Ronald G. Ballinger, Sc.D.

In addition to his consulting work at Exponent, Dr. Ballinger is a Professor of Nuclear Science and Engineering a Professor of Materials Science and Engineering and Head of the H.H. Uhlig Corrosion Laboratory in the Department of Materials Science and Engineering at MIT. He is active in the teaching of graduate and undergraduate subjects in reactor design, corrosion engineering, chemistry, mechanical behavior, and physical metallurgy.

Dr. Ballinger's areas of specialization are materials selection, advanced alloy development for and engineering of nuclear engineering systems, and environmental degradation and life assessment of these systems. These systems include current light water reactor (LWR), advanced reactor and fusion energy systems. Specific areas of active research are as follows: (1) environmental effects on material behavior, (2) physical metallurgical and electrochemical aspects of environmentally assisted cracking in aqueous systems, (3) experimental as well as modeling and simulation of stress corrosion cracking and hydrogen embrittlement in Light Water Reactor systems, including the effect of radiation (4) the effect of radiation on aqueous chemistry, including experimental as well as modeling and simulation (7) experimental fatigue and fracture mechanics, (8) degradation of materials properties and their effects on component life, (9) nuclear fuel performance including, gas reactor coated particle fuel and environmental degradation, processing, and storage of metallic uranium fuel, and (10) materials development for advanced reactor and fusion systems including, supercritical water, supercritical CO2, liquid metal, high temperature gas reactor and cryogenic structural applications.

Dr. Ballinger is a member of the International Cooperative Group on Environmentally Assisted Cracking of Light Water Reactor Materials (ICG-EAC). The ICG-EAC is charged with the development of methodology for understanding degradation of Light Water Reactor (LWR) materials.

Dr. Ballinger has served or is serving on several DOE committees dealing with the stabilization, processing and disposition of metallic uranium fuel from the production reactors as well as from research reactors including teams to evaluate options for the Hanford, Savannah River, and INEL sites. He also is, or has been, a member of several DOE committees to evaluate advanced reactor options and materials for these options. These committees include: (1) the DOE Independent Technical Review Group (ITRG): Design Features and Technology Uncertainties for the Next Generation Nuclear Plant. The ITRG was tasked with evaluating options for the Next Generation Nuclear Plant (NGNP), (2) The DOE Power Conversion Unit Study Committee tasked with evaluation options for the NGNP power conversion unit, (3) the Idaho National Laboratory Materials Review Board, and (4) the Yucca Mountain Independent Performance Assessment Review Panel.

Dr. Ballinger has consulted extensively in the power industry (nuclear and fossil) as well as chemical, petrochemical and other industries in the areas of environmental degradation, failure analysis, materials selection. Dr. Ballinger is also active in teaching coursed related to materials selection and environmental degradation in industrial settings. His involvements include: (1) participation in summer courses at MIT utility executives, the MIT Reactor Safety Course, a joint MIT-EPRI course. Materials Reliability in Nuclear Power Systems (course developer), and involvement in the MIT-British Petroleum (BP) Operations and Projects Academies.

Dr. Ballinger has authored or co-authored more than 100 scientific publications and is a member of several professional societies including the National Association of Corrosion Engineers, The American Society for Metals, The Electrochemical Society, The American Nuclear Society, and the American Society for Testing and Materials. Professor has served as Chair of the Materials Science and Technology Division of the American Nuclear Society.

Kim, JH, Ballinger RG. SCC crack growth behavior of 316SS welds in BWR environments. Corrosion, in press.

MacLean HJ, Ballinger RG, Kolaya LE, Simonson SA, Lewis N, Hanson ME. The effect of annealing at 1500°C on migration and release of ion implanted silver in CVD silicon carbide. J Nucl Mat 2006; 357(1-3):31-47.

Ballinger RG, Lim J. An overview of corrosion issues for the design and operation of lead and lead-bismuth cooled reactor systems. Nucl Technol 2004; 147(3):418-435.

