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401 West Main Street, Room E2234
Richmond, Virginia 23284

Education

• PhD, Nuclear Engineering (1983), University of Virginia
• ME, Nuclear Engineering (1980), University of Virginia
• BS, Applied Mathematics and Physics (double major, 1977), Western Michigan University

Professional Experience:

• 27 years in Nuclear Risk Analysis, Safety Analysis and Operations with Dominion’s nuclear business unit in Virginia

Areas of Research:

• Nuclear Probabilistic Risk Analysis
• Nuclear Safety Analysis

Teaching Focus Areas:

• Nuclear Reactor Safety
• Probabilistic Risk Analysis
• Nuclear Power Plant Design

Laboratory Development:

• Presently overseeing final construction of the VISIBLE REACTOR, a working, 3-kW thermal model of a Pressurized Water Reactor Nuclear Power Station.
• Presently overseeing design and construction of an electronic nuclear plant SIMULATOR, patterned after the North Anna Power Station in central Virginia.
• Both projects are being worked jointly with the Electrical Engineering Department, and are scheduled for completion in the 2009-2010 academic year.

Selected Publications:

1. Analysis of ECCS Bypass Data, NUREG-0573, June, 1979 (contributing author)
2. Bubble Behavior in LMFBR Core Disruptive Accidents, NUREG/CR-2111, July, 1981 (contributing author)
3. Bubble Behavior in LMFBR Core Disruptive Accidents, NUREG/CR-2603, April, 1982 (contributing author)
4. Bubble Behavior and Aerosol Conditions in LMFBR Core Disruptive Accidents, Report UVA/532345/NEEP83/101, March, 1983 (contributing author)
5. Droplet Size Distribution from Bulk Flashing, Nuclear Science and Engineering, Vol. 88, No. 4, December, 1984 (primary author)
6. Vepco Relaxed Power distribution Control Methodology and Associated FQ Surveillance Technical Specifications, VEP-NE-1-A, March 1986 (contributing author)
7. Monte Carlo DNBR Limit Development Using Few-Channel Thermal-Hydraulic Models, Trans. ANS, Vol. 52, June 1986 (primary author)
8. Monte Carlo Departure from Nucleate Boiling Ratio Limit Development Using Few-Channel Thermal-Hydraulic Code Models, Nuclear Technology, Vol. 77, No. 2, May 1987 (primary author)
9. Statistical DNBR Evaluation Methodology, VEP-NE-2-A, June, 1987 (sole author)
10. Qualification of the WRB-1 CHF Correlation in the Virginia Power COBRA Code, VEP-NE-3-A, July 1990 (primary author)
11. The Probability Density Function of the Total Departure from Nucleate Boiling Ratio, Nuclear Technology, Vol. 95, No. 2 August, 1991 (sole author)
12. Alternate (a)(4) Acceptance Criteria, Trans. ANS, New Orleans, November 2003 (principal author)
13. Recovery from a Catastrophic Station Blackout, Proceedings of the 8th Intl Conference On Probabilistic Safety Assessment and Management, New Orleans, 2006 (primary author)

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• Virginia Commonwealth University | School of Engineering | Department of Mechanical Engineering
• 401 West Main Street | Room E3221 | P.O. Box 843015 | Richmond, Virginia 23284-3015
• Phone: (804) 828-9117 | TDD: (800) 828-1120 | Fax: (804) 827-7030 | E-mail: mechanicalengr@vcu.edu
• Last Updated: 04/08/2008
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