Resume for James Robert (Bob) White
CONTACT INFORMATION
Address: 300-5 El Capitan Drive, Islamorada, FL 33036-4146
Phone: (305) 664-8575 or (305) 393-5606 (cellular)
FAX/Email: (305) 664-8575 / whitej7@ASME.org
CAPABILITY SUMMARY
Nuclear safety analysis including waste tank safety and reactor
safety analysis of both LOCA and operational transients using
state-of-the-art computer codes such as RELAP5 and TRAC-PF1/MOD2
Analysis and interpretation of reactor safety experiments
Computer code development and assessment
Task and personnel management
Quality Assurance Plan and Procedures Development
QUALIFICATIONS
B.S. Engineering Physics, Texas Tech University
(Graduated in top 10% of class)
M.S. Nuclear Engineering, University of New Mexico
(Graduated in top 10% of class)
In addition, I have completed fifteen semester hours of course
work towards an MBA degree through Idaho State University, and
have taken several specialized training courses, including a four-
week Station Nuclear Engineer Course, an eleven-week self-study
Technical Staff Training Program, and short courses in personnel
management, project management, public speaking, technical
writing, root cause analysis, failure modes and effects analysis
and software QA.
Registered Professional Engineer - Texas Certificate Number 65058
(currently expired).
EXPERIENCE SUMMARY
Over twenty five years experience in commercial and government
nuclear reactor technology, including analytical, experimental,
and business development activities in the following areas:
* Program development and marketing technical services
* Nuclear waste tank safety analysis and data evaluation
* Safety analysis (including methods development and integration,
and project management)
* Operational transient and loss of coolant accident experiment
planning and analysis
* Small, intermediate, and large break experiment planning and
analysis
* Computer code assessment and development
* Experiment conduct including instrumentation selection and
qualification
* Hydraulic piping loads determination
* Boiling water reactor operational transient analysis
* Boiling water reactor in-core fuel management
* Boiling water reactor process computer software development
* Quality assurance plan preparation and procedure development
DETAILED EXPERIENCE SUMMARY
EMPLOYER DATES AND JOB RESPONSIBILITIES
J. R. White Consulting April 1998 - Present Self-employed as
186 Harborview Dr. consultant. Provided support to Los
Tavernier, FL 33070 Alamos National Laboratory for safety of
Accelerator Production of Tritium project.
Developed web pages for a variety of clients.
Los Alamos National June 1989 - April 1998 Staff Member - Acted
Laboratory as Principal Investigator for the Preparation
Engineering and Safety of two Safety Assessments of a Mixing Pump
Analysis Group in a Hanford Washington Radioactive Waste
Los Alamos, NM 87545 Tank.
Acted as Project Leader for LANL Safety
Programs while on a change-of-station
assignment at the Hanford site.
Performed TRAC-PF1/MOD2 Analysis in Support
of the Restart of the Savannah River
Production Reactors. Performed TRAC-
PF1/MOD2 Independent Assessment Calculations
and Loss of Pumping Accident Analyses.
Developed Group Quality Assurance Plan, and
the Necessary Procedures to Implement the
Plan.
Gulf States Utilities April 1988 - June 1989 Senior Nuclear
River Bend Station Safety Engineer. Assisted in the Preparation
P. O. Box 220 of Topical Report for the Qualification of
St. Francisville, LA Reload Transient Analysis Methods. Performed
Variety of Thermal Hydraulic Analyses in
Support of Plant Operation.
Self-Employed 1985 - 1988 Consultant to Dr. L. J.
J. R. White Consulting Ybarrondo of Scientech Inc., - Assisted in
Evaluation of the Nuclear Plant Data Bank
for the U.S. Nuclear Regulatory Commission.
Developed Software for the Plant Data
Management System.
Self-Employed 1985 - 1987 Consultant to Exxon Nuclear
J. R. White Consulting Company Performed Assessment Calculations of
the JAERI CCTF Facility Using TRAC-PF1/MOD1
Performed Detailed Review and Analysis of
the TRAC Code Assessment History. Provided
Recommendations for Modifications to TRAC
for Use in Appendix K Reflood Calculations.