Loewen EP, Ballinger RG, Lim J. Corrosion studies in support of a medium power lead cooled reactor. Nucl Technol 2004; 147(3):436-457.

Wang J, MacLean H, Ballinger RG. An integrated fuel performance model for the modular pebble bed reactor. Nucl Technol 2004; 147(4).

Long Y, Yuan Y, Ballinger RG, Pilat EE, Kazimi MS. A fission gas release model for high burnup PWR thoria fuel. Nucl Technol 2002; 138(3).

Long Y, Yuan Y, Ballinger RG, Pilat EE, Kazimi MS,. A fission gas release model for high burnup PWR thoria fuel. Nucl Technol 2002; June.

Brisson BW, Ballinger RG, McIlree AR. IGSCC crack initiation and growth in mill annealed Alloy 600 tubing in high temperature caustic. Corrosion 1998; 54(7):504-514.

Jang CH, Grundy DC, Ballinger RG, Steeves MM. Characterization of simulated production welds in Alloy 908. Adv Cryogen Eng 1997; 42:391-398.

Morra MM, Steeves MM, Ballinger RG. The effects of oxygen concentration, stress, temperature and cold work on the constant-load stress-rupture behavior of Incoloy Alloy 908. Adv Cryogen Eng 1997; 42:399-406.

Watanabe Y, Ballinger R, Harling OK, Kohse GE. Effects of neutron irradiation on transpassive corrosion behavior of austenitic stainless steels. Corrosion 1995; 51(9):651-659.

Jang CH, Hwang IS, Ballinger RG, Steeves MM. Development of high toughness weld for Incoloy 908. Adv Cryogen Eng 1994; 40B:1323-1330.

Morra MM, Nicol S, Toma L, Hwang IS, Steeves MM, Ballinger RG. Stress accelerated grain boundary oxidation of Incoloy Alloy 908 in high temperature oxygenous atmospheres. Adv Cryogen Eng 1994; 40B:1291-1298.

Hwang IS, Ballinger RG. A multi-frequency A.C. potential drop technique for the detection of small cracks. J Meas Sci Technol 1992; 3:62-74.

Hwang IS, Morra MM, Ballinger RG, Nakajima H, Shimamoto S, Tobler RL. Charpy absorbed energy and JIC as measures of cryogenic fracture toughness. J Test Eval 1992; 20(4):248-258.

Morra M, Ballinger R, Hwang I. Incoloy 908, a new low coefficient of expansion alloy for high strength cryogenic applications-physical metallurgy. Metallurg Trans 1992; 23A:3177-3192.

Turnbull A, Ballinger R, Hwang I, Morra M, Psaila-Dombrowski M. Hydrogen transport in nickel base alloys. Metallurg Trans 1992; 23A:3231-3244.

Kumar K, Hwang IS, Ballinger RG, Dauwalter CR, Stecyk A. Analysis of palladium cathodes used for heavy water electrolysis. Fusion Technol 1991; 19(1):178-187.

Tobler RL, Reed RP, Hwang IS, Morra MM, Ballinger RG, Nakajima H, Shimamoto S. Charpy impact tests near absolute zero. J Test Eval 1991; 19(1):34-40.

Albagli D, et al. Measurement of neutron and gamma ray emission rates, other fusion products, and power in electrochemical cells having palladium cathodes. J Fusion Energy 1990; 9(2):133-148.

Hwang IS, Ballinger RG, Hosoya K. Electrochemistry of multiphase nickel-base alloys-in aqueous systems. J Electrochem Soc 1989; 136(7).

Steeves M, et al. Progress in the manufacture of the U.S. DPC Test Coil. IEEE Trans Magnet 1989; 25(2).

Hosoya K, Ballinger R, Prybylowski J, Hwang IS. The role of microstructure in environmentally assisted cracking of nickel-base alloys. Corrosion 1988; 44:838-853.

Prybylowski JW, Ballinger RG, Elliott C. Quantitative analytical electron microscopy of multiphase alloys. J Elect Micros Tech 1988; 11.

