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Mukesh Bachav

Government of the United States of America - Idaho National Laboratory

Box 1625

Idaho Falls, ID 83415

United States

SCHOLARLY PAPERS

11

DOWNLOADS

507

TOTAL CITATIONS

0

Scholarly Papers (11)

1.

Inferring Low Alloy Steel Thermal/Irradiation Microstructural Evolution Via Thermal Diffusivity

Number of pages: 11 Posted: 12 Dec 2023
Massachusetts Institute of Technology (MIT), Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Massachusetts Institute of Technology (MIT), University of Ottawa, Massachusetts Institute of Technology (MIT), Massachusetts Institute of Technology (MIT), Massachusetts Institute of Technology (MIT), Harbin Engineering University, Harbin Engineering University - Key Laboratory of Superlight Materials & Surface Technology and Massachusetts Institute of Technology (MIT)
Downloads 94 (720,278)

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Non-destructive evaluation (NDE), low-alloy steel, transient grating spectroscopy (TGS), thermal diffusivity

2.

Local Chemical Ordering of a Neutron-Irradiated CrFeMnNi Compositionally Complex Alloy

Number of pages: 21 Posted: 17 Oct 2024
University of Wisconsin-Madison, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Division of Characterization and Post-Irradiation Examination, Government of the United States of America - Division of Characterization and Post-Irradiation Examination, University of Wisconsin-Madison, Government of the United States of America - Idaho National Laboratory, Missouri University of Science and Technology - Department of Materials Science and Engineering and University of Wisconsin-Madison
Downloads 87 (759,537)

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Neutron Irradiation, Irradiation Effects, Microstructural evolution, Compositionally Complex Alloys, high entropy alloys

3.

Multi-Scale, Multi-modal Characterization of Silicon Carbide Cladding Following Safety Testing in the Transient Reactor Test Facility (TREAT)

Number of pages: 37 Posted: 25 Nov 2025
Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Division of Characterization and Post-Irradiation Examination, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and Government of the United States of America - Idaho National Laboratory
Downloads 72 (867,774)

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Silicon Carbide Cladding, micro-mechanical testing, FIB, TEM, 4D-STEM, Electron Energy Loss Spectroscopy (EELS), APT

4.

Correlating Microstructure and Mechanical Properties of Harvested High Dose Zorita Light Water Reactor Internals

Number of pages: 33 Posted: 04 Feb 2024
Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Division of Characterization and Post-Irradiation Examination, Government of the United States of America - Idaho National Laboratory and Government of the United States of America - Idaho National Laboratory
Downloads 53 (1,031,043)

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Irradiated 304 stainless steel (SS, microstructure, atom probe, Transmission electron microscopy, mechanical properties, radiation induced segregation

5.

Discerning the Effect of Various Irradiation Modes on the Corrosion of Zircaloy-4

Number of pages: 40 Posted: 23 Aug 2024
University of Michigan at Ann Arbor - Department of Nuclear Engineering and Radiological Sciences, Government of the United States of America - Naval Nuclear Laboratory, Government of the United States of America - Naval Nuclear Laboratory, Pennsylvania State University - Department of Mechanical and Nuclear Engineering, affiliation not provided to SSRN, affiliation not provided to SSRN, Government of the United States of America - Idaho National Laboratory and University of Michigan
Downloads 48 (1,086,013)

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Zirconium, Corrosion, Irradiation, Radiolysis

6.

Phase stability of a Zr-Ru BCC+B2 eutectic refractory alloy during annealing and proton irradiation

Number of pages: 21 Posted: 04 Apr 2026
University of Texas at El Paso, University of Texas at El Paso, Texas A&M University, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Texas A&M University - Department of Nuclear Engineering and Government of the United States of America - Idaho National Laboratory
Downloads 36 (1,249,711)

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Refractory alloys, Eutectic alloys, BCC+B2, Superalloys, Omega phase

7.

Zr Clustering and Fission Product Segregation in Irradiated Annular U-10zr Fuel Investigated Via Correlative Tem and Apt Characterization

Number of pages: 26 Posted: 16 May 2025
Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Oak Ridge National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, University of Idaho and Government of the United States of America - Idaho National Laboratory
Downloads 35 (1,249,711)

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Metallic fuel, Fission products, Fuel constituent redistribution, Transmission Electron Microscopy, Atom Probe Tomography

8.

High Resolution Microstructural, Chemical Studies and Localized Burnup Analysis in an Irradiated U-10zr Metallic Fuel

Number of pages: 20 Posted: 28 May 2025
Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Division of Characterization and Post-Irradiation Examination, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory and Government of the United States of America - Idaho National Laboratory
Downloads 33 (1,277,121)

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Metallic fuel, irradiation, uranium, zirconium, Transmission electron microscopy, atom probe tomography, Precipitation, isotopes

9.

Electric-Field-Assisted-Sintering of Rare-Earth Oxide Dispersion Strengthened Fe-Cr-Mo Alloys

Number of pages: 19 Posted: 13 May 2025
Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Clemson University, Texas A&M University - Department of Nuclear Engineering, Government of the United States of America - Idaho National Laboratory and Government of the United States of America - Idaho National Laboratory
Downloads 28 (1,345,526)

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Oxide dispersion strengthening, Fe-Cr-Mo alloy, Mechanical alloying, Electric field-assisted sintering, Tensile properties, Atom Probe Tomography

10.

Fission Products in Fuel Cladding Chemical Interaction (FCCI) Region of ATR-Irradiated HT9-Clad U-10MTZ (10MTZ=5Mo-4.3Ti-0.7Zr, wt.%) Metallic Fuel

Number of pages: 33 Posted: 20 Apr 2026
Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, University of Idaho, Government of the United States of America - Idaho National Laboratory and Government of the United States of America - Idaho National Laboratory
Downloads 12 (1,534,404)

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Metallic fuel, Fuel Cladding Chemical Interaction (FCCI), Fission Products, Transmission Electron Microscopy (TEM), Electron Energy Loss Spectroscopy (EELS), Atom Probe Tomography (APT).

11.

TEM characterization of two variants of fuel-cladding chemical interaction in a HT-9 Clad U-10Zr Fuel. Variant 2: FCCI without a Zr Rind

Number of pages: 26 Posted: 30 May 2026
Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, Government of the United States of America - Idaho National Laboratory, University of Florida and Government of the United States of America - Idaho National Laboratory
Downloads 9 (1,561,096)

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Metallic fuel, U-Zr, HT9, fuel-cladding chemical interaction (FCCI), transmission electron microscopy (TEM)