LESTER M. PETRIE, JR.

PUBLICATIONS

2009

2008

2007

2006

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).

2005

Fox, P. B., L. M. Petrie, Jr., and C. M. Hopper, Minimum Critical Values Study, ORNL/TM-2003/211, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2005.

Dunn, M. E., N. M. Greene, and L. M. Petrie, "Status of ORNL Cross-Section Processing and Library Generation Capabilities," presented at the International Workshop on Nuclear Data for Generation IV Nuclear Energy Systems, Antwerp, Belgium, April 5-7, 2005.

Dunn, M. E., P. B. Fox, N. M. Greene, and L. M. Petrie, "ENDF/B-VI Library Generation and Testing for the SCALE Code System," Trans. Am. Nucl. Soc. 92, 758-759 (2005).

Williams, M. L., S. Goluoglu, and L. M. Petrie, "Recent Enhancements to the SCALE 5 Resonance Self-Shielding Methodology," Trans. Am. Nucl. Soc. 92, 751-753 (2005).

Bowman, S. M., M. D. DeHart, and L. M. Petrie, "Integrated KENO Monte Carlo Transport for 3-D Depletion with SCALE," in The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, Tennessee, April 17-21, 2005 .

Dunn, M. E., D. F. Hollenbach, and L. M. Petrie, "Monte Carlo Methods Development for a Continuous-Energy Version of Keno," in The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, Tennessee, April 17-21, 2005 .

2004

DeHart, M. D., and L. M. Petrie, “A Radioisotope Depletion Method Using Monte Carlo Transport with Variance Reduction and Error Propagation,” Proc. of ANS: PHYSOR 2004 "The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments," Chicago, IL, April 25-29, 2004.

Dunn, M. E., N. M. Greene, and L. M. Petrie, “Point KENO V .a: A Continuous-Energy Monte Carlo Code for Transport Applications,” Proc. of ANS: PHYSOR 2004 "The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments," Chicago, IL, April 25-29, 2004.

2003

Karni, Y., D. Regev, E. Greenspan, S. Goluoglu, L. M. Petrie, and C. M. Hopper, “On the SMORES Capability for Minimum Critical Mass Determination,” in Proc. of ANS 2003 Annual Meeting “The Nuclear Technology Expansion: Unlimited Opportunities,” June l–5, 2003, San Diego, CA. [Summary]. Trans. Am. Nucl. Soc. 88, 82–83 (June 2003).

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

Karni, Y., D. Regev, E. Greenspan, S. Goluoglu, L. M. Petrie, and C. M. Hopper, “The SMORES Capability for Minimum Critical Mass Determination,” in Proc. of The 7th International Conference on Nuclear Criticality Safety (ICNC2003), October 20–24, 2003, Tokai-mura, Japan.

2002

Hopper, C. M., L. M. Petrie, L. J. Ott, and C. V. Parks, Design Parameters for a Natural Uranium UO 3 or U 3O 8 Fueled Nuclear Reactor, ORNL/TM-2002/240, UT-Battelle, LLC, Oak Ridge National Laboratory, November 2002.

Fox, P. B., 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, May 2002.

Goluoglu, S., L. M. Petrie, C. M. Hopper; Y. Karni, D. Regev, and E. Greenspan, “SMORES – A New SCALE Sequence for the Determination of Bounding Curves and Data,” in Proc. of American Nuclear Society, 2002 Annual Meeting “The Revival of the Nuclear Energy Option,” June 9–13, 2002, Hollywood, FL. Trans. Am. Nucl. Soc. 86, 114–116 (June 2002).

Parks, C. V., 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, September 2002.

Hollenbach, D. F., L. M. Petrie, B. T. Rearden, and S. M. Bowman, “KENO Postprocessor Analysis and Plotting Capabilities,” in Proc. of American Nuclear Society 2002 Winter Meeting “Building the World Nuclear Community -- Strategies for the Deployment of New Nuclear Technologies”, November 17–21, 2002, Washington, DC. Trans. Am. Nucl. Soc. 87, 270–272 (2002).

2001

Parks, C. V., 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, UT-Battelle, LLC, Oak Ridge National Laboratory, April 2001.

Hopper, C. M., L. M. Petrie, and D. F. Hollenbach, Results and Interpretations for Establishing Criticality Indexes for Material Handling and Storage Configurations, ORNL/CF-01/28, UT-Battelle, LLC, Oak Ridge National Laboratory, May 2001 (Letter Report to M. Brady Raap).

