Reactor and Nuclear Systems Division

Lester Petrie

Lester M. Petrie, Jr.

S&T Staff
Nuclear Data and Criticality Safety Group
Reactor and Nuclear Systems Division
Nuclear Science and Engineering Directorate
Oak Ridge National Laboratory
P.O. Box 2008, Bldg. 5700
Oak Ridge, TN 37831-6170
Phone: 865.574.5259
Fax: 865.574.3527
petrielmjr@ornl.gov

Curriculum Vitae

Research Interests

  • nuclear criticality safety analyses and methods development
  • nuclear data processing methods and tools
  • reactor physics methods development
  • sensitivity and uncertainty analyses and methods development
  • radiation shielding

Education

  • B.Che., Chemical Engineering, Georgia Institute of Technology, Atlanta, GA, 1959
  • M.S., Nuclear Engineering, Massachusetts Institute of Technology, Cambridge, MA, 1962
  • Sc.D., Nuclear Engineering, Massachusetts Institute of Technology, Cambridge, MA, 1965

Publications

B. T. Rearden, L. M. Petrie, Jr., D. E. Peplow, M. A. Jessee, D. Wiarda, M. L. Williams, R. A. Lefebvre, J. P. Lefebvre, I. C. Gauld, and S. Goluoglu, "Scale 6.1 Enhancements for Nuclear Criticality Safety," in Proceedings of the International Conference on Nuclear Criticality, Edinburgh, U.K., September 19-22, 2011.

L. M. Petrie, Jr., R. A. Lefebvre, and D. Wiarda, "Standard Composition Library," Sect. M8 of SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, ORNL/TM-2005/39, Version 6.1, Oak Ridge National Laboratory, Oak Ridge, Tennessee, June 2011. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-785.

S. Goluoglu, L. M. Petrie, Jr., M. E. Dunn, D. F. Hollenbach, and B. T. Rearden, "Monte Carlo Criticality Methods and Analysis Capabilities in SCALE," Nucl. Technol. 174, 214-235, May 2011.

S. Goluoglu, J. Leppanen, L. M. Petrie, and M. E. Dunn, "SCALE Monte Carlo Eigenvalue Methods and New Advancements," in Proceedings of the Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010), Tokyo, Japan, October 17-21, 2010.

B. T. Rearden, C. M. Perfetti, M. L. Williams, and L. M. Petrie, Jr., "SCALE Sensitivity Calculations Using Contributon Theory," in Proceedings of the Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010), Tokyo, Japan, October 17-21, 2010.

B. T. Rearden, L. M. Petrie, and M. L. Williams, "Advances in Sensitivity Analysis Capabilities with SCALE 6.0 and 6.1," in Proceedings of the Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010), Tokyo, Japan, October 17-21, 2010.

D. E. Peplow and L. M. Petrie, Jr., "Criticality Accident Alarm System Modeling Made Easy With SCALE 6.1," Trans. Am. Nucl. Soc. 102, 297-299 (2010).

D. E. Peplow and L. M. Petrie, Jr., "Criticality Accident Alarm System Modeling with SCALE," in Proceedings of the International Conference on Mathematics, Computational Methods and Reactor Physics (M&C 2009), Saratoga Springs, NY, May 3-7, 2009.

S. M. Bowman, M. D. DeHart, M. E. Dunn, S. Goluoglu, J. E Horwedel, L. M. Petrie, Jr., B. T. Rearden, and M. L. Williams, "New Criticality Safety Analysis Capabilities in SCALE 5.1," in Proceedings of the 8th International Conference on Nuclear Criticality, St. Petersburg, Russia, May 28-June 1, 2007.

S. Goluoglu, M. E. Dunn, N. M. Greene, L. M. Petrie, and D. F. Hollenbach, "Generation and Testing of the ENDF/B-VI Continuous-Energy Cross-Section Library for Use with Continuous-Energy Versions of KENO," in Proceedings of the 8th International Conference on Nuclear Criticality, St. Petersburg, Russia, May 28-June 1, 2007.

D. F. Hollenbach, L. M. Petrie, and S. M. Bowman, "Advances in the KENO-VI Geometry Package," Trans. Am. Nucl. Soc. 95, 296-298 (2006).

S. M. Bowman, M. D. DeHart, and L. M. Petrie, "Integrated KENO Monte Carlo Transport for 3-D Depletion with SCALE," usr-stevebowman-1-paper.pdf in Proceedings of The Monte Carlo 2005 Topical Meeting, The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, Tenn., April 17-21, 2005, on CD-ROM, American Nuclear Society, La Grange Park, Ill. (2005).