Prybylowski JW, Ballinger RG. The influence of microstructure on environmentally assisted cracking of alloy 718. Corrosion 1987; 43(2):111-117.

Ballinger RG, Lucas GE, Pelloux RM. The effect of plastic strain on the evolution of crystallographic texture in Zircaloy-2. J Nucl Mat 1984; 126:53-69.

Ballinger RG, Pelloux RMN. The effect of anisotropy on the mechanical behavior of Zircaloy 2. J Nucl Mat 1981; 97(3).

Dobson WG, Biederman RR, Ballinger RG. Zircaloy-4 oxidation in steam under transient oxidizing conditions. ASTM, STP 663, 1977.

Ballinger RG, Dobson WG, Biederman RR. Oxidation reaction kinetics of Zircaloy-2 in an unlimited steam environment. J Nucl Mat 1976; 62(2):3.

Books

Ballinger RG. The anisotropic mechanical behavior of Zircaloy-2. Garland Publishing Co., Inc., New York, 1979.

Presentations and Published Abstracts

Kim JH, Ballinger RG, Stahle PW. SCC crack growth in 316L weld metals in BWR environments. NACE-2008, New Orleans, LA, March 17-21, 2008.

Lim JY, McKrell TJ, Eastwick G, Ballinger RG. Corrosion of materials in supercritical carbon dioxide environments. NACE-2008, New Orleans, LA, March 17-21, 2008.

Ballinger RG. MIT-BP Operations Academy Course. Risk Based Degradation Management, January 2008.

Hixon JR, Kim JH, Ballinger RG. Effect of thermal aging on SCC and mechanical properties of stainless steel weld metals. 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, Whistler, BC, August 19-23, 2007.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Institute for Nuclear Power Operations, June 2007.

Ballinger RG. Reactor materials issues. MIT Nuclear Science & Engineering Department Reactor Safety Course, June 2007.

Ballinger RG, Hejzlar P, Kazimi MS, Kohse GH, Ostrovsky Y, Stahle PW, Xu Z. A new facility for the irradiation of materials at very high temperatures. ICAPP-2006, Reno, NV, June 4-8, 2006.

Lim J, Ballinger RG, Stahle PW, Li N. Effects of chromium and silicon on iron-alloy corrosion in Pb-Bi eutectic. ANS Annual Summer Meeting, Reno, NV, June 4-8, 2006.

Lim J, Li N, Ballinger RG. Materials testing in supercritical CO2. ANS Annual Summer Meeting, Reno, NV, June 4-8, 2006.

Miu KK, Ballinger RG, Li N, Lim J, Rigual DA. The development of autocatalytic structural materials for use in the sulfur-iodine process for the production of hydrogen. ANS Annual Summer Meeting, Reno NV, June 4-8, 2006.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Institute for Nuclear Power Operations, June 2006.

Ballinger RG. Reactor materials issues. MIT Nuclear Science & Engineering Department Reactor Safety Course, June 2006.

Ballinger RG. Critical materials issues for current and advanced nuclear power systems. ASM Meeting, Boston, MA, April 20, 2006.

Lim J, Ballinger RG, Stahle PW. Corrosion resistant alloy development for Pb-Bi eutectic service. ANS Annual Summer Meeting, San Diego, CA, June 5-9, 2005.

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, June 2005.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Institute for Nuclear Power Operations, June 2005.

Wang C, Ballinger RG, Stahle PW, Dimetri E, Koronowski M. Power conversion system design for an indirect cycle, helium cooled pebble bed reactor system. ANS Annual Winter Meeting, Washington, DC, November 15-18, 2004.

MacLean HJ, Ballinger RG. Silver ion implantation and annealing in CVD silicon carbide: The effect of temperature on silver migration. 2nd Topical Meeting on High Temperature Reactors, Beijing, China, September 22-24, 2004.

Wang J, Ballinger RG. Fracture mechanics based coated particle fuel failure models. 2nd Topical Meeting on High Temperature Reactors, Beijing, China, September 22-24, 2004.

