Randy A. Schwarz

Picture of Randy A. Schwarz

Randy Schwarz
PO Box 1308
Richland, WA 99352 USA
RandySchwarz@mcnpvised.com

Education
M.S. Computer Science, Washington State University, Richland, WA, May 2005.
M.S. Nuclear Engineering, University of Washington, Richland, WA, June 1990.
B.S. Physics, Western Washington University, Bellingham, WA, June 1986.
A.A. Degree, Everett Community College, Everett, WA, June 1982.
Technical Capabilites

Graphical User Interface Development

Co-developer (with Lee Carter, Carter M.C. Analysis) of the MCNP Visual Editor, a graphical user interface for the MCNP computer code. Currently distributed internationally through the Nuclear Energy Agency in France and nationally through the Radiation Safety Information Computational Center in Oak Ridge, Tennessee.

Computer Applications and Programming

Created a computer program for reactor operations at the Fast Flux Test Facility to calculate the decay heat of assemblies.
Prime developer of the MCNP Visual Editor, involving thousands of lines of C code and the creation of a graphical user interface.
Wrote a program to calculate temperatures in test fuel pins irradiated in a light water reactor. Includes a graphical animations show temperature over time.

Source Term Generation

Used ORIGEN-2 to calculate isotropic inventories and neutron and gamma ray source terms for reactor fuel assemblies, transportation applications, and waste tanks. Created cross section database for K-Basin fuel.
Used ORIGENS to calculate inventories in NRC monitored reactors.

Neutronics Calculations

Performed reactor physics calculations for the Fast Flux Test Facility (FFTF), a liquid metal reactor.
Performed core design calculations for light water reactors using the WIMS and MCNP computer codes.

Shielding Analysis

Performed numerous shielding analysis for transportation casks, nuclear facilities, and waste tank risers.

Scientific Visualization

Developed an interactive ALARA tool, using color animations, to calculate dose rates to operations personnel around a nuclear waste tank.
Developed interactive ALARA tool for calculating dose rates for the transportation of radioactive materials inside a shipping casks.
Made numerous visualizations of complex nuclear behavior using MCNP data.

Awards

1998 Named Tri-Cities Engineer of the Year, Nominated by the American Nuclear Society
1992 Information Systems Advisory Council Award
1990 Information Systems Advisory Council Award
1989 Westinghouse Signature Award of Excellence.

