Personal profile
Biography
Craig Marshall, is a Research Associate for the Thermal Property Group of the Characterization and Post-Irradiation Examination Division of the Idaho National Laboratory. In this capacity he operates several instruments to collect data on the thermal properties of nuclear fuels, claddings, and structural materials. These instruments include Differential Scanning Calorimetry (DSC), Laser Flash Analysis (LFA), and Push-Rod Dilatometry.
Marshall received his B.S. degree in metallurgical engineering from the University of Idaho. In the past he worked as a fuel fabrication engineer at Idaho National Laboratory and document coordinator for the Reduced Enrichment Research and Test Reactors Program. In this capacity, he put together As-Built packages for approval to insert experimental test plates in the Advanced Test Reactor. He has also worked as a metallurgical engineer assisting in designing a molten aluminum spray system from start to finish and as a research engineer assisting in the development of new hard-facing alloys. He has co-authored 6 publications, has completed Six Sigma Yellow Belt Training, and speaks Japanese.
Education/Academic qualification
Bachelor, Metallurgical Engineering, University of Idaho
Award Date: May 1 2023
Welding Engineering, Brigham Young University - Idaho
… → 1998
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Collaborations and top research areas from the last five years
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Enhancing thermal conductivity of UO2 with the addition of UB2 via conventional sintering techniques
Watkins, J. K., Wagner, A. R., Middlemas, S. C., Craig Marshall, M., Metzger, K. & Jaques, B. J., Feb 2022, In: Journal of Nuclear Materials. 559, 153421.Research output: Contribution to journal › Article › peer-review
Open Access3 Scopus citations -
Mechanical and Thermophysical properties of low enriched uranium-10wt% molybdenum rolled foils
Schulthess, J., Heighes, M., Michelich, C., Adkins, C., Marshall, M. C., Plummer, M., Lemma, F. D., Trowbridge, T. & Cole, J. I., May 2022, In: Journal of Nuclear Materials. 563, 153628.Research output: Contribution to journal › Article › peer-review
Open Access8 Scopus citations -
Recent Progress in U-10Mo Mechanical and Thermophysical Property Characterization
Schulthess, J. L., Pavlov, T. R., Heighes, M. P., Adkins, C. A., Tan, C., Marshall, M. C., Hanson, W. A., Giglio, J. J. & Cole, J. I., Oct 3 2022.Research output: Contribution to conference › Presentation › peer-review
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Effects of intermetallic compounds on the thermophysical properties of uranium –palladium alloys
Middlemas, S. C., Marshall, M., Adkins, C. A., Di Lemma, F., Tolman, K. R., Benson, M. T. & Hin, C., Jan 5 2021, In: Journal of Alloys and Compounds. 850, 156664.Research output: Contribution to journal › Article › peer-review
Open Access2 Scopus citations -
SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln
Benson, M. T., King, J. A., Mariani, R. D. & Marshall, M., Oct 2017, In: Journal of Nuclear Materials. 494, p. 334-341 8 p.Research output: Contribution to journal › Article › peer-review
Open Access35 Scopus citations