Wang J, Ballinger RG, Diecker JT. Design optimization and analysis of coated particle fuel using advanced fuel performance modeling techniques. 2nd Topical Meeting on High Temperature Reactors, Beijing, China, September 22-24, 2004.

Wang J, Ballinger RG, MacLean HJ, Diecker JT. TIMCOAT: An integrated fuel performance model for coated particle duel. 2nd Topical Meeting on High Temperature Reactors, Beijing, China, September 22-24, 2004.

Ballinger RG. Fatigue and fracture of students and other materials: Nuclear engineering—An exciting time. Seminar given at Oak Ridge National Laboratory, July 2004; Los Alamos National Laboratory, July 2004.

Maclean HJ, Ballinger RG. Silver migration in SiC: A new perspective. Global 2003, New Orleans, LA, November 16-20, 2003.

Wang J, Ballinger RG. An improved coated particle fuel failure model. Global 2003, New Orleans, LA, November 16-20, 2003.

Lim J, Ballinger RG, Stahle PW. Fe-Cr-Si alloy development for Pb-Bi eutectic service. Global 2003, New Orleans, LA, November 16-20, 2003.

Wang J, Ballinger RG. The effect of design and uncertainty on coated particle fuel reliability. ANS Annual Summer Meeting, San Diego, CA, June 1-5, 2003.

Lim J, Ballinger RG, Stahle PW. Experimental studies on the corrosion of Fe-Si, Fe-Cr, and Fe0Cr-Si alloys in Pb-Bi eutectic. ANS Annual Summer Meeting, San Diego, CA, June 1-5, 2003.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Institute for Nuclear Power Operations, June 2003.

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, June 2003.

Lim J, Ballinger RG, Loewen E. The effect of silicon on the corrosion of iron in lead-bismuth eutectic. Invited paper. Eleventh International Conference on Nuclear Engineering. Tokyo, Japan, April 20-23, 2003.

Andersson B, Limback M, Wikmark G, Hauso E, Johnsen T, Ballinger RG, Nystrand AC. Test reactor studies of the shadow corrosion phenomena. pp. 583-615. In: Zirconium in the Nuclear Industry: 13th International Symposium, ASTM STP 1423. Moan GD, Rudling P (eds), ASTM International, West Conshohocken, PA, 2002.

Maclean HJ, Ballinger RG. Silver migration and release in thin silicon carbide. ANS Annual Winter Meeting, Washington, DC, November 2002.

Lim J, Ballinger RG, Stahle PW. Experimental study of the corrosion of Fe-Si alloys in liquid Pb. ANS Annual Winter Meeting, Washington, DC, November 2002.

Wang C, Ballinger RG, No HC. Dynamic modeling of modular pebble bed reactor system. ANS Annual Winter Meeting, Washington, DC, November 2002.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Sponsored by National Academy for Nuclear Training, June 2002.

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, June 2002.

Long Y, Ballinger RG, Meyer JE, Kazimi MS. RIA investigation for high burnup ThO2-UO2 fuel. ANS Annual Meeting, Hollywood, FL, June 2002.

Wang CY, Ballinger RG, Stahle PW, Demetri E, Koronowski M. Design of a power conversion system for an indirect cycle, helium cooled, pebble bed reactor system. HTR 2002, pp. 164-174, Petten, Netherlands, April 22-24, 2002.

Kadak A, et al. The MIT pebble bed reactor. ANS Winter Meeting, Reno, NV, November 12-15, 2001.

Wang J, Ballinger RG. A fracture mechanics based failure model for TRISO fuel particles. ANS Winter Meeting, Reno, NV, November 2001.

Wang J, Ballinger RG. An integrated fuel performance model for the modular pebble bed reactor. ANS Winter Meeting, Reno, NV, November 2001.

Lim J, Stahle PW, Ballinger RG. A test system for experimental studies of liquid metal structural material interaction. ANS Winter Meeting, Reno, NV, November 2001.