Publications
Technical Meeting Publications

R. J. Morford, W. L. Bunch, L. L. Carter, J. W. Daughtry, R. A. Schwarz, and W. P. Stinson, "Source Term and Shielding Calculations to Support Decommissioning of Shippingport Reactor," Proceedings of the Seventh International Conference on Radiation Shielding, September 12-16, 1988, Winfrith, England, Vol. I, (1988).
L. L. Carter, W. L. Bunch, R. J. Morford, D. W. Wootan, and R. A. Schwarz, "Monte Carlo Applications for The Design and Operation of Nuclear Facilities," Proceedings of the Seventh International Conference on Radiation Shielding, September 12-16, 1988, Winfrith, England, Vol. II, (1988).
L. L. Carter and R. A. Schwarz, "Preliminary Shield Design for the SP-100 Ground Test," Proceedings of the 6th Symposium on Space Nuclear Power Systems, January 9-12, 1989, Albuquerque, New Mexico.
L. L. Carter, D. W. Wootan and R. A. Schwarz, "Monte Carlo Optimization Technique Applied to Plutonium-238 Production in FFTF," Trans. Amer. Nucl. Soc., 60, p. 637-638 (1989).
R. A. Schwarz, L. B. Brix and L. L. Carter, "Calculating the Decay Heat of Assemblies at the Fast Flux Test Facility," Proceedings of the American Nuclear Society Western Regional Paper Conference, April 6-8, 1989, Corvallis, Oregon.
D. W. Wootan, H. R. Brager, L. L. Carter, A. H. Lu, F. M. Mann, W. Y. Matsumato, J. A. Rawlins, R. E. Schenter, F. A. Schmittroth, R. A. Schwarz, R. L. Simons, "Isotope Production Test in the Fast Flux Test Facility," Proceedings of the Seventh American Society for Testing and Materials - EURATOM Symposium on Reactor Dosimetry, August 27-31, 1990, Strasboug, France
R. A. Schwarz, L. L. Carter and D. W. Wootan, "Calculational Methods Used in Evaluating the Multi-Isotope Production Assembly Experiment," Trans. Amer. Nucl. Soc., 61, p. 346-347 (1990).
J. A. Rawlins, F. A. Schmittroth, F. M. Mann, R. E. Schenter, A. H. Lu, L. L. Carter, D. W. Wootan and R. A. Schwarz, H. R. Bragger, W. Y. Mattsumoto, "Physics of Plutonium-238 Production in the Fast Flux Test Facility," Trans. Amer. Nucl. Soc., 60, p. 276-277 (1990).
R. A. Schwarz, J. H. Lu and N. Shrivastava, "Graphical Post-Processor Created for the ORIGEN2 Code," Proceedings of the American Nuclear Society Topical New Horizons in Radiation Protection and Shielding, p. 56-63, April 26-May 1, 1992, Pasco, Washington.
H. Lu, R. A. Schwarz and R. L. Simons, "Benchmark Calculation for FFTF Inner Radial Shield Damage Rates," Proceedings of the American Nuclear Society Topical New Horizons in Radiation Protection and Shielding, p. 313-320, April 26-May 1, 1992, Pasco, Washington.
R. A. Schwarz, L. L. Carter, F. A. Schmittroth and L. B. Brown, "Online Calculation of the Decay Heat of Assemblies at the Fast Flux Test Facility," Proceedings of the American Nuclear Society Topical New Horizons in Radiation Protection and Shielding, p. 480, April 26-May 1, 1992, Pasco, Washington.
R. A. Schwarz and J. S. Lan, "Methods for Calculating Dose Rates from Large Nuclear Reactor Fuel Arrays," Proceedings of the American Nuclear Society Topical New Horizons in Radiation Protection and Shielding, p. 573-577, April 26-May 1, 1992, Pasco, Washington.
R. A. Schwarz, L. L. Carter, T. P. Dole, S. M. Fredrickson, and B. M. Templeton, "Graphical User Input Interface for MCNP," Trans. Amer. Nucl. Soc., 69, p. 401 (1993).
J. Alderman, S. S. Shiraga, R. A. Schwarz, R. J. Smith, D. W. Wootan, "Neptunium Storage at Hanford," Proceedings of the 11th Symposium on Space Nuclear Power and Propulsion, January 9-13, 1994, Albuquerque, New Mexico.
J. S. Lan, R. A. Schwarz, R. A. Karnesky, J. Greenborg and R. P. Omberg, "Reducing Accessibility of Weapons Plutonium," Trans. Amer. Nucl. Soc., 70, p. 70-71 (1994).
R. A. Schwarz, L. L. Carter and K. E. Hillesland, "Calculation of Radiation Fields for Hanford Site Tank Riser Modifications," Trans. Amer. Nucl. Soc., 71, p. 603 (1994).
R. A. Schwarz, L. L. Carter and K. E. Hillesland, "Calculation of Radiation Fields for Hanford Site Tank Riser Modifications," Decommissioning, Decontamination, and Environmental Restoration at Contaminated Nuclear Sites, Vol. 2, p. 345-349, November 13-18, 1994, Washington D. C.
J. R. Green, R. A. Schwarz, K. E. Hillesland, V. E. Roetman, J. G. Field,, "Introduction to Radcalc: A Computer Program to Calculate the Radiolytic Production of Hydrogen Gas from Radioactive Wastes in Packages," Proceedings of 1995 U. S. Department of Energy Defense Programs 2nd Annnual Packaging Workshop, June 12-15, 1995, San Francisco, California.
R. A. Schwarz, D. E. Bullock, J. Greenborg, "ALARA Calculations Using Interactive Visualization Tools," Proceedings of the 1996 Topical on Radiation Protection and Shielding, Vol. 2, p.1004-1011, 1996, No.Falmouth, Massachusetts.
Y. Y. Liu, R. A. Schwarz, J. S. Tang, "Monte Carlo Simulation of Radiation Streaming from a Radioactive Material Shipping Cask," Proceedings of the 1996 Topical on Radiation Protection and Shielding, Vol. 2, p.1053-1060, 1996, No.Falmouth, Massachusetts.
L. L. Carter, R. A. Schwarz, "Visual Creation of Lattice Geometries for MCNP Criticality Calculations," Trans. Amer. Nucl. Soc., 77, p. 223 (1997).
R. A. Schwarz, L. L. Carter, "Visual Editor to Create and Display MCNP Input Files," Trans. Amer. Nucl. Soc., 77, p. 311-312 (1997).
R. A. Schwarz, Lee L. Carter, Karl E. Hillesland Victor, E. Roetman, "Advanced MCNP Input File Creation Using the Visual Editor," Proceedings of the American Nuclear Society Topical on Technologies for the New Century, Vol. 2, p.317-324, April 19-23,1998, Nashville Tennessee.
L. L. Carter, R. A. Schwarz, "The Visual Creation and Display of MCNP Geometries and Lattices for Criticality Problems," Trans. Amer. Nucl. Soc., (1999).
L. L. Carter, R. A. Schwarz, J. Pfohl, "A Microsoft Windows Version of the MCNP Visual Editor," Trans. Amer. Nucl. Soc., 81, p. 256-257 (1999).
R. A. Schwarz, L. L. Carter, W Brown, "Particle Track Visualization Using the MCNP Visual Editor," Proceedings of the Topical on Radiation Protection for Our National Priorities Medicine, the Environment and, the Legacy, p.324-331, 2000, Spokane, Washington.
R. A. Schwarz, L. L. Carter, "Current State of Monte Carlo Visualization Tools," Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, p. 815-819, October 23-26, 2000, Lisbon Portugal.
R. A. Schwarz, "Current Status of the MCNP Visual Editor," Proceedings of the 2002 Topical on Radiation Protection and Shielding, April 14-18, 2002, Santa Fe, New Mexico.
R. A. Schwarz, "Fission Source Visualization for Criticality Problems using Source Point Generation Plotting," Proceedings of the 2002 Topical on Radiation Protection and Shielding, April 14-18, 2002, Santa Fe, New Mexico.
R. A. Schwarz, "Simple Visualization Techniques used to Optimize the Shielding Configuration of a Reactor on Mars," Proceedings of the 2002 Topical on Radiation Protection and Shielding, April 14-18, 2002, Santa Fe, New Mexico.
A.L. Schwarz, R. A. Schwarz, and L. L. Carter, "3-D Plotting Capabilities in the Visual Editor for Release 5 of MCNP," Proceedings of the 2003 Topical on Mathematical and Computational Sciences, April 6-10, 2003, Gatlinburg, Tennessee.
R.A.. Schwarz, A.L.. Schwarz, and L. L. Carter, " Conversion Of Computer Aided Design (CAD) Output Files To Monte Carlo N-Particle (MCNP) Input Files," The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, TN, April 17-21, 2005
R.A.. Schwarz, A.L.. Schwarz, and L. L. Carter, " Wizards and Visualization Features for MCNP Geometries and Sources," The American Nuclear Society’s 14th Biennial Topical Meeting of the Radiation Protection and Shielding Division, Carlsbad New Mexico, USA. April 3-6, 2006.

