Transportation Technologies Group

Biographical Information

A nuclear engineer with over 12 years of diverse engineering and project management experience, Mr. Reich has experience in managing engineering, computer programming, and operations teams. His areas of expertise include satellite and radio communications, transportation risk assessment, nuclear fuel cycle analysis, development of advanced nuclear reactor concepts, computer simulation and modeling, and computer programming. His current assignments requiring frequent travel to the Russian Federation have increased his skills in the Russian language.
PROFESSIONAL EXPERIENCE:

OAK RIDGE NATIONAL LABORATORY (1988-Present)

Project Manager

Bill is currently the Project Lead for Material Protection, Control & Accounting Program's (MPC&A) Transportation Security Project, which includes developing transportation security systems for use in the Russian Federation. The team, which he oversees, consists of team members from Oak Ridge National Laboratory (ORNL), Sandia National Laboratories, and Pacific Northwest Laboratory.

His work in the the Chemical Technology Division's Transportation Technologies Group involves satellite-based transportation security and communications systems used to protect special nuclear material in the Russian Federation. He also managed the DOE TRANSCOM, a satellite-based transportation tracking and communications system used to protect spent fuel shipments. He has experience in engineering management, computer programming, and the supervision of operations teams. He also has expertise in the areas of satellite and radio communications, transportation risk assessment, nuclear fuel cycle analysis, development of advanced nuclear reactor concepts, computer simulation and modeling, and computer programming.

BATTELLE PACIFIC NORTHWEST LABORATORIES (1987)

Graduate Student

Studied the corrosion of potassium silicate glasses using Fourier Transform Infrared Spectroscopy. Performed automated data acquisition and analysis using a PC-based system.

UNIVERSITY OF MISSOURI-ROLLA (1986-1987)

Graduate Student

Studied the desorption of water from silicate glasses using Modulated Beam Mass Spectrometry. Operated multi-channel analyzer; performed peak analysis, isotope ID, remote operation with Spectran-F analyzing algorithm.

SUNNEN PRODUCTS CO. (1982-1986)

Engineer

Functioned as a software engineer. Developed a data base system using MAPPER. Created a number of FORTRAN and BASIC programs for Drafting Department and Process Engineering. Functioned as a draftsman in Plant Engineering and Drafting Department.

EDUCATION:

Self-taught Russian language skills

M.S. Nuclear Engineering, December 18, 1993

Thesis: Nature of Incorporated Water in Hydrated Potassium Silicate Glasses

B.S. Nuclear Engineering, July 29, 1986

Technological Minor in Economics, July 29, 1986

University of Missouri-Rolla

ADDITIONAL SKILLS:

Very knowledgeable with IBM and Macintosh microcomputer hardware, software, and programming languages. Hardware knowledge of all Intel-based systems, 68000-based systems, and peripherals. Proficient user of many applications including Windows 2000/NT/98/95, MS Office Suite, dBase, FoxPro, WordPerfect, Lotus Suite, Norton Utilities, SigmaPlot, TableCurve, PeakFit, MathCAD, FORTRAN, BASIC, and C languages. Computer virus and data recovery expert.

PUBLICATIONS & PRESENTATIONS:

U.S. Nuclear Regulatory Commission, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, NUREG-1437, Vol. 1, Addendum 1. Authored Section 6.3—Transportation, August 1999.

J. T. Slankas, J. R. Griggs, W. J. Reich, G. A. Chartrand, D. E. Robertson, W. Gromov, Radio Communications Systems at Russian Nuclear Sites, Presented at the INMM 40^th Annual Conference, July 25-28, 1999, Phoenix, AZ.

W. J. Reich, Status of Transportation Security Project—Communications, Oak Ridge National Laboratory, briefing presented to Minatom Regulatory Project Team, Washington, DC, November 13, 1998.

W. J. Reich, Status of MVD Project—Communications, Oak Ridge National Laboratory, briefing presented to Minatom Regulatory Project Team, Washington, DC, November 13, 1998.

W. J. Reich, R. L. Clark, J. Croes, S. Schmid, T. L. Wilson, S. B. Ludwig, D. J. Spellman, Identification of Reactor Systems and Operations Issues Resulting from MOX Fuel Disposition, ORNL/TM/LTR-109, August 1998.