Hopper, C. M., L. M. Petrie, and D. F. Hollenbach, Classified Confirmatory Nuclear Criticality Scoping Calculations, ORNL/CF-01/28, May 2001. Document is classified, but title and number is not classified (per CMH 5/29/2001)

Hollenbach, D. F., L. M. Petrie, P. B. Fox, and K. R. Elam, “SCALE 5: New Cross-Section Processing Features and Capabilities,” 35390.pdf in Proc. of 2001 ANS Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety, November 11–15, 2001, Reno, NV. [ANS Order No.: 700284; ISBN: 0-89448-659-4]

2000

Parks, C. V., B. T. Rearden, M. D. DeHart, B. L. Broadhead, C. M. Hopper, and L. M. Petrie, Annual Environmental Management Science Program (EMSP) Project Summary. Project Title: Development of Nuclear Analysis Capabilities for DOE Waste Management Activities, ORNL/TM-2000/65, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, February 2000.

Westfall, R. M., 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, March 29, 2000, Albuquerque, NM.

Bowman, S. M., B. L. Broadhead, C. B. Bryan, J. A. Bucholz, K. W. Childs, A. L. Edwards, M. B. Emmett, P. B. Fox, S. K. Fraley, G. E. Gilels, N. M. Greene, O. W. Hermann, T. J. Hoffman, D. F. Hollenbach, W. C. Jordan, J. R. Knight, N. F. Landers, L. C. Leal, K. Lucius, C. V. Parks, L. M. Petrie, J. C. Ryman, J. S. Tang, J. C. Turner, J. T. West, R. M. Westfall, and P. T. Williams, 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.

Bowman, S. M., 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), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2000.

Rearden, B. T., L. M. Petrie, and D. F. Hollenbach, "Sensitivity and Uncertainty Analysis for Nuclear Criticality Safety Using KENO in the SCALE Code System," Section NG-V/01, pp. 230–231, 2000 in Proc. of Monte Carlo 2000 — Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation Applications, October 23–26, 2000, Lisbon, Portugal. [abstract]

Greenspan, E., 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, December 2000.

1999

Parks, C. V., B. T. Rearden, M. D. DeHart, B. L. Broadhead, C. M. Hopper, and L. M. Petrie, Annual Environmental Management Science Program (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 1999.

Bowman, S. M., J. E. Horwedel, D. L. Barnett, and L. M. Petrie, “SCALE Graphical Developments for Improved Criticality Safety Analyses,” pp. 278–287 in Proc. of ICNC'99, Sixth International Conference on Nuclear Criticality Safety, Vol. I, Palais des Congrès, Versailles, FRANCE, September 20–24, 1999. [Paper]

Greenspan, E., Y. Karni, D. Regev, and L. M. Petrie, “The SWAN-SCALE Code for Optimization of Critical Systems,” in Proc. of American Nuclear Society 1999 Winter Meeting, November 14–18, 1999, Long Beach, CA. Trans. Am. Nucl. Soc., 81, 170–171 (1999).

1998

Hollenbach, D. F., 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, May 16–17, 1995, San Diego, CA (April 1998).

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

Parks, C. V., 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 Proc. of Environmental Management Science Program Workshop, July 27-30, 1998, Chicago, IL (Poster 113).

1997

Dunn, M. E., 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, 234–235 (June 1997).

Petrie, L., D. Kent Parsons, and G. D. Spriggs, “KENO Lifetimes” Trans. Am. Nucl. Soc. 76, 234–235 (June 1997).

Bowman, S. M., B. L. Broadhead, D. F. Hollenbach, and L. M. Petrie, Jr., Joint Report of Foreign Travel to Rez (near Prague), Czech Republic, ORNL/FTR-6399, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, October 9–18, 1997.

Parks, C. V., M. D. DeHart, B. L. Broadhead, C. M. Hopper, and L. M. Petrie, “Development of Nuclear Analysis Capabilities for DOE Waste Management Activities,” Environmental Management Science Program Workshop, July 27–30, 1998, Chicago, IL, CONF-980736, July 1998 (Poster 113).

1996

Bowman, S. M., B. L. Broadhead, and L. M. Petrie, Joint Report of Foreign Travel by S. M. Bowman, B. L. Broadhead, and L. M. Petrie, ORNL/FTR-5858, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, July 1996.

Parks, C. V., L. M. Petrie, S. M. Bowman, B. L. Broadhead, N. M. Greene, and J. E. White, “SCAMPI: A Code Package for Cross-Section Processing,” Vol. 2, pp. 1080–1087 in Proc. Radiation Protection & Shielding 1996 Topical Meeting, Advances and Applications in Radiation Protection and Shielding, April 21–25, 1966, No. Falmouth, Mass., 1996.

