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Doug C. Crawford

Chief Scientist

Research Areas:
Nuclear Engineering; Nuclear Fuels


As the Chief Scientist for the Materials & Fuels Complex, Doug Crawford is responsible for implementing strategies to modernize the MFC research capabilities to impact the deployment of advanced nuclear energy technology, foster collaborations with nuclear universities and laboratories, and facilitate delivery of outcomes for industrial partnerships to meet fuels and materials research and development needs. Crawford had previously worked at Argonne National Laboratory-West and INL in increasingly responsible leadership positions, with emphasis on R&D of nuclear fuels and materials. In 2007, Crawford worked at GE Hitachi Nuclear Energy leading engineering teams supporting boiling water reactor customers with fuel technology, reactor systems and components engineering, and reactor plant mechanical analysis. Crawford also worked at Oak Ridge National Laboratory as reactor technology leader and GAIN deputy director before rejoining INL.


Bachelor's degree, metallurgical engineering, University of Idaho, 1984

Master's degree, nuclear engineering, University of Washington, 1986

Doctorate, nuclear engineering, University of Michigan, 1991

MBA, University of Chicago, 2005

Douglas C. Crawford, Douglas L. Porter, Steven L. Hayes, “Fuels for sodium-cooled fast reactors: US perspective,” Journal of Nuclear Materials 371 (2007) 202–231.

Douglas C. Crawford, Douglas L. Porter, Steven L. Hayes, Mitchell K. Meyer, David A. Petti, Kemal Pasamehmetoglu, “An approach to fuel development and qualification,” Journal of Nuclear Materials 371 (2007) 232–242.

L. C. Walters, D. L. Porter, and D. C. Crawford, “Nuclear Fuel Considerations for the 21st Century,” International Seminar on Advanced Nuclear Energy Systems Toward Zero Release of Radioactive Wastes, in Progress in Nuclear Energy, Vol. 40, No. 3-4 (2002), pp. 513-521.

Editor, "Proceedings of the International Symposium on Fuels for Liquid Metal Reactors," Chicago, IL, November 15-20, 1992, published in Journal of Nuclear Materials 204 (1993) 1- 270.

R.G. Pahl, D.L. Porter, D.C. Crawford, and L.C. Walters, "Irradiation Behavior of Metallic Fast Reactor Fuels," Journal of Nuclear Materials 188 (1992) 3-9.

D.C. Crawford and G.S. Was, "The Role of Grain Boundary Misorientation in Intergranular Cracking of Ni-16Cr-9Fe in 360°C Argon and High Purity Water," Metallurgical Transactions A, 23A (1992), 1195-1206.

P. Cantonwine, D. Crawford, M. Downs, B. Joe, T. Bahensky, J. Reimer, C. del laHoz, K. Petersen, M. Reitmeyer, J. Morris, A. Zbib, “Channel - Control Blade Interference Management at LaSalle 1 and 2 during 2007 and 2008,” Proceedings of Top Fuel 2009, September 6-10, 2009, Paris, France, Paper 2154.

D. C. Crawford, R. J. Schneider, and A. A. Lingenfelter, “GNF Fuel Performance Update,” American Nuclear Society 2008 Winter Meeting, Reno, NV, November 9-13, 2008, Trans. Am. Nucl. Soc., 99 (2008).

D. C. Crawford, A. E. Wright, R. W. Swanson, and R. E. Holtz, “RIA Testing Capability of the Transient Reactor Test Facility,” Proceedings of the IAEA Technical Committee Meeting on Fuel Cycle Options for LWRs and HWRs, Victoria, Canada, May 1998, IAEA-TECDOC- 1122, pp. 99-109.

D. C. Crawford, D. L. Porter, S. L. Hayes, and R. N. Hill, “Fuel Element Design for the Enhanced Destruction of Plutonium in a Nuclear Reactor,” U. S. Patent No. 5,887,044, Issued March 23, 1999.

  • April 2008 GE Hitachi Nuclear Quality Cup Team Member

  • ANS Materials Science and Technology Division 2006 Significant Contribution Award

  • ANS 1996 Young Member Engineering Achievement Award

  • ANL Exceptional Performance Awards

  • ANS Materials Science and Technology Division Scholarship

  • Tau Beta Pi, Phi Gamma Delta chapter Outstanding Senior

  • Ziegler Foundation Scholarship at University of Idaho

Research Interests:

​Crawford's subject matter expertise includes fast reactor and boiling water reactor fuel performance and design, fuel safety testing and licensing, fuel specification, technical leadership and issue resolution, and nuclear materials storage technology.

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