W. J. Reich, R. L. Clark, J. Croes, B. D. Murphy, J. C. Ryman, S. Schmid, T. L. Wilson, S. B. Ludwig, D. J. Spellman, Impacts on Reactor Systems, Operations, Equipment, and Facilities from the Use of Mixed Oxide (MOX) Fuels, ORNL/TM/LTR-140, August 1998.

W. J. Reich, S. B. Ludwig, Transportation of Fissile Materials in the Russian Federation, ORNL/MD/LTR-123, Draft May 1998.

W. J. Reich, Prototype Demonstration of Railcar Security System, Oak Ridge National Laboratory, briefing presented to DOE/NN Program Review Team, Albuquerque, NM, May 4, 1998.

W. J. Reich, Command Post Integration, Oak Ridge National Laboratory, briefing presented to DOE/NN Program Review Team, Albuquerque, NM, May 4, 1998.

W. J. Reich, Demonstration of the TRANSCOM for Windows Tracking Software System, briefing presented to Russian Production State Enterprise Eleron, Moscow, Russian Federation, February 11-20, 1997.

W. J. Reich, TRANSCOM Transportation Tracking and Communications System, briefing presented to Russian Scientific Production State Enterprise Eleron, Albuquerque, NM, November 7, 1996.

W. J. Reich, Satellite Tracking Technologies, briefing presented to Russian Scientific Production State Enterprise Eleron, Albuquerque, NM, November 7, 1996.

D. P. Cleary, L. N. McCold, W. J. Reich, P. E. Johnson, Supplemental Analysis: Cumulative Environmental Impacts of Spent Nuclear Fuel Transport in the Vicinity of the Proposed Yucca Mountain High-Level Waste Repository Attributable to License Renewal, and Implications of Higher-Burn-Up Fuel for the Conclusions in Table S-4, prepared by Oak Ridge National Laboratory for the Nuclear Regulatory Commission, NRC Job Code W6760, October 1997.

S. B. Ludwig, W. J. Reich, Transportation and S&S Support for the Joint U.S./Russian Program, briefing to J. Baker, DOE/MD, March 13, 1997.

W. J. Reich et. al, Upgrading TRANSCOM—A Tracking and Communications System for Radioactive Material Shipments, presented at the 11th International Conference on the Packaging and Transportation of Radioactive Materials (PATRAM ‘95), Las Vegas, Nevada, December 3-8, 1995.

Oak Ridge National Laboratory and Resources For The Future, Estimating Externalities of Nuclear Fuel Cycles, Report No. 8 on the External Costs and Benefits of Fuel Cycles: A Study By the U.S. Department of Energy and the Commission of European Communities, published by McGraw-Hill, April 1995.

C. W. Forsberg, K. R. Elam, W. J. Reich, New Glass Material Oxidation and Dissolution System Facility: Direct Conversion of Surplus Fissile Materials, Spent Nuclear Fuel, and Other Materials to High-Level-Waste Glass, Storage and Disposition of Weapons-Usable Fissile Materials Programmatic Environmental Impact Statement Data Report, ORNL/MD/LTR-13, March 28, 1995.

W. J. Reich, D. J. Wrest, E. Newman, Calculation of Axial Europium Isotopic Mass for HFIR Control Cylinders Using ORIGEN2, DRAFT, August 1994.

C. W. Forsberg, W. J. Reich, W. J. Rowan, Japanese Suppliers in Transition from Domestic Nuclear Reactor Vendors to International Suppliers, ORNL-6766, June 1994.

C. W. Forsberg, J. Conklin, W. J. Reich, Use of a Temperature Initiated Passive Cooling System (TIPACS) for the Modular High-Temperature Gas-Cooled Reactor Cavity Cooling System (RCCS), ORNL-6767, April 1994.

Environmental Restoration Program, Mixed Waste Disposal Initiative Project: A Comprehensive Conveyance Study for the Off-Site Shipment of Oak Ridge K-25 Site Stabilized Pond Waste, Authored chapter on transportation impacts, ES/ER/TM-64, September 1993.

C. W. Forsberg, R. E. Norman, W. J. Reich, L. J. Hill, The European Nuclear Power Industry: Restructuring for Combined Strength and Worldwide Leadership, ORNL-6758, June 1993.

