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:
- Special Award, American Nuclear Society (ANS), 2010
- Peter D. Hedgecock Award, American Society for Testing and Materials International Committee E10 on Nuclear Technology and Applications, 2010
- Award of Appreciation, American Society for Testing and Materials Committee E10, 1997
- Best Paper Award, American Nuclear Society, 1994
- Award of Appreciation, American Society for Testing and Materials Committee E10, 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 and author of two chapters for IAEA Book on "Assessment of Irradiation embrittlement effects in reactor pressure vessel steels”, Nuclear Energy Series. No. NP-T-311 (2006)
- Author of chapter for IAEA TRS-429 on "IAEA Guidelines on Master Curve Application to Reactor Pressure Vessel Integrity Assessment," 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:
- Coordinator for ORNL High-Flux Isotope Reactor Surveillance Program
- 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, stainless steels and high nickel alloys 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 |
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