Jeremy Todd Busby
Research Scientist
Nuclear Materials Science & Technology Group
Materials Science & Technology Division
Oak Ridge National Laboratory
P.O.Box 2008
Oak Ridge, TN 37831-6138
Phone: (865) 241-4622
Fax: (865) 241-3650
e-mail: busbyjt@ornl.gov

Education:

  • Bachelor of Science in Nuclear Engineering, December 1995, Kansas State University, Manhattan, KS.  Cum Laude
  • Masters of Science in Nuclear Engineering, December 1998, University of Michigan, Ann Arbor, MI
  • PhD in Nuclear Engineering, December 2000, University of Michigan, Ann Arbor, MI.

Professional Experience and Interests

Currently, Dr. Busby leads the Advanced Structural Materials Development program in support of GNEP as well as leading material development efforts for ITER shield modules and space reactors.  Dr. Busby’s experience and other interests include:  irradiation effects in metals for high temperature reactors, fusion reactors, and spacecraft reactors, radiation-effects in refractory metals, identifying the mechanisms of embrittlement for materials under high temperature irradiation, scanning and transmission electron microscopy and techniques for measuring chemical composition, radiation-damage fundamentals, identifying and understanding the controlling mechanism of irradiation-assisted stress corrosion cracking (IASCC), post-irradiation annealing, and localized deformation of irradiated materials.

  • 11/04 to present:  Research Staff (Oak Ridge National Laboratory)
    Current activities:
    • National Program Manager for GNEP Advanced Structural Materials Program
    • Reactor Materials Lead for NASA-DOE Space-Fission Power System Program
    • Program Manager for US-ITER Cast Stainless Steel Development Program
  • 11/04 to present:  Adjunct Assistant Professor of Nuclear Engineering and Radiological Sciences (University of Michigan)
  • 1/01 to 11/04:  Assistant Research Scientist (University of Michigan)
  • 1/96 to 12/00: Graduate Student Research Assistant

Honors and Awards:

  • ORNL Early Career Award for Engineering Accomplishment, 2007
  • ORNL Significant Event Award, 2007
  • ANS Landis Young Member Achievement Award, 2006
  • Literary Award, ANS Materials Science and Technology Division, 2002
  • NERS Graduate Student of the Year: University of Michigan, 2000
  • Award of Appreciation, American Society for Testing and Materials Committee E-10, 1997
  • Best Paper Award, American Nuclear Society, 1994
  • Award of Appreciation, American Society for Testing and Materials Committee E-10, 1993
  • Fellow, ASM International, 1992
  • Award of Appreciation, American Society of Mechanical Engineers, 1990
  • Martin Marietta Energy Systems Publication Award, 1989
  • Martin Marietta Energy Systems Technical Achievement Award, 1988
  • W. H. Hobart Memorial Medal, American Welding Society, 1985
  • Best Paper Award, Ductile Iron Division, American Foundrymen's Society, 1975

Societies:

  • ASM International
  • American Society for Testing and Materials

Professional Activities:

  • ANS Materials Science and Technology Division Executive Committee, 2004-present
  • TMS Nuclear Materials Executive Committee, 2003-present
  • Co-Organizer for International Symposium on Environmental Degradation (2005-2011)
  • Co-Organizer for ASTM Radiation Effects on Materials Conference (2004-2010)
  • Officer, International Group on Radiation Damage Mechanisms (IGRDM), 1989 — present
  • Member, Subcommittee on Materials, ASME Boiler and Pressure Vessel Code; formerly Chairman, Subgroup on Toughness
  • Member, American Society for Testing and Materials Committee E-8 on Fracture and Fatigue Testing of Materials
  • Member, American Society for Testing and Materials Committee E-10 on Nuclear Technology and Applications
  • International Atomic Energy Agency (IAEA) activities:
    • Chairman, CRP-6 on "Nickel Mechanisms Effects on RPV Steels"
    • Member, CRP-5 on "Surveillance Programs Results Application to RPV Integrity Assessment"
    • Co-editor and author of two chapters for IAEA TRS on "Neutron Radiation Embrittlement of Reactor Pressure Vessels" to be published (2004)
    • Author of chapter for IAEA TECDOC on "IAEA Guidelines on Master Curve Application to Reactor Pressure Vessel Integrity Assessment," to be published (2004)
    • Consultant to IAEA for (1) Evaluation of Mochovce Nuclear Power Plant, and (2) develop strategic plan on NPP management with European Commission
  • General Chairman and Editor of Proceedings, 18th ASTM International Symposium on Effects of Radiation on Materials, 1996
  • Co-Chairman and Editor of Proceedings, 17th ASTM International Symposium on Effects of Radiation on Materials, 1994
  • Co-Chairman and Editor of Proceedings, 16th ASTM International Symposium on Effects of Radiation on Materials, 1992
  • Consultant to Kernkraftwerk Obrigheim (KWO) GmbH on evaluation of the KWO Reactor Pressure Vessel, Obrigheim am Neckar, Germany, 1995
  • Consultant to Preussen Elektra Aktiengesellschaft, on evaluation of the Kernkraftwerk Stade (KKS) Reactor Pressure Vessel, Hannover, Germany, 1998

Scope of Research:

  • Experimental fracture mechanics with emphasis on elastic-plastic behavior to provide techniques for characterizing material parameters critical to the fracture process
  • Fracture studies of low-alloy pressure vessel steels to provide engineering data for structural integrity assessments of nuclear reactor vessel, coal conversion pressure vessels, etc ., including statistical evaluation
  • Metallurgical studies of nuclear reactor vessel steels to simulate irradiated properties for performance of large fracture mechanics experiments
  • Irradiation studies of low-alloy steels and stainless steels to determine effects of neutron irradiation on mechanical properties and fracture toughness of light-water nuclear reactors
  • Fracture toughness studies of graphite materials for nuclear reactor and space applications and of nodular cast irons with emphasis on microstructural interactions
  • Irradiation studies of advanced high temperature structural materials for Generation IV reactors
  • Materials studies including fracture properties, radiation effects, and characterization for evaluation of High-Flux Isotope Reactor pressure vessel

Selected Publications:





 Oak Ridge National Laboratory