1995

Bowman, S. M., R. Q. Wright, M. D. DeHart, C. V. Parks, and L. M. Petrie, “Recent Validation Experience with Multigroup Cross-Section Libraries and SCALE,” Presented at Fifth International Conference on Nuclear Criticality Safety, ICNC’95, September 17‑21, 1995, Albuquerque, NM (1995).

Hollenbach, D. F., S. M. Bowman, L. M. Petrie, and C. V. Parks, “New Enhancements to SCALE for Criticality Safety Analysis,” presented at Fifth International Conference on Nuclear Criticality Safety, ICNC’95, September 17–21, 1995, Albuquerque, NM (1995).

Parks, C. V., W. C. Jordan, L. M. Petrie, and R. Q. Wright, “Use of Metal/Uranium Mixtures to Explore Data Uncertainties,” Trans. Am. Nucl. Soc. 73, 217–218 (1995).

1994

Jordan, W. C., L. M. Petrie, R. Q. Wright, and C. V. Parks, “Calculation of k infinity for Homogeneous 235U Metal Mixtures: Will the Real k infinity Please Stand Up?,” p. 29–31 in Proc. Nuclear Criticality Technology Safety Project, LA-13277-C, May 10–11, 1994, Williamsburg, VA (1994).

Hollenbach, D. F., N. F. Landers, and L. M. Petrie, “KENO Developments,” p. 103 in Proc. of the Nuclear Criticality Technology Safety Project, May 10–11, 1994, Williamsburg, VA (1994).

Hollenbach, D. F., 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).

1993

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

1992

Greene, N. M., W. E. Ford III, L. M. Petrie, and J. W. Arwood, AMPX-77: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Cross-Section Libraries from ENDF/B-IV and/or ENDF/B-V, ORNL/CSD/TM-283, Martin Marietta Energy Systems, Oak Ridge National Laboratory, October 1992.

Hollenbach, D. F., H. L. Dodds, and L. M. Petrie, “Improvements in the Vectorization of the KENO V.a Criticality Safety Code,” Trans. Am. Nucl. Soc. 65, 241–242 (1992).

1991

Petrie, L. M., 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, September 17–19, 1991, OECD NEA Data Bank, Saclay, France.

Petrie, L. M., “Vectorization of the KENO V.a Criticality Safety Code,” 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, September 17-19, 1991, OECD NEA Data Bank, Saclay, France.

Childs, R. L., L. M. Petrie, and N. F. Landers, “A User's Guide for the Starter Computer Program,” ORNL/TM-11872, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.

Parks, C. V., and L. M. Petrie, Report of Foreign Travel by C. V. Parks and L. M. Petrie, ORNL/CSD/FTR-4105, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1991.

Hollenbach, D. F., 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, 348–349 (1991).

Parks, C. V., L. M. Petrie, J. Manneschmidt, and J. L. Bartley, “SCALE-4: An Updated Version of the Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation,” in Proc. of ANS/ENS International Topical Meeting on Advances in Mathematics, Computations, and Reactor Physics, April 28–May 1, 1991, Pittsburgh, PA.

1990

Whitesides, G. E., and L. M. Petrie, Report of Foreign Travel by L. M. Petrie and G. E. Whitesides, ORNL/CSD/FTR-3621, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1990.

Ford, W. E., J. W. Arwood, N. M. Greene, D. L. Moses, L. M. Petrie, R. T. Primm, C. O. Slater, R. M. Westfall, and R. Q. Wright, ANSL-V: ENDF/B-V Based Multigroup Cross-Section Libraries for Advanced Neutron Source (ANS) Reactor Studies , ORNL-6618, 1990.

1989

Landers, N. F., and L. M. Petrie, “Uncertainties Associated with the Use of the KENO Monte Carlo Criticality Codes,” pp. 289–296 in Proc. International Topical Meeting on Safety Margins in Criticality Safety, November 26–30, 1989, San Francisco, CA (1989).

Whitesides, G. E., and L. M. Petrie, Report of Foreign Travel by G. E. Whitesides and L. M. Petrie, ORNL/CSD/FTR-3328, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1989.

1988

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

Westfall, R. M., 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, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1988.

1987

Ford, W. E. 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).

Wright, R. Q., W. E. Ford III, N. M. Greene, L. M. Petrie, R. T. Primm III, and R. M. Westfall, “Benchmarking of the 99-Group ANSL-V Library,” Winter Meet. Am. Nucl. Soc., November 15–19, 1987, Los Angeles, CA.

Arwood, J. W., W. E. Ford III, N. M. Greene, L. M. Petrie