Wang CY, Ballinger RG, Stahle PW, Demetri E, Koronowski M. Turbo machinery for an indirect, closed, intercooled, helium cycle pebble bed reactor system. ANS Winter Meeting, Reno, NV, November 2001.

Long Y, Yuan Y, Kazimi MS, Ballinger RG. A fission gas release model for high burnup thoria fuel. Trans. ANS, Reno, NV, November 2001.

Ballinger RG. Cutting edge research in nuclear engineering. Seminar at the US Naval Academy, October 19, 2001.

Ballinger RG. Reactor Materials Issues. MIT Nuclear Engineering Department Reactor Safety Course, July 2001.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Sponsored by National Academy for Nuclear Training, June-July 2001.

Takayasu M, Ballinger RG, Goldfarb RB, Squitieri AA, Lee PJ, Larbalestier DC. Multifilamentary Nb3Sn wires reacted in hydrogen gas environment. Presented at CEC-ICMC 2001, I-09A-04, submitted to Advances in Cryogenic Engineering.

Lim J, Ballinger R. Development of a facility for liquid metal-structural material interaction. ANS Winter Meeting, Washington, DC, November 10-12, 2000.

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, July 2000.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Sponsored by National Academy for Nuclear Training, June-July 2000.

Chatelain A, Anderson B, Ballinger RG, Wikmark G. 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, April 10-13, 2000.

Ballinger RG. Competitive nuclear power? Yes: The case for the pebble bed reactor. American Nuclear Society, Northeastern Section, December 1, 1999.

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, July 1999.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Sponsored by National Academy for Nuclear Training, June-July 1999.

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, July 1998.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Sponsored by National Academy for Nuclear Training, June-July 1998.

Brisson BW, Ballinger RG, McIlree AR. 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, August 10-14, 1997.

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, July 1997.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Sponsored by National Academy for Nuclear Training, June-July 1997.

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, July 1996.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Sponsored by National Academy for Nuclear Training, June-July 1996.

Ballinger RG. Technical and political issues related to the DPRK weapons program. American Nuclear Society, Northeastern Section, February 28, 1996.

Shoji T, Suzuki S, Ballinger R. Theoretical prediction of SCC growth behavior-threshold and plateau growth rate. 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, pp. 881-892, Breckenridge, CO, August 7-10, 1995.

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

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, July 1995.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives, Sponsored by National Academy for Nuclear Training, June-July 1995.

Ballinger RG. Integration of management and technology for improved power plant performance. Participant, Lecturer, June 1995.

Ballinger RG. Irradiation induced segregation and it’s effect on IASCC. Seminar given at Korea Atomic Energy Research Institute and Korea Advanced Institute of Technology, May 30, 1995.

Ballinger RG. Fuel degradation issues at the DPRK Nyongbyon reactor site. Seminar given at Korea Atomic Energy Research Institute, May 29, 1995.

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

Ballinger RG. Steam generator degradation. Seminar given at Korea Atomic Energy Research Institute, May 27, 1995.

Ballinger RG. Society of Automotive Engineers-short course on corrosion engineering. March 2-3, 1995.

Ballinger RG, Johnson AB, Jr., Simpson KA. Kinetic and thermodynamic bases to resolve issues regarding conditioning of uranium metal fuels. DOE Spent Nuclear Fuel Challenges & Initiatives, Salt Lake City, UT, December 13-16, 1994.

Ballinger RG. Reactor materials issues. MIT Nuclear Engineering Department Reactor Safety Course, July 1994.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Sponsored by National Academy for Nuclear Training, June-July 1994.

Ballinger RG. Integration of management and technology for improved power plant performance. Participant, Lecturer, June 1994.

Ballinger RG. Materials selection. DOE Intern Program, MIT, June 1994.

Ballinger RG. Participant (lecturer) in MIT reactor technology program for utility executives. Sponsored by National Academy for Nuclear Training, June-July 1993.

Ballinger RG. Crack and crevice chemistry modeling in aqueous systems. University of Virginia, Department of Materials Science seminar series, May 12, 1992.