G. J. Dyer, W. J. Reich, Transportation Risk Assessment for the Oak Ridge K-25 Site Mixed Waste Disposal Initiative, ES/ER/TM-68, April 1993.

Damages and Benefits of the Nuclear Fuel Cycle: Estimation Methods, Impacts, and Values, Authored chapter on transportation impacts, Oak Ridge National Laboratory, DRAFT, May 1993.

Department of Energy, Construction and Operation of Retrievable Transuranic and Mixed Transuranic Waste Storage Facilities at Oak Ridge National Laboratory, in Oak Ridge, Tennessee, Authored the sections on transportation risks, DOE/EA-0349, January 1993.

C. W. Forsberg, L. J. Hill, W. J. Reich, W. J. Rowan, The Changing Structure of the International Commercial Nuclear Power Reactor Industry, ORNL/TM-12284, December 1992.

Department of Energy, Class III/IV Solid Low-Level Waste Storage at Solid Waste Storage Area 7 at the Oak Ridge National Laboratory, Authored the sections on transportation risks, December 1992.

G. E. Michaels, W. J. Reich, Effects of an LMR-Based Partitioning-Transmutation System on U.S. Nuclear Fuel Cycle Health Risk, presented at the OECD/NEA International Information Exchange Program on Actinide and Fission Product Separation and Transmutation, November 1992.

K. J. Notz, R. Salmon, T. D. Welch, W. J. Reich, R. S. Moore, E. A. Dorsey, Characteristics of Potential Repository Wastes, 4 vols., ORNL/M-2217/V1-V4, July 1992.

K. J. Notz, R. S. Moore, R. Salmon, T. D. Welch, W. J. Reich, "Spent Fuel Characteristics Provided by the CDB — An Update," pp. 122-30 in Proceedings of the 3rd International Conference on High-Level Radioactive Waste Management, Las Vegas, April 12-16, 1992, American Nuclear Society, 1992.

T. J. Blasing, R. A. Brown, G. F. Cada, C. Easterly, D. L. Feldman, C. W. Hagan, R. M. Harrington, R. O. Johnson, R. H. Ketelle, R. L. Kroodsma, L. N. McCold, W. J. Reich, P. A. Schofield, M. L. Socolof, R. P. Taleyarkhan, J. W. Van Dyke, Phase I Environmental Report for the Advanced Neutron Source at Oak Ridge National Laboratory, ORNL/TM-12069, February 1992.

C. W. Forsberg, W. J. Reich, Worldwide Advanced Nuclear Power Reactors with Passive and Inherent Safety: What, Why, How, and Who, ORNL/TM-11907, September 1991.

W. J. Reich, R. S. Moore, Analysis of Assembly Serial Number Usage in Domestic Light-Water Reactors, ORNL/TM-11841, May 1991.

W. J. Reich, R. S. Moore, K. J. Notz, Distribution of Characteristics of LWR Spent Fuel, ORNL/TM-11670, January 1991.

K. J. Notz, T. D. Welch, R. S. Moore, W. J. Reich, Preliminary Waste Form Characteristics, ORNL/TM-11681, September 1990.

W. J. Reich, An Overview of Direct and Indirect Verification Methods for Special Nuclear Material in Spent Nuclear Fuel, K/ITP-204, July 1989.

C. W. Forsberg, D. L. Moses, W. E. Kohn, W. J. Reich, E. B. Lewis, R. Gibson, G. A. Murphy, R. H. Staunton, R. Pearson, Proposed and Existing Passive and Inherent Safety-Related Structures, Systems, and Components (Building Blocks) for Advanced Light-Water Reactors, ORNL-6554, May 1989.

A. F. McBride, W. M. Ward, J. W. Roddy, W. J. Reich, P. N. Austin, L. B. McCarn, S. B. Ludwig, R. W. Roussin, Compendium of Technical Computer Codes Used in Support of the DOE Office of Civilian Radioactive Waste Management, ORNL/TM-10919, April 1989.

A. R. Irvine, T. D. Welch, W. J. Reich, Predisposal Treatment and Packaging of Miscellaneous Radioactive Waste and Non-LWR Fuel for Low Long-Term Release Rates in an Oxidizing Environment, ORNL/TM-10214, March 1989.

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