M. E. Dunn, N. M. Greene, and L. M. Petrie, "Continuous-energy Version of KENO V.a for Criticality Safety Applications," pp. 439-446 in Proceedings of the 7th International Conference on Nuclear Criticality Safety (ICNC2003), October 20-24, 2003, Tokai-mura, Japan.

Y. Karni, D. Regev, E. Greenspan, S. Goluoglu, L. M. Petrie, and C. M. Hopper, "On the SMORES Capability for Minimum Critical Mass Determination," Trans. Am. Nucl. Soc. 88, 82-83 (2003).

C. M. Hopper, L. M. Petrie, L. J. Ott, and C. V. Parks, Design Parameters for a Natural Uranium UO3- or U3O8-Fueled Nuclear Reactor, ORNL/TM-2002/240, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 2002.

D. F. Hollenbach, L. M. Petrie, B. T. Rearden, and S. M. Bowman, "KENO Postprocessor Analysis and Plotting Capabilities," Trans. Am. Nucl. Soc. 87, 270-272 (2002).

C. V. Parks, B. D. Murphy, L. M. Petrie, and C. M. Hopper, Plutonium Production Using Natural Uranium From the Front-End of the Nuclear Fuel Cycle, ORNL/TM-2002/118, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 2002.

S. Goluoglu, L. M. Petrie, C. M. Hopper (ORNL); Y. Karni, D. Regev, and E. Greenspan (Univ. CA, Berkeley), "SMORES -- A New SCALE Sequence for the Determination of Bounding Curves and Data," Trans. Am. Nucl. Soc. 86, 114-116 (June 2002).

P. B. Fox and L. M. Petrie, Validation and Comparison of KENO V.a and KENO-VI, ORNL/TM-2001/110, UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2002.

C. V. Parks, B. T. Rearden, M. D. DeHart, B. L. Broadhead, and L. M. Petrie, Jr., "Final EMSP Report U.S. Department of Energy--Development of Nuclear Analysis Capabilities for DOE Waste Management Activities," April 2001.

S. M. Bowman, W. C. Jordan, J. F. Mincey, C. V. Parks, and L. M. Petrie, Experience With the SCALE Criticality Safety Cross-Section Libraries, NUREG/CR-6686 (ORNL/TM-1999/322), U.S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, October 2000.

S. M. Bowman et al., SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2R6), Vols. I, II, III, May 2000. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-545.

N. M. Greene, L. M. Petrie, and R. M. Westfall, "NITAWL-II: SCALE System Module for Performing Resonance Shielding and Working Library Production," Sect. F2 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. I-III, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), May 2000. Available from Radiation Shielding Information Center at Oak Ridge National Laboratory as CCC-545.

E. Greenspan, Y. Karni, L. M. Petrie, and D. Regev, SWANS: A Prototypic SCALE Criticality Sequence for Automated Optimization Using the SWAN Methodology, ORNL/TM-1999/274 (UCBNE-4226), UT-Battelle, LLC, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2000.

R. M. Westfall, L. M. Petrie, R. C. Little, and E. K. Fujita, "The Analytical Methods Task of the DOE Nuclear Criticality Safety Program, Status Review & Future Work Areas," DOE Nuclear Criticality Technology & Safety Workshop, Albuquerque, NM, March 29, 2000.

S. M. Bowman, J. E. Horwedel, D. L. Barnett, and L. M. Petrie, "SCALE Graphical Developments for Improved Criticality Safety Analyses," Vol. I, pp. 278-287 in Proceedings ICNC'99, Sixth International Conference on Nuclear Criticality Safety, Palais des Congres, Versailles, France, September 20-24, 1999.

C. V. Parks, M. D. DeHart, B. L. Broadhead, C. M. Hopper, and L. M. Petrie, "Development of Nuclear Analysis Capabilities for DOE Waste Management Activities," CONF-980736, pp. 222-223, in Proceedings of Environmental Management Science Program Workshop, Chicago, Ill., July 27-30, 1998.

C. V. Parks, M. D. DeHart, B. L. Broadhead, C. M. Hopper, and L. M. Petrie, Annual EMSP Summary Progress Report. Project Title: Development of Nuclear Analysis Capabilities for DOE Waste Management Activities, ORNL/TM-1999/101, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, June 1998.

D. F. Hollenbach and L. M. Petrie, "Comparison of the CENTRM Resonance Processor to the NITAWL Resonance Processor in SCALE," Trans. Am. Nucl. Soc. 78, 158 (1998).