Murphy J, Ballinger R, Becker H, Gwinn D, Methew S. Turbogenerator Flywheel For Alcator C-Mod. 14th Symposium on Fusion Engineering, San Diego, CA, October 1-3, 1991.

Psaila-Dombrowski M, Turnbull A, Ballinger RG. Modelling the electrochemistry in cracks and crevices in boiling water reactor environments. Conference on Life Prediction of Corrodible Structures, Cambridge, UK, September 23-26, 1991.

Ballinger RG. IASCC of boiling water reactor structural materials. New York (Schenectady Chapter) Joint ASM/ANS Monthly Meeting, September 12, 1991.

Lidar P, Ballinger R, Hwang I. The use of potential drop techniques for the evaluation of environmentally assisted cracking of austenitic alloys. International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Monterey, CA, August 25-31, 1991.

Oka T, Ballinger R, Hwang I. Modelling of hydrogen assisted cracking of Ni-base Alloy X-750 in water. International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Monterey, CA, August 25-31, 1991.

Shoji T, Yamaki K, Ballinger R, Hwang I. Grain boundary segregation and intergranular stress corrosion cracking susceptibility of austenitic stainless steels in high temperature water. International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Monterey, CA, August 25-31, 1991.

Hwang IS, Ballinger RG, Morra MM, Tao B, Mathew S. Improved mechanical properties of Alloy 718 by anneal and direct aging process for nuclear fusion applications. International Symposium on the Metallurgy and Applications of Superalloys 718, 625 and Various Derivatives, ASM/NACE, pp. 621-634, Pittsburgh, PA, June 23-26, 1991.

Ballinger RG. Your MIT education and your role in society. Tau Beta Pi initiation banquet, May 9, 1991.

Harling OK, Kohse GE, Driscoll MJ, Ballinger RG. In-Pile Facilities for LWR Materials and Chemistry Studies at the MIT Research Reactor. JAIF International Conference on Water Chemistry in Nuclear Power Plants, Fukui City, Japan, April 22-25, 1991.

Hwang I, Ballinger R, Morra M, Steeves M. Mechanical properties of Incoloy 908—An update. ICMC/CEC 91, Huntsville AL, April 1-5, 1991.

Ballinger RG. Cold fusion—The science and the politics. Gordon Institute, Distinguished Speaker Lecture Series, January 16, 1991.

Psaila-Dombrowski M, Turnbull A, Ballinger R. Implications of crevice chemistry for cracking of BWR recirculating inlet safe-ends. UK Corrosion 90, Surrey, October 29-31, 1990.

Ballinger RG. Cold fusion—Where have we been and where are we going, a critical perspective. ASME Boston Section, May 10, 1990.

Ballinger RG. Symposium on Cold Fusion, Current Status of International Scientific Findings. Special Panel Discussion at Corrosion ‘90, Las Vegas, NV, April 24, 1990.

Turnbull A, Ballinger RG, Hwang IS, Gates RM. The influence of microstructure on hydrogen transport in nickel-base alloys. Proceedings, 4th International Conference on The Effect of Hydrogen on The Behavior of Materials, pp. 121-132, Moran, WY, September 12-15, 1989.

Morra MM, Hwang IS, Ballinger RG, Steeves MM, Hoenig MO. Effect of cold work and heat treatment on the 4°K tensile, fatigue and fracture toughness properties of Incoloy 908. 11th International Conference on Magnet Technology (MT-11), Tsukuba, Japan, August 28-September 1, 1989.

Harling OK, et al. Engineering activities at the MIT research reactor in support of power reactor technology. 1989 ANS Reactor Operations Topical Meeting, Charlotte, NC, August 6-9, 1989.

Ballinger RG. Observations on the Impact of Cold Fusion Research. Invited lecture at the spring meeting of the American Nuclear Society, Atlanta, GA, June 4, 1989.

Luckhardt SC, et al. Measurements of neutron and gamma ray emission rates and calorimetry in electrochemical cells having palladium cathodes. APS Meeting Baltimore, MD, June 1, 1989.