Self-Employed 1985 Consultant to Los Alamos National
J. R. White Consulting Laboratory - Performed TRAC-PF1/MOD1
Analysis of the Small Break International
Standard Problem 18, and TRAC-PF1/MOD1
Analysis of the University of Maryland
Facility.
Snake River Software 1984 - 1987 Vice President in Charge of
2100 Belmont Marketing for Software Publishing Company -
Idaho Falls, ID Developed and Marketed Computer Software for
Home Applications.
Intermountain 1982 - 1985 Senior Engineer - Performed
Technologies, Inc. RELAP5 Analysis of Steam Generator Tube
Idaho Falls, ID Rupture and Over-cooling Transients in
Babcock and Wilcox Plants. Principal
Investigator on Pressurized Thermal Shock
Analysis Task for the Nuclear Safety
Analysis Center.
Self-Employed 1982 Consultant to Los Alamos National
J. R. White Consulting Laboratory - Performed TRAC-PF1 analysis of
LOFT Intermediate Break Experiment L5-1 and
Severe Core Transient L8-2.
Intermountain 1980-1982 Senior Engineer and Principal
Technologies, Inc. Investigator Analysis and Assessment of LOFT
Idaho Falls, ID Program for the Electric Power Research
Institute (EPRI). Participated in Program
Review and Analysis Development for EPRI
Safety Relief Valve Testing Program. Acted
as Principal Investigator for Feasibility
Study for JAERI Nuclear Reactor Safety
Analysis System.
EG&G Idaho, Inc. 1978-1980 Supervisor, LOFT Program Planning
Idaho Falls, ID Section, LOFT Program Planning and Data
Evaluation Branch - Preparation of
Experiment Operating Specifications, LOFT
Program Documents, and Experiment Safety
Analysis Reports.
Aerojet Nuclear Co. 1975 - 1978 Senior Engineer, LOFT Program
Idaho Falls, ID Planning Section Preparation of Experiment
Prediction and Post-test Analysis Reports,
Analysis of Experiment Results, and
Performing Analyses for Planning Future
Experiments.
Tennessee Valley 1973 - 1975 Engineer, Nuclear Section,
Authority, Division of Power Production- Developed
Chattanooga, TN Software to Support Plant Operation in the
Event of the Unavailability of the Browns
Ferry Nuclear Plant Process Computer.
Became Principal Nuclear Engineer for Browns
Ferry Unit 1 and Participated in the Startup
of Browns Ferry Unit 2. Developed Software
for Implementation and Monitoring of the
Browns Ferry In-core Fuel Management
Program.
Prepared Chapter 15 Operational Transients
Analysis for BWR-6 GESSAR While on Loan to
General Electric Company in San Jose.
PUBLICATIONS
Evaluation of Mitigation Strategies in Facility Group I
Double-Shell Flammable-Gas Tanks at the Hanford Site,
C. Unal, P. Sadasivan, W. L. Kubic, and J. R. White, Los Alamos
National Laboratory Technical Report LA-UR-97-4912, February 1998.
A Preliminary Safety Assessment for Operation of the
Mixer Pump During Retrieval Operations in Tank 241-SY-
101, Los Alamos National Laboratory Technical Report
LA-UR-95-839, July 1995.
Challenges and Methodology for Safety Analysis of a High-Level
Waste Tank with Large Periodic Releases of Flammable Gas, with
J. N. Edwards, K. O. Pasamehmetoglu and C. W. Stewart. This paper
was accepted for publication and presentation at a Thermal
Hydraulics of Waste Management session at the 1994 ANS Winter
Annual Meeting.
New Challenges in the Safety Analysis of the DoE's High-Level
Waste Tanks, with J. N. Edwards and K. O. Pasamehmetoglu. This
paper was accepted for publication and presentation at the
American Chemical Society, I&EC Division at a conference entitled
Emerging Technologies in Hazardous Waste Management VI, September
1994, Atlanta, GA.
A Safety Assessment for Proposed Pump Mixing Operations
to Mitigate Episodic Gas Releases in Tank 241-101-SY:
Hanford Site, Richland Washington, Los Alamos National
Laboratory Technical Report LA-UR-95-3196, August 1992.
The TRAC-PF1/MOD2 Computer Code - Developmental Assessment
Results, paper submitted for consideration to the 28th
ASME/AlChe/ANS National Heat Transfer Conference, J. C. Spore,
J. R. White, et. al., August 9-12, 1992, Los Alamos National
Laboratory report LA-UR-92-203 Revised.
Los Alamos Confirmatory Power Limits for the Restart of
Savannah River K Reactor, Los Alamos National Laboratory
Report N-6-92-011, J. N. Edwards, J. R. White, et. al., November
1991.
Summary of TRAC-PF1/MOD2 Analysis of the Savannah River
Heat Transfer Laboratory Subcooled Boiling Flow
Instability Tests, Los Alamos National Laboratory Letter
Report, J. R. White, August 1989.
RELAP5 Simulation of Reactor Water Backflow Into The High
Pressure Core Spray (HPCS) System Piping, paper for 1989 Winter
ANS Meeting, J. S. Miller, J. L. Thompson and J. R. White,
February, 1989.
RETRAN Simulation of BWR/6 Load Rejection Transients, paper for
1989 Winter ANS Meeting, J. S. Miller, J. R. White, et. al.,
February, 1989.
Nuclear Plant Data Bank Test Results Report, Report
Prepared for the Nuclear Regulatory Commission through Scientech
Corporation, J. R. White, September, 1987.
One-Dimensional Analysis of CCTF Run 54 with the Advanced
Nuclear Fuel Corporation's Version of TRAC-PF1/MOD1,
Report Prepared for ANF Corporation, J. R. White, April, 1987.
Response of a B&W Plant to Steam Generator Tube
Ruptures, NSAC Report 101, J. R. White et. al, September, 1986.
TRAC-PF1/MOD1 Revision 12.1 Calculation for International
Standard Problem 18, Los Alamos National Laboratory Report
LA-UR-86-2591, Clay P. Booker and J. R. White, July 1986.
Recommendations for Additional Assessment Calculations
for the Exxon Version of TRAC-PF1/MOD1, Report Prepared for
Exxon Nuclear Company, J. R. White, January 1986.
TRAC-PF1 Independent Assessment, Los Alamos National
Laboratory Report LA-10548-MS, C. P. Booker, B. E. Boyack,
P. Coddington, T. D. Knight, J. K. Meier, and J. R. White, October
1985.
Proposed TRAC-PF1/MOD1 Best-Estimate Evaluation Model,
Report Prepared for Exxon Nuclear Company, J. R. White, July 1985.
Preliminary TRAC-PF1/MOD1 User Guidelines, Report Prepared
for Exxon Nuclear Company, J. R. White, June 1985.
Nuclear Plant Data Bank Evaluation, Scientech Report
Prepared for the Nuclear Regulatory Commission under SBIR Contract
NRC-04-84-148, L. J. Ybarrondo, J. R. White, and K. V. Moore,
February, 1985.
Thermodynamic Modeling and Correlation of Two-Phase
Centrifugal Pump Characteristics, J. R. White, et al.,
Intermountain Technologies Incorporated Report.
Comparison of Experimental Results with Analytical
Calculations of LOFT Small Breaks L3-1, L3-5, and L3-6,
EPRI Topical Report, J. R. White, et al.
A Comparative Analysis of RELAP5 Against RETRAN and CRAFT for
Overcooling Transients in a B&W Plant, Paper presented at the
Joint ANS/ASME Conference on Design, Construction & Operation of
Nuclear Power Plants, J. R. White, et al., 1984.
Response of a B&W Lower Loop Plant to Overcooling
Transients Using RELAP5, Nuclear Safety Analysis Center Report
NSAC-71, June, 1984.
Evaluation of RELAP5/MOD1 for Analysis of Steam Generator Tube
Rupture Transients in OTSG Plants, Paper and Presentation at the
ANS Topical Meeting on Anticipated and Abnormal Plant Transients
in Light-Water Reactors, Jackson, Wyoming, 1983.