D. F. Hollenbach and L. M. Petrie, "Assurances Associated with Monte Carlo Code Results," pp. 71-73 in Proceedings of the Nuclear Criticality Technology Safety Workshop, LA-13439-C, San Diego, CA, May 16-17, 1995 (April 1998).

M. E. Dunn, C. L. Bentley, S. Goluoglu, R. E. Pevey, H. L. Dodds, and L. M. Petrie, "Continuous-Energy Methods Development for the Monte Carlo Code KENO V.a," Trans. Am. Nucl. Soc. 76, 234-35, June 1997).

L. Petrie, D. Kent Parsons, and G. D. Spriggs, "KENO Lifetimes," Trans. Am. Nucl. Soc. 76, 367-368, June 1997.

C. V. Parks, L. M. Petrie, S. M. Bowman, N. M. Greene, and J. E. White, "SCAMPI: A Code Package for Cross-Section Processing," Vol. 2, p. 1080 in Proceedings of Rad. Prot. & Shielding 1996 Topical Meeting, Advances and Applications in Radiation Protection and Shielding (1996).

C. V. Parks, W. C. Jordan, L. M. Petrie, and R. Q. Wright, "Use of Metal/Uranium Mixtures to Explore Data Uncertainties," Trans. Am. Nucl. Soc. 73, 217-18 (1995).

W. C. Jordan, L. M. Petrie, R. Q. Wright, and C. V. Parks, "Calculation of k8 for Homogeneous 235U Metal Mixtures: Will the Real k8 Please Stand Up?," p. 29, Proceedings of Nuclear Criticality Technology Safety Project, LA-13277-C, Williamsburg, Va., May 10-11, 1994.

D. F. Hollenbach, N. F. Landers, and L. M. Petrie, "KENO Developments," p. 103, Proceedings of the Nuclear Criticality Technology Safety Project, Williamsburg, VA, May 10-11,1994.

D. F. Hollenbach, L. M. Petrie, and H. L. Dodds, "Vectorization Methods Development for a New Version of the KENO-V.a Criticality Safety Code," Nucl. Sci. Eng. 116(3), 147-64 (1994).

D. F. Hollenbach, L. M. Petrie, and N. F. Landers, "KENO VI: A Monte Carlo Criticality Program with Generalized Quadratic Geometry," (1993); pp. 58-63, Proceedings of Top. Meet. on Physics and Methods in Criticality Safety, Nashville, TN, Sept. 19-23, 1993.

D. F. Hollenbach, H. L. Dodds, and L. M. Petrie, "Improvements in the Vectorization of the KENO V.a Criticality Safety Code," Trans. Am. Nucl. Soc. 65, 241-42 (1992).

L. M. Petrie, N. F. Landers, N. M. Greene, and C. V. Parks, "New SCALE-4 Features Related to Cross- Section Processing," presented at Seminar on SCALE-4 and Related Modular Systems for the Evaluation of Nuclear Fuel Facilities and Package Design Featuring Criticality, Shielding, and Heat Transfer Capabilities, OECD NEA Data Bank, Saclay, France, September 17-19, 1991.

D. F. Hollenbach, W. Newmyer, B. Basoglu, H. L. Dodds, N. F. Landers, and L. M. Petrie, "Vectorization of the KENO V.a Criticality Safety Code," Trans. Am. Nucl. Soc. 64, 348-49 (1991).

N. F. Landers and L. M. Petrie, "Uncertainties Associated with the Use of the KENO Monte Carlo Criticality Codes," pp. 289-96, Proceedings of Int. Top. Meet. on Safety Margins in Criticality Safety, San Francisco, Nov. 26-30, 1989.

W. C. Jordan, C. V. Parks, and L. M. Petrie, "An Improved Dancoff Correction Factor for the SCALE Code System," Trans. Am. Nucl. Soc. 56, 324-325, June 1988.

R. M. Westfall, H. R. Dyer, and L. M. Petrie, Assessment of Criticality Computational Software for the U.S. Department of Energy Office of Civilian Radioactive Waste Management Applications, ORNL/CSD/TM-247, Oak Ridge National Laboratory, Oak Ridge, Tenn., 1988.

D. Ugolini, L. M. Petrie, and H. L. Dodds, "Evaluation of a Simplified Version of KENO V.a on a Parallel Processor Computer," Trans. Am. Nucl. Soc. 55, 326-27 (1987).

W. E. Ford III, J. W. Arwood, N. M. Greene, L. M. Petrie, R. T. Primm, M. W. Waddell, and C. C. Webster, "ANSL-V: ENDF/B-V Based Multigroup Cross-Section Libraries for Advanced Neutron Source (ANS) Reactor Studies," Trans. Am. Nucl. Soc. 55, 614-616 (1987).

