Research Interests:

Experimental investigation of fracture behavior and radiation effects in materials, including: irradiation-induced microstructural evolution and embrittlement in reactor pressure vessel steels and other structural materials in nuclear reactor systems; influence of various environmental factors on fracture toughness and mechanical properties of structural materials.

Education:

• BS, Engineering, U.S. Military Academy, West Point, 1964
• MS, Nuclear Engineering, University of Wisconsin, Madison, 1971
• PhD, Metallurgical Engineering, University of Wisconsin, Madison, 1974

Honors and Awards:

• 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 (ASTM)
• The Metallurgical Society (TMS)
• American Nuclear Society (ANS)

Professional Activities:

• 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 and Task Leader, CRP-8 on “Master curve Approach to Monitor the Fracture Toughness of Reactor Pressure Vessels (RPV) in Nuclear Power Plants”;
  • Member, CRP-5 on "Surveillance Programs Results Application to RPV Integrity Assessment."
• Editor of TRS and author of two chapters for IAEA TRS on "Neutron Radiation Embrittlement of Reactor Pressure Vessels" to be published (2008)
• Author of chapter for IAEA TECDOC on "IAEA Guidelines on Master Curve Application to Reactor Pressure Vessel Integrity Assessment," 2005.
• Editor of TECDOC and author of chapter for IAEA-TECDOC-1441on "Effects Of Nickel On Irradiation Embrittlement Of Light Water Reactor Pressure Vessel Steels," 2005.
• Consultant to IAEA for (1) Evaluation of Mochovce Nuclear Power Plant, and (2) develop strategic plan on NPP management with European Commission
• Member, U.S./Russia Joint Coordinating Committee on Civilian Nuclear Reactor Safety (JCCCNRS) Working Group 3 on Radiation Embrittlement and Annealing of Reactor Vessel (1989-1998).
• 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: