Obtain employment as a nuclear safety or other type of analyst.
Thomas Lewis
1400 Hunt Avenue, Richland, WA 99354
Cell: (541) 207-8083
e-mail: sthomaslewis[at]gmail.com
SUMMARY
• Experienced with implementation of 10 CFR 830, DOE 0 413.3A, DOE 0 420.1B and related standards and guides.
• Performed criticality safety evaluations and calculations.
• Developed models to prevent criticality accidents and the spread of radioactive material.
• Skilled in the writing of technical reports specifying safety limits and specification.
• Worked with management and plant personnel in the implementation of the limits and specifications.
• Experienced with Monte-Carlo Computer Codes, particularly SCALE, KENO, and MONK.
• Knowledgeable in nuclear reactor theory, neutron transport theory, chemistry, and mathematics.
RELATED EXPERIENCE
Criticality Safety Engineer
IT Networks – Richland, Washington 99352 2009 - 2010
• Performed Criticality Safety Evaluations for the CH2M-Hill Plateau Remediation Project.
• Assisted in the implementation of neutronics codes involving transmutation of uranium and plutonium using Runge-Kutta boundary value solution techniques.
Senior Engineer
Superior Technical Resources, Inc. – King of Prussia, Pennsylvania 2003
• Provided technical support to Lockheed-Martin Company, Space Power Division in the area of nuclear rocket launch safety.
• Developed models regarding various accident scenarios and conditions at launch sites, including the breakup of the Radioisotope Thermal Generator (RTG), and the spread of Pu-238 contamination at the launch site.
• Instrumental in the determination of errors and problems with the various FORTRAN and Monte-Carlo computer codes used to determine rocket launch safety.
Double Contingency Analysis Engineer
Entor Corporation - Aiken, South Carolina 1998 - 1999
• Provided technical support to the Westinghouse Savannah River Company in the area of Double Contingency Analysis for the FB-Line and HB-Line processes.
• Developed detailed thermodynamics, heat transfer and fluid mechanics models to prevent the release of radioactive materials in the various facilities that process nuclear material.
• Reviewed Criticality Safety documentation, double contingency analysis documentation, and Probabilistic Risk Assessments (PRA) for the various proposed and current operating processes at the Savannah River Site.
Nuclear Safety Engineer
Parallax, Inc. - Paducah, Kentucky and Piketon, Ohio 1994 -1997
• Provided technical support and consultation in the area of Nuclear Criticality Safety to Lockheed-Martin Utility Services (LMUS) and Lockheed-Martin Energy Systems (LMES) at Paducah, Kentucky and Piketon, Ohio for changes in U-235 assay, and for the transition from the Department of Energy (DOE) to the Nuclear Regulatory Commission (NRC) oversight and regulation consistent with 10 CFR 830, DOE O 413.3A, and DOE O 420.1B.
• Performed Nuclear Criticality Safety calculations using the SCALE system with KENO, and authored reports to summarize the results of calculations to evaluate the consequences of changing the U-235 assay from 3.5 to 5.5%.
• Performed Nuclear Criticality Safety computer code validations, involving the use of statistical analyses, to ensure that the computer code results were consistent with experimental data.
• Summarized the results in technical reports. Worked with management and plant personnel in the implementation of the limits developed by the results of the calculations.
Paper presented for the Nuclear Criticality Safety Division of the American Nuclear Society, August 1997: Uranium Enriched to Less Than One Weight Percent U-235 - Safe for Operations at Uranium Enrichment Plants
Nuclear Safety Engineer
Nuclear Fuel Services - Erwin, Tennessee 1990 - 1994
• Performed calculations and authored Nuclear Criticality Safety Analysis reports to summarize the results of the calculations. Provided support for the various processes and equipment for the highly enriched uranium materials at Nuclear Fuel Services.
• Performed calculations using KENO and other SCALE codes, and authored safety analyses reports for future and proposed processes at Nuclear Fuel Services and other nuclear facilities consistent with 10 CFR 830, DOE O 413.3A, and DOE O 420.1B.
• Performed Probabilistic Risk Assessments (PRA) for various proposed and current operating processes at NFS using the CAFTA software.
• Worked with management and plant personnel in the implementation of the limits developed by the results of the calculations.
Engineer
Westinghouse Hanford Company - Richland, Washington 1983 - 1990
• Performed Nuclear Criticality Safety calculations and analyses using MONK and KENO and authored Nuclear Criticality Safety Analysis reports for the various plutonium and uranium reprocessing facilities on the Hanford Site such as the PUREX and Plutonium Finishing Plants.
• Performed shutdown, refueling, startup, and Nuclear Criticality Safety calculations and authored reports summarizing the results of the calculations for the Fast Flux Test Facility (FFTF) on the Hanford Site.
• Worked with management and plant personnel in the implementation of the limits developed by the results of the calculations.
EDUCATION
Corporate Sponsored
• Nuclear Criticality Safety Short Course – Santa Fe, NM - 1985
• Auditing – Nuclear Fuel Services – 1991
• Probabilistic Risk Assessment – Nuclear Fuel Services - 1991
• Monte Carlo Methods – University of Tennessee – 1992
• Nuclear Criticality Safety Workshop – Los Alamos, NM - 1993
Academic
• Graduate courses in Nuclear Engineering - University of Washington – 1985 to 1990
• M. S. - Chemical Engineering - Louisiana State University - 1980
• B. S. - Chemical Engineering - Brigham Young University - 1976
ADDITIONAL EXPERIENCE
Mathematics and Chemistry Instructor
Chemeketa Community College – Salem, Oregon - 2009
Mathematics and Science Assistance
Linn-Benton Community College – Albany, Oregon - 2009
Customer Service Representative
Signal Northwest - Albany, Oregon 2005 - 2008
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