Ballinger RG. Cold fusion confusion. Special Seminar at College of Engineering, Northeastern University, Boston, MA, May 25, 1989.

Ballinger RG. Cold fusion confusion. MIT Chapter, Society of Sigma XI, May 18, 1989.

Ballinger RG. Comments on cold fusion. Testimony presented to the Committee on Science, Space & Technology, U.S. House of Representatives, Washington, DC, April 26, 1989.

Ballinger RG. Cold fusion confusion. Special Seminar at Corrosion '89, New Orleans, LA, April 18, 1989.

Ballinger RG. Electrochemical aspects of environmentally assisted cracking in Ni-Cr-Fe alloys. Corrosion ‘89, Corrosion Research Symposium, New Orleans, LA, April 18, 1989.

Morra, M, Ballinger RG, Hwang IS. The relationship between processing, structure, and properties of a new high strength, low coefficient of expansion alloy for cryogenic service. 1989 TMS Annual Meeting, Las Vegas, NV, February 27-March 2, 1989.

Ballinger RG. The role of the material/environment interface in environmentally assisted crack growth in aqueous systems. Seminar at Rensselaer Polytechnic Institute, Department of Materials Engineering, Troy, NY, January 26, 1989.

Ballinger RG. Electrochemical aspects of environmentally assisted cracking. Seminar at Battelle Pacific Northwest Laboratories, November 11, 1988.

Ballinger RG. Fusion energy—A challenge for engineering materials. Meeting of Boston Section of American Society for Metals, November 3, 1988.

Becker H, Ballinger RG. 316LN forgings for Alcator C-Mod; metallurgical and design considerations. 11th Cryogenic Structural Materials Workshop, Colorado Springs, CO, October 18-19, 1988.

Ballinger RG, Elliott CS, Hwang IS. Corrosion fatigue of alloy X-750 in aqueous environments. International Conference on Environment Induced Cracking of Metals, Kohler, WI, October 2-7, 1988.

Driscoll MJ, et al. The MIT in-pile loops for coolant chemistry and corrosion studies. 1988 JAIF International Conference on Water Chemistry in Nuclear Power Plants, Tokyo, Japan, April 19-22, 1988.

Hwang IS, Ballinger RG, Hosoya K. High temperature electrochemistry of precipitation hardened nickel base alloys in aqueous systems. 172nd Meeting of the Electrochemical Society, Honolulu, HI, October 18-23, 1987.

Steeves MM, et al. The US-DPC. A poloidal coil test insert for the Japanese demonstration poloidal coil test facility. Tenth International Conference on Magnet Technology, Boston, MA, September 21-25, 1987.

Martin JL, Ballinger RG, et al. Tensile, fatigue and fracture toughness properties of a new low coefficient of expansion cryogenic structural alloy, Incoloy 9XA. International Conference on Cryogenic Materials and Cryogenic Engineering, St. Charles, IL, June 14-18, 1987.

Morra M, Ballinger RG, et al. Incoloy 9XA, a new low coefficient of thermal expansion sheathing alloy of use in ICCS magnets. International Conference on Cryogenic Materials and Cryogenic Engineering, St. Charles, IL, June 14-15, 1987.

Ballinger RG. Incoloy 9XA, a new low coefficient of thermal expansion sheathing alloy of use in ICCS magnets. International Conference on Cryogenic Materials and Cryogenic Engineering, St. Charles, IL, June 12, 1987.

Ballinger RG. Tensile, fatigue, and fracture toughness properties of a new low coefficient of expansion cryogenic structural alloy, Incoloy 9XA. International Conference on Cryogenic Materials and Cryogenic Engineering, St. Charles, IL, June 11, 1987.

Ballinger RG, et al. Low coefficient of expansion structural materials development for conductor applications. 9th Annual Cryogenic Structural Materials Workshop, Reno, NV, October 6-8, 1986.

Prybylowski JW, Ballinger RG. The influence of microstructures on environmentally assisted cracking of alloy 718. Corrosion ‘86, Houston, TX, March 17-21, 1986.

