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Sohail Shah

Government of the United States of America - Idaho National Laboratory

SCHOLARLY PAPERS

11

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Scholarly Papers (11)

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1.

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

Number of pages: 11 Posted: 12 Dec 2023
Benjamin Dacus, Mukesh Bachav, Sohail Shah, Myles Stapelberg, Courtney Tower, Quincy Johnson, Angus P. C. Wylie, Cody A. Dennett, Yang Zhang, Zhongwu Zhang and Michael Short
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 98 (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
Nathan Curtis, Sohail Shah, Mukesh Bachav, Kaustubh Bawane, Fei Teng, Calvin Parkin, Tiankai Yao, Prof. Haiming Wen and Adrien Couet
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 88 (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
Guang Yang, Tanner Mauseth, Arnold Pradhan, Sohail Shah, Cameron Howard, Tiankai Yao, Mario MATOS, Jason Schulthess, Fei Teng, Daniel Murray, Mukesh Bachav, Sean Gonderman, Jack Gazza, Madeline Feltus, Fei Xu and Peng Xu
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, Idaho National Laboratory and Government of the United States of America - Idaho National Laboratory
Downloads 73 (867,774)

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

4.

Effect of Cyclic Ageing on the Early-Stage Clustering in Al-Zn-Mg(-Cu) Alloys

Number of pages: 20 Posted: 14 Mar 2022
Sohail Shah, Elisabeth Thronsen, Sigurd Wenner, Calin Marioara, Randi Holmestad and Bjørn Holmedal
Government of the United States of America - Idaho National Laboratory, affiliation not provided to SSRN, SINTEF Industry, SINTEF Industry, Norwegian University of Science and Technology (NTNU) - Department of Physics and Norwegian University of Science and Technology (NTNU) - Department of Materials Science and Engineering
Downloads 65 (924,743)

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Aluminum alloys, Atom probe tomography (APT), Transmission electron microscopy (TEM), Cyclic ageing, Natural ageing

5.

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

Number of pages: 33 Posted: 04 Feb 2024
Mukesh Bachav, Sohail Shah, Cameron Howard, Boopathy Kombaiah, Sriswaroop Dasari, Fei Teng, Yachun Wang and Jason Daniel
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

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
Nasim Mahmud Polash, Jose Talamantes Chavez, Benjamin Mejia Diaz, Sohail Shah, Mukesh Bachav, Boopathy Kombaiah, Lin Shao and Sriswaroop Dasari
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 44 (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
Arnold Pradhan, Sohail Shah, Daniele Salvato, Jason Harp, Luca Capriotti, Mukesh Bachav, Indrajit Charit and Tiankai Yao
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 38 (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
Sohail Shah, Anshul Kamboj, Kourtney Wright, Daniele Salvato, Arnold Pradhan, Daniel Murray, Luca Capriotti, Tiankai Yao and Mukesh Bachav
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 34 (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
Sohail Shah, xinchang zhang, Cheng Sun, Lin Shao, Jorgen F. Rufner and Mukesh Bachav
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 29 (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.

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
Bao-Phong Nguyen, Daniele Salvato, Sohail Shah, Fidelma Di Lemma, Luca Capriotti, Mukesh Bachav, Tiankai Yao, Assel Aitkaliyeva and Yachun Wang
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 15 (1,561,096)

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

11.

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
Arnold Pradhan, Tiankai Yao, Sohail Shah, Jatuporn Burns, Mukesh Bachav, Indrajit Charit, Colby Jensen and Yachun Wang
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).