W. C. Jordan, N. F. Landers and L. M. Petrie, Validation of KENO V.a Comparison with Critical Experiments, ORNL/CSD/TM-238, 1986.

C. V. Parks, L. M. Petrie, N. F. Landers, and J. A. Bucholz, "Computational Methods for Criticality Safety Analysis within the SCALE System," presented at the Workshop on the SCALE-3 Modular System, Saclay, France, 24-27 June 1986, Newsletter of the NEA Data Bank, No. 33, pp. 31-44, October 1986.

L. D. Bates, J. E. Van Cleve, Jr., J. P. Belk, G. W. Dahlberg, O. W. Hermann, R. W. McClung, R. K. Nanstad, L. M. Petrie, C. V. Parks, L. B. Shappert, M. Siman-Tov, W. C. Stoddart, J. S. Tang, and J. C. Turner, Summary of the Technical Review of the Safety Analysis Reports for Packaging (SARP) for the Transnuclear Transport/Storage Casks: TN-BRP and TN-REG, ORNL/TM-9889, Martin Marietta Energy Systems, Oak Ridge National Laboratory, July 1986.

L. M. Petrie, J. C. Turner, and G. B. Stewart, Review of PGDP Assessment of Criticality Safety Problems in Increasing Product Assay to 5 wt % U-235, ORNL/CSD/TM-225, Oak Ridge National Laboratory, Oak Ridge, Tenn., 1985.

L. M. Petrie, J. T. Thomas, Assessment of Computational Performance in Nuclear Criticality, ORNL/CSD/TM-224, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 1985.

R. M. Westfall, L. M. Petrie, N. M. Greene, and J. L. Lucius, "NITAWL-S: SCALE System Module for Performing Resonance Shielding and Working Library Production," Sect. F2 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Vols. I-III, NUREG/CR-0200 Rev. 3 (ORNL/NUREG/CSD-2/R3), December 1984.

J. A. Bucholz, J. R. Knight, C. V. Parks, L. M. Petrie, J. C. Turner, R. M. Westfall, and J. C. Ryman, "Standard Composition Library," Sect. M8 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation - Volume 3: Miscellaneous, ORNL/NUREG/CSD-2/V3/R1, U. S. Nuclear Regulatory Commission, Oak Ridge National Laboratory, 1983.

C. V. Parks, O. W. Hermann, T. J. Hoffman, N. F. Landers, L. M. Petrie, J. S. Tang, and W. D. Turner, "Standardized Analyses of Nuclear Shipping Containers," in Proceedings of the 7th Inter. Symp. on Packaging and Transportation of Radioactive Materials, May 15-20, 1983, New Orleans, La., Vol II, p. 1455 of CONF-830528, 479-80 (1983).

W. E. Ford III, B. R. Diggs, J. R. Knight, N. M. Greene, L. M. Petrie, C. C. Webster, R. M. Westfall, R. Q. Wright, and M. L. Williams, "The CSRL-V ENDF/B-V 227-Group Neutron Cross-Section Library and Its Application to Thermal Reactor and Criticality Safety Benchmarks," in Proceedings of Thermal Reactor Benchmark Calculations, Techniques, Results, and Applications, May 17-18, 1982, Electric Power Research Institute, Upton, N.Y., EPRI NP-2855, pp. 19-1 - 19-25, 1983.

J. T. West, L.M. Petrie, S. K. Fraley, KENO-IV/CG, The Combinatorial Geometry Version of the KENO: Monte Carlo Criticality Safety Program, NUREG/CR-0709 (ORNL/UREG/CSD-7), Oak Ridge National Laboratory, Oak Ridge, Tenn., September 1979.

T. J. Hoffman, S. K. Fraley, R. M. Westfall, and L. M. Petrie, "Monte Carlo Radioactive Heat Transfer for Spent-Fuel Shipping Casks," Trans. Am. Nucl. Soc. 28, 262-3 (1978).

R. M. Westfall and L. M. Petrie, "Standardized Safety Analysis of Nuclear Fuel Shipping Containers," pp. 842-849 in Proceedings of the Fifth International Symposium on Packaging and Transportation of Radioactive Materials, May 7-12, 1978, Las Vegas, NV.

L. M. Petrie, N. F. Cross, KENO IV-An Improved Monte Carlo Criticality Program, ORNL-4938, Oak Ridge National Laboratory, Oak Ridge, Tenn., November 1975.

J. R. Knight and L. M. Petrie, 16 and 123 Group Weighting Functions for KENO, ORNL/TM-4660, Union Carbide Corp., Oak Ridge National Laboratory, November 1975.