024· 2 cited
Atom Probe Tomography (APT) Characterization of Annular U-Zr Metallic Fuel Cladded with HT-9
Microscopy and Microanalysis·2024· 2 citedOpen Access
Correlating microstructure and mechanical properties of harvested high dose Zorita light water reactor internals
Journal of Nuclear Materials·2024· 7 citedOpen Access
Microstructural evolution in doped high entropy alloys NiCoFeCr-3X (X=Pd/Al/Cu) under irradiation
Journal of Nuclear Materials·2024· 9 citedOpen Access
A critical review of irradiation-induced changes in reactor pressure vessel steels
Progress in Nuclear Energy·2024· 9 citedOpen Access
Atom probe tomography of segregation at grain boundaries and gas bubbles in neutron irradiated U-10 wt% Mo fuel
Materials Letters·2024· 1 citedOpen Access
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Frequent Co-authors

Emmanuelle A. Marquis(11), Lingfeng He(10), Tiankai Yao(8), Fei Teng(8), Adrien Couet(7), Jian Gan(6), G.R. Odette(5), Dennis D. Keiser(5), Zefeng Yu(5), Amrita Sen(5), Janelle P. Wharry(5), F. Danoix(4), B. Hannoyer(4), R. Danoix(4), F. Vurpillot(4), Takuya Yamamoto(3), Yan Dong(3), Daniel J. Murray(3), Peng Wang(3), Arthur T. Motta(3)