Ballinger RG, Prybylowski JW. An overview of advanced high strength nickel base alloys for LWR applications. EPRI Workshop on Advanced High Strength Materials for LWR Internal Applications, Clearwater Beach, FL, March 12-13, 1986.

Ballinger RG, Prybylowski JW, Elliott CK. Effect of processing history and chemistry on the structure of nickel base superalloys. Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Monterey, CA, September 9-12, 1985.

Ballinger RG. Fracture in nickel base alloys in nuclear power system environments. Keynote Lecturer at the Washburn Dedication Symposium in Materials Engineering, given at Worcester Polytechnic Institute, March 29, 1985.

Ballinger RG, Moshier WC, Siebein KN, Latanision RM. A Study of the thermal aging behavior in alloy 600 tubing. 9th International Congress on Metallic Corrosion, pp. 265-273, Toronto, Canada, June 3-7, 1984.

Sheeks CK, Ballinger RG, Latanision RM. Fatigue crack growth of inconel alloy X-750 in simulated PWR and BWR environments. 9th International Congress on Metallic Corrosion, pp. 310-316, Toronto, Canada, June 3-7, 1984.

Sheeks CK, Moshier WC, Ballinger RG, Latanision RM, Pelloux RM. Fatigue crack growth of alloys X-750 and 600 in simulated PWR and BWR environment. International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, Myrtle Beach, SC, August 22-25, 1983.

Ballinger RG. Pattern recognition techniques for alloy development. Seminar given at TRW, Inc., Caldwell Labs, Euclid, OH, July 12, 1983.

Ballinger RG. Advanced fuel design and performance. Short course given at Westinghouse Electric Corporation, Water Reactor Divisions, July 11, 1983.

Ballinger RG. Thermal behavior of nuclear fuel rods, thermal-hydraulic design and safety for light water reactors. Center for Advanced Engineering Study, MIT, May 16-21, 1983.

Ballinger RG. Corrosion fatigue in Alloy X-750. Seminar given at Cruesot Loire Laboratories, Firminy, France, March 29, 1983.

Ballinger RG. Fatigue in nickel base alloys. Seminar given at Framatome, Paris, March 28, 1983.

Ballinger RG. Environmentally assisted cracking of nickel-base alloys for nuclear applications. MIT Industrial Liaison Program Symposium on Corrosion. December 1982.

Ballinger RG, et al.. Fission gas release and fuel reliability at extended burnup. pp. 4-35. Topical Meeting on LWR Extended Burnup, Fuel Performance and Utilization, Williamsburg, VA, April 4-8, 1982.

Ballinger RG, Latanision RM, Moshier WC, Pelloux RMN. The role of uncertainty in the measurement of crack length by compliance techniques. International Conference on Subcritical Crack Growth, pp. 261-285, Freiberg (W. Ger.), May 13-15, 1981.

Ballinger RG, Christensen R, Eilbert R, Oldberg S, Rumble E, Was GS. Clad failure modeling progress. Fifth International Conference on Zirconium in the Nuclear Industry, August 1980.

Was GS, Tischner HH, Hall EL, Latanision RM, Ballinger RG, Pelloux RMN. Effects of Heat Treatment on Segregation and Precipitation of Trace Elements in Inconel 600. Environmental Fracture Session 1, Fall Meeting of TMS-AIME, Milwaukee, WI, September 1979.

Ballinger RG, Pelloux RMN. The anisotropic mechanical behavior of Zircaloy-2. 3rd International Conference on Mechanical Behavior of Materials, Vol. 2, pp. 685-695, Cambridge UK, August 1979.

• Founder, Altran Materials Engineering (now a part of Altran Solutions)

• Tau Beta Pi (member)
• Sigma XI (associate member)
• Pi Tau Sigma (member)
• American Nuclear Society (member; Past Chair, Materials Science & Technology Division)
• American Society for Metals (member)
• TMS (member)
• National Association of Corrosion Engineers (member)
• American Society for Testing and Materials (member)