RETRAN-02 Calculations of Operational Transients in the Loss-of-
Fluid Test Facility, Nuclear Technology, J. R. White, et al.,
May, 1983.
RETRAN-02 Calculations of Operational Transients in LOFT, paper
presented at The Second International RETRAN Meeting, San Diego,
California, J. R. White, et al., April, 1982.
Comparison of the Semiscale Reactor Vessel Differential
Pressure and Gamma Densitometer Data for Selected
Semiscale MOD-3 Small-Break Experiments, ITI Report Prepared
for the Electric Power Research Institute, J. R. White, 1981.
Feasibility Study for Development of Nuclear Reactor
Safety Analysis System, Study Performed for JAERI through NDC,
J. R. White, et al., 1981.
Modeling Loss-of-Fluid Test Small-Break Experiments with RETRAN,
Nuclear Technology, Volume 54, J. R. White, et al., 1981.
RETRAN-02 Analysis of LOFT Experiment L9-1/L3-3, ITI
Report ITI-4020, J. R. White, 1980.
An Assessment of LOFT Nuclear Tests L2-2 and L2-3, ITI
Report ITI-I-4017, J. R. White, et al., 1980.
Small-Break Loss-of-Coolant Analytical Techniques for
Power Reactors - Current Capability and Future Trends, ITI
Report ITI-DR-4, J. R. White, et al., 1980
Comparisons of Experimental Results with RETRAN Calculations of
LOFT Experiment L3-1, paper presented at the First International
RETRAN Meeting, Seattle, Washington, 1980.
RELAP4/MOD6 Predictions Comparisons With LOFT LOCE L2-2
Data, LTR-20-100, J. R. White, 1979.
Preliminary Post-test Analysis of LOFT LOCE L2-2,
LTR-20-103, J. R. White, et al., 1979.
Prediction of the LOFT System Thermal-Hydraulic Response to a
Nuclear LOCE With the RELAP4/MOD6 Code, Invited Paper and
Presentation for the ASME Topical Meeting on Pressure Vessels and
Piping, J. R. White, et al., 1979.
Carryover Rate Fraction Correlation for LOFT Safety Analysis
Calculations, ANS Transactions, ANS Annual Meeting, J. C. Lin
and J. R. White, 1979.
Failure of LOCE Controller to Trip Primary Coolant
Pumps, LTR-L0-11-081, J. R. White, et al., 1979.
Analysis of Inadvertent Opening of the RABVs During
L3-1, LTR-L0-11-076, J. R. White, 1979.
Analysis of Loss of Auxiliary Feedwater During LOFT LOCE
L3-1, LTR-L0-11-79-077, J. R. White, 1978.
Prediction of LOFT Fluid Conditions of a Nuclear LOCE, ANS
Transactions, ANS Winter Meeting, J. R. White, 1978.
Fuel Cladding Temperature Predictions for LOFT LOCE L1-5, ANS
Transactions, ANS Winter Meeting, J. L. Perryman and J. R. White,
1978.
Best-Estimate Experiment Predictions for LOFT Nuclear
Experiments L2-2, L2-3 and L2-4, LOFT-TR-101, J. R. White,
et al., 1978.
Posttest Analysis of LOFT Experiment L1-3A,
TREE-NUREG-1137, J. R. White, et al., 1977.
Effects of RELAP4/MOD5 Modeling of the LOFT Pressurizer, ANS
Transactions, ANS Annual Meeting, J. R. White, et al., 1977.
Experiment Prediction for LOFT Non-nuclear Experiment
L1-4, TREE-NUREG-1086, J. R. White, et. al., 1977.
Experiment Prediction for LOFT Experiment L1-2, EPL1-2,
J. R. White, et al., 1975.
Calculated and Measured Neutron Spectra in the Sandia Annular
Core Pulsed Reactor, paper presented at American Nuclear Society
Meeting, J. R. White, et al., 1971.
PROFESSIONAL SOCIETY AFFILIATIONS AND ACTIVITIES
Member, American Society of Mechanical Engineers
Member, Tau Beta Pi (Engineering Honorary Society)
Member, Sigma Pi Sigma (Physics Honorary Society)