International Meeting Publications

L. L. Carter, J. S. Lan, and R. A. Schwarz, "Enhanced Physics Design with Hexagonal Repeated Structure Tools Using Monte Carlo Methods," Proceedings of the International Topical Meeting, Advances in Mathematics, Computations, and Reactor Physics, April 28 - May 2, 1991.
R. A. Schwarz, L. L. Carter and N. Shrivastava, "Creation of MCNP Input Files with a Visual Editor," Proceedings of the 8th International Conference on Radiation Shielding, p. 454-459, April 24-28, 1994, Arlington, Texas.
R. A. Schwarz, R. J. Morford, L. L. Carter, G. B. Jones, and J. Greenborg, "Operational Dose Rate Visualization Techniques," Proceedings of the 8th International Conference on Radiation Shielding, p. 1225-1232, April 24-28, 1994, Arlington, Texas.
R. A. Schwarz, L. L. Carter, "Visual Editor for Creating MCNP Input Files," Proceedings of the International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, p. 1146-1147, April 30 - May 4, 1995, Portland, Oregon.
Randolph A. Schwarz, Steve F. Kessler, Tom A Tomaszewski, "Dose Rate Visualization of Radioisotope Thermoelectric Generators," Proceedings of the Space Technology and Applications International Forum, p.1481-1486, January 7-11, 1996, Albuquerque, NM.

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