Faculty

Ronald G. Ballinger

 

Disciplines

Research

Research Interests

  • Environmental effects on materials behavior
  • Electrochemistry
  • Corrosion
  • Advanced materials for fusion systems advanced statistical and experimental techniques for experimental analysis
  • Nuclear fuel performance analysis

Recent Professional Service

  • US Department of Energy Technical Assistance Group (TAG) for Disposition of N-Reactor Fuel
  • US Department of State Technical Advisory Committee on Conditioning of North Korean Reactor (DPRK) Fuel
  • US Department of Energy Technical Advisory Committee on Disposition of Savannah River Reactor Site Metallic Fuel
  • American Nuclear Society, Materials Science and Technology Division, Committee Member


Major Product Development

Responsible for the conception, development, and bringing to commercial acceptance of a super alloy, Alloy 908, for use in cryogenic magnet systems. This alloy was chosen as the sheath material for ITER (International Thermonuclear Experimental Reactor).

 

Selected Publications

Papers in Refereed Journals

Y. Watanabe, R. Ballinger, O.K. Harling, G.E. Kohse, "Effects of Neutron Irradiation on Transpassive Corrosion Behavior of Austenitic Stainless Steels," Corrosion 51 (9), 1995, pp. 651-659.

B.W. Brisson, R.G. Ballinger, A.R. McIlree, "IGSCC Crack Initiation in Mill Annealed Alloy 600 Tubing in High Temperature Caustic," Corrosion 54 (7), 1998, pp. 504-514.

Papers in Refereed Conferences

T. Shoji, S. Suzuki, R. Ballinger, "Theoretical Prediction of SCC Growth Behavior-Threshold and Plateau Growth Rate." Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Breckenridge, CO, 8/7-8/10/95, 881-892.

C.H. Jang, D.C. Grundy, R.G. Ballinger, M.M. Steeves, "Characterization of Simulated Production Welds in Alloy 908," Adv. in Cryogenic Eng., in press.

M.M. Morra, M.M. Steeves, R.G. Ballinger, "The Effects of Oxygen Concentration, Stress, Temperature and Cold Work on the Constant-Load Stress-Rupture Behavior of Incoloy Alloy 908," Adv. in Cryogenic Eng., in press.

B.W. Brisson, R.G. Ballinger, A.R. McIlree, "IGSCC Crack Initiation in Mill Annealed Alloy 600 Tubing in High Temperature Caustic," Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Amelia Island, FL, 8/10-8/14/97.

A. Chatelain, B. Anderson, R.G. Ballinger, G. Wikmark, "Enhanced Corrosion of Zirconium-Base Alloys in Proximity to Other Metals: The Shadow Effect," International Topical Meeting on Light Water Reactor Fuel Performance, Park City, UT, 4/10-4/13/2000.

Invited Lectures

March 2-3, 1995. Society of Automotive Engineers - Short Course on Corrosion Engineering.

May 27, 1995. "Steam Generator Degradation," Seminar given at Korea Atomic Energy Research Institute.

May 28, 1995. "Plant Conditioning Monitoring," Seminar given at Korea Atomic Energy Research Institute.

May 29, 1995. "Fuel Degradation Issues at the DPRK Nyongbyon Reactor Site," Seminar given at Korea Atomic Energy Research Institute.

May 30, 1995. "Irradiation Induced Segregation and Its Effect on IASCC," Seminar given at Korea Atomic Energy Research Institute and Korea Advanced Institute of Technology.

June 1995. "Integration of Management and Technology for Improved Power Plant Performance," Participant, Lecturer.

June-July 1995. Participant (Lecturer) in MIT Reactor Technology Program for Utility Executives, Sponsored by National Academy for Nuclear Training.

July 1995. "Reactor Materials Issues," MIT Nuclear Engineering Department Reactor Safety Course.

July 27, 1995. "Degradacion Ambiental-Falta de Relacion Entre la Corrosion General y Localizada," UNEXPO, Puerto Ordaz, Venezuela.

February 28, 1996. "Technical and Political Issues Related to the DPRK Weapons Program," American Nuclear Society, Northeastern Section.

June-July 1996. Participant (Lecturer) in MIT Reactor Technology Program for Utility Executives, Sponsored by National Academy for Nuclear Training.

July 1996. "Reactor Materials Issues," MIT Nuclear Engineering Department Reactor Safety Course.

June-July 1997. Participant (Lecturer) in MIT Reactor Technology Program for Utility Executives, Sponsored by National Academy for Nuclear Training.

July 1997. "Reactor Materials Issues," MIT Nuclear Engineering Department Reactor Safety Course.

June-July 1998. Participant (Lecturer) in MIT Reactor Technology Program for Utility Executives, Sponsored by National Academy for Nuclear Training.

July 1998. "Reactor Materials Issues," MIT Nuclear Engineering Department Reactor Safety Course.

June-July 1999. Participant (Lecturer) in MIT Reactor Technology Program for Utility Executives, Sponsored by National Academy for Nuclear Training.

July 1999. "Reactor Materials Issues," MIT Nuclear Engineering Department Reactor Safety Course.

December 1, 1999. "Competitive Nuclear Power? Yes: The Case for the Pebble Bed Reactor," American Nuclear Society, Northeastern Section.

Related News

BP announced research plans with MIT and University of Manchester
BP is supporting a new program on materials and corrosion research, as it applies to oilfield applications.
February 10, 2010