Biographical Sketch of Randolph Allen Schwarz 

Education:

M.S. Computer Science, Washington State University, Tri-Cities, WA, 2005.

M.S. Nuclear Engineering, University of Washington, Tri-Cities, WA, 1990.

B.S. Physics, Western Washington University, Bellingham, WA, 1986.

Positions and Experience:

Visual Editor Consultants, Richland, WA, 7/01 – present, Owner. Responsibilities: MCNP Visual Editor development.

Battelle, Richland, WA, 10/96 – 12/2006, Senior Research Engineer, Materials and Engineering Analysis. Responsibilities: Nuclear Engineer with expertise in Monte Carlo N-Particle (MCNP) applications and scientific visualization.

Westinghouse Hanford Company, Richland, WA, 9/86 – 9/96, Advanced Scientist, Radiation Physics and Shielding. Responsibilities: Shielding and reactor physics analysis.

Research and Professional Experience:

Principal Investigator for the following Grants:

• DOE Phase 1 grant, July 22, 2002, through April 21, 2003, DE-FG03-02ER83568

• DOE Phase 2 grant, June 27, 2003 through June 26, 2005, DE-FG02-03ER83844

• DOE Phase 1 grant, June 27, 2005 through March 26, 2006,  DE-FG02-05ER84178

• NASA Phase 1 grant, January 20, 2006 through July 24, 2006,  NNL06AA48P

• DOE Phase 1 grant, June 20, 2007 through March 19, 2008,  DE-FG02-07ER84735         

• NASA Phase 2 grant, December 1, 2006 through December 2, 2008,  NNL07AA10C

Graphical User Interface Development

·         Creator of the MCNP Visual Editor (RSICC PSR-358, PSR-500, CCC-730), 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.

·         Created a computer program for reactor operations at the Fast Flux Test Facility (FFTF) to calculate the decay heat of assemblies.

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 ORIGEN-S to calculate inventories in NRC monitored reactors.

Neutronics Calculations       

·         Performed reactor physics calculations for the 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 analyses 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 cask.

·         Created numerous visualizations of complex nuclear behavior using MCNP data.

Awards:

1998 Tri-Cities Engineer of the Year.  Awarded by the Washington Society of Professional Engineers.

Technical Meeting Publications:

R.A. Schwarz, L.L. Carter, T.P. Dole, S.M. Fredrickson, and B.M. Templeton, “Graphical User Input Interface for MCNP,” Trans. Am. Nucl. Soc., 69, 401 (1993).

R.A. Schwarz, L.L. Carter, and N. Shrivastava, “Creation of MCNP Input Files with a Visual Editor,” Proc. 8th Int. Conf. on Radiation Shielding, 454-459, April 1994, Arlington, Texas.

R.A. Schwarz, R.J. Morford, L.L. Carter, G.B. Jones, and J. Greenborg, “Operational Dose Rate Visualization Techniques,” Proc. 8th Int. Conf. on Radiation Shielding, 1225-1232, April 1994, Arlington, Texas.

R.A. Schwarz and L.L. Carter, “Visual Editor for Creating MCNP Input Files,” Proc. Int. Conf. on Mathematics and Computations, Reactor Physics, and Environmental Analyses, 1146-1147, April 30 - May 4, 1995, Portland, Oregon.

R.A. Schwarz, D.E. Bullock, and J. Greenborg, “ALARA Calculations Using Interactive Visualization Tools,” Proc. 1996 Topical on Radiation Protection and Shielding, Vol. 2, 1004-1011, 1996, No. Falmouth, Massachusetts.

R.A. Schwarz and L.L. Carter, “Visual Editor for Creating MCNP Input Files,” Proc. Int. Conf. on Mathematics and Computations, Reactor Physics, and Environmental Analyses, 1146-1147, April 30 - May 4, 1995, Portland, Oregon.

L.L. Carter and R.A. Schwarz, “Visual Creation of Lattice Geometries for MCNP Criticality Calculations,” Trans. Amer. Nucl. Soc., 77, 223 (1997).

R.A. Schwarz and L.L. Carter, “Visual Editor to Create and Display MCNP Input Files,” Trans. Amer. Nucl. Soc., 77, 311-312 (1997).

R.A. Schwarz, L.L. Carter, K.E. Hillesland, and V.E. Roetman, “Advanced MCNP Input File Creation Using the Visual Editor,” Proc. Am. Nucl. Soc. Topical, Technologies for the New Century, 2, 317-324, April 1998, Nashville, Tennessee.

L.L. Carter and 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, and J. Pfohl, “A Microsoft Windows Version of the MCNP Visual Editor,” Trans. Amer. Nucl. Soc., 81, 256-257 (1999).

R.A. Schwarz, L.L. Carter, and W. Brown, “Particle Track Visualization Using the MCNP Visual Editor,” Proc. Am. Nucl. Soc. Topical Radiation Protection for Our National Priorities Medicine, the Environment and, the Legacy, 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.