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Ronald W. King
EXPERIENCE SUMMARY
Mr. King has 31 years of technical and management experience at increasing
levels of responsibility in development of nuclear energy technologies,
particularly in the area of sodium-cooled fast reactors and operational
safety at Argonne National Laboratory (ANL). He has been involved in fast
reactor projects in the US and internationally, and in other U.S.
Department of Energy nuclear energy and national security programs. He has
specific experience in systems engineering and operational safety analysis
of liquid metal-cooled reactors and systems. Mr. King has served in senior
management positions at ANL involving these and other engineering
activities related to nuclear systems design, development, technical
evaluation, and safety documentation. He was the Senior Technical Advisor
for the engineering tasks supporting design of systems for deactivating
and draining the sodium coolant from the BN-350 fast breeder reactor in
the Republic of Kazakhstan, working jointly with engineers and managers
from the U.S. and Kazakhstan. He developed and managed the plant-life
extension/aging management program for the EBR-II reactor, the first of
its kind for a sodium-cooled reactor. Mr. King transferred to the new
Idaho National Laboratory in 2005, and refocused his efforts on technical
work for the development of a new fast-neutron test reactor, and
supporting the formation of a nuclear utility advisory board for advising
the new INL on nuclear power issues.
Professional Employment Overview:
2005-2006: Staff Engineer, Fission and Fusion Systems Engineering
Department, Idaho National Laboratory.
Principal Investigator for the development and evaluation of concepts for
a fast-spectrum irradiation test reactor, leading a team of six engineers
and collaborating with ANL on the project. He was a principal in the
formation of the INL Utility Advisory Board in 2005.
2001-2005: Manager, Reactor Systems Technology Section, Nuclear
Technology
Division, Argonne National Laboratory.
Managed the activities of ten professionals with expertise in reactor
systems development, nuclear measurements and analysis, and advanced
analytical methods development. Supported both national and international
programs under the direction of the DOE and other government agencies
including national security programs and advanced reactor development
programs. Principal in the formation of the Utility Advisory Board for the
University of Chicago/Argonne National Laboratory.
1974-2001: Argonne National Laboratory.
Served in a variety of engineering, management, and senior management
roles at ANL supporting EBR-II programs, the Integral Fast Reactor
program, and the EBR-II Spent Fuel Treatment project.
EDUCATION
B.S. Mechanical Engineering, University of Idaho, 1970.
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Selected Professional Activities: |
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Member, ASME Boiler and Pressure Vessel Code, Section
XI, Division 3 Subgroup Committee on Liquid Metal Cooled Systems,
1997-present |
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Member, Editorial Advisory Board—Journal of Nuclear
Technology, 2003—present. |
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Charter Member, Department of Mechanical Engineering
Advisory Board, University of Idaho College of Engineering,
2003—Present |
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Member, Nuclear Engineering Department
Development/Advisory Board, University of Missouri-Rolla, 1996—Present |
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Member, National Executive Committee of the DOE
Energy Facility Contractors Group, 2001-2002, representing Argonne
National Laboratory |
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Member, American Nuclear Society and American Society
of Mechanical Engineers |
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Served on organizing committees and as session chair
and panel member for several national and international technical
conferences and workshops |
PUBLICATIONS
Author or co-author of over 30 technical papers on liquid metal reactors (LMRs),
LMR life extension, and diagnostic techniques for reactor plant
surveillance. Selected titles follow.
R. W. King, and D. L. Porter, Performance of Key Features of EBR-II and
the Implications for Next Generation Systems, Proceedings of the ASME
10th International Conference on Nuclear Engineering (ICONE-10), Crystal
City, VA, April 14-18, 2002.
R. W. King, Reliability, Operability, and Safety of the EBR-II
Sodium-Cooled Fast Reactor Power Station, Transactions of the 2002
Winter Meeting of the American Nuclear Society, Vol87, Washington, DC,
November 17-21, 2002.
S. D. Herrmann, R. W. King, K. R. Durstine, and C. S. Eberle,
Pilot-Scale Equipment Development for Lithium-Based Reduction of Spent
Oxide Fuel, Proceedings of the ANS Third Topical Meeting on DOE Spent
Nuclear Fuel and Fissile Material Management, Charleston, SC, September
1998.
R. W. King and H. W. Buschman, Development of a Risk-Based In-Service
Inspection Program for an LMR, Trans. American Nuclear Society 74, p.
261, Reno, NV, June 1996.
S. Keyvan and R. W. King, The Role of Acoustic Monitoring as a
Diagnostic Tool in Nuclear Reactors, Journal of Acoustic Emission,
Summer Issue, April 22, 1991.
R. W. King and D. L. Porter, Evaluations of Material Aging Effects on
Extended Life Operation of EBR-II, Proceedings 11th International
Conference on Structural Mechanics in Reactor Technology, Vol. D, pp. 377-
382, Tokyo, Japan, August 18-23, 1991.
R. W. King and R. M. Singer, Development and Application of Diagnostic
Systems to Achieve Fault Tolerance, Proceedings of the 7th Power Plant
Dynamics, Control and Testing Symposium, Knoxville, TN, May 15-17,1989.
R. W. King and R. M. Singer, Use of a Pattern Recognition Scheme to
Compensate for Critical Sensor Failures, Proceedings of the 1st
International Machinery Monitoring and Diagnostic Conference, Las Vegas,
NV, September 11-14, 1989.
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