Senior Nuclear Criticality Safety Engineer

With extensive technical experience in the fields of nuclear criticality safety, nuclear safety, mechanical and thermal systems, and nuclear system design, Mr. Bahney is a results-oriented professional with the skills necessary to establish and support a successful nuclear safety program. 

June 1998- Present

Paschal Solutions, Inc., Hixson TN,  NISYS Corporation, Duluth, GA and United States Enrichment Corporation, Piketon, OH

Mr. Bahney is a Senior Nuclear Criticality Safety Engineer supporting the Portsmouth and Paducah Gaseous Diffusion Plants, the American Centrifuge Plant in Piketon, Ohio, and the Isotek U-233 Downblending and Disposition Project in Oak Ridge, Tennessee.  Responsibilities include:

·         Perform engineering evaluations of plant systems and establish operating limits and procedures to ensure criticality safety.

·         Developed NCS program policies, program procedures, and performance metrics.

·         Provide NCS event response, corrective action plans, classroom training (qualified instructor), emergency operations support, and technical support as subject matter expert for work planning.

·         Review plant changes for adherence to regulatory requirements and safety analysis documentation (DOE and NRC USQ Determinations).

·         Conduct plant inspections and provide technical expertise for upgrades and procedure changes to implement safety requirements.

·         Perform technical reviews of hazard analyses, safety basis documents, plant change reviews (qualified reviewer), and criticality accident alarm system design.

·         Proficient in SCALE and MCNP code packages for nuclear systems analysis, criticality, and accident alarm system response, including PC and Unix installation, validation, and administration.

Dec. 1992- May 1998       

Framatome Cogema Fuels, Las Vegas, Nevada

Mr. Bahney was the Lead Thermal Design Engineer in Waste Package Development.  Responsibilities included:

·         Developed conceptual waste package designs for the proposed high-level radioactive waste repository at Yucca Mountain, Nevada.

·         Established engineered barrier system thermal design methodology.

·         Developed effective thermal conductivity method for the determination of peak spent fuel cladding temperatures.

·         Presented waste package design concepts and issues to the DOE, NRC, and utility representatives.

·         Authored quality assurance procedures and performed job specific training.

·         Proficient in CAE (ANSYS-FEA), CAD (Pro/Engineer and SDRC), and Unix system administration.

Sept. 1990- Aug. 1992      

DOE/Oak Ridge Associated Universities, Oak Ridge, Tennessee

As a recipient of a Civilian Radioactive Waste Management Fellowship, Mr. Bahney completed his research practicum at the Electric Power Research Institute and analyzed conceptual designs for the Universal Container System for storage and disposal of spent nuclear fuel and other high-level wastes.

Sept. 1989- Aug. 1990     

The Ohio State University, Columbus, Ohio

Mr. Bahney was a Student Research Assistant in the Nuclear Engineering Department.  Research projects included testing for transient critical heat flux in the cooling system of the proton accelerator target for boron-neutron capture therapy and calorimetric power calibrations of the university research reactor.

·         The Ohio State University, Columbus, Ohio

Master of Science degree in Nuclear Engineering (pending)

Specialization in Nuclear Waste Management (GPA:  3.76)

·         The Ohio State University, Columbus, Ohio

Bachelor of Science degree in Mechanical Engineering

Specialization in Nuclear Engineering (GPA:  3.51)

·         DOE “Q” Clearance – Active

·         DOE “L” Clearance – 1998-2008

·         DOE “Q” Clearance – 1991-1992

·         Authorized Derivative Classifier, Portsmouth Gaseous Diffusion Plant

·         Short courses in criticality safety, critical experiments, and software packages

·         Qualified Senior NCS Engineer, Calculation Analyst, and USQD Preparer (DOE/ERWM and NRC-regulated)

·         American Nuclear Society:  Ohio Section past Vice-President, Nevada Section past Treasurer, OSU Student Section past active member, and international conference organizer

·         American Society of Mechanical Engineers

·         Put-in-Bay Yacht Club 2006 Commodore and Web Site Administrator

·         “Implementation of Independent Verification for General Batching Operations,” Proceedings of the 2005 ANS Nuclear Criticality Safety Division Topical Meeting, Knoxville, Tennessee, September 18 – 22, 2005, American Nuclear Society.

·         “Effective Thermal Conductivity Method for Predicting Spent Nuclear Fuel Cladding Temperatures in a Dry Fill Gas,” Transportation, Storage, and Disposal of Radioactive Materials Proceedings, PVP-Vol. 348, The 1997 ASME Pressure Vessels and Piping Conference, Orlando, Florida, July 27 – 31, 1997, American Society of Mechanical Engineers.

·         “Parametric Thermal Evaluation of Waste Package Emplacement,” High Level Radioactive Waste Management 1996, Proceedings of the Seventh Annual International Conference, Las Vegas, Nevada, April 29 – May 3, 1996, American Nuclear Society.

·         “Determination of SNF Peak Temperatures in the Waste Package,” High Level Radioactive Waste Management 1995, Proceedings of the Sixth Annual International Conference, Las Vegas, Nevada, April 30 – May 5, 1995, American Nuclear Society.

·         “Thermal Response of the Waste Package/MPC and EBS,” High Level Radioactive Waste Management 1994, Proceedings of the Fifth Annual International Conference, Volume 2, Las Vegas, Nevada, May 22 – 26, 1994, American Nuclear Society.

      Paschal Solutions, Inc.                   1300 Highcrest Dr.                  Hixson, TN 37343            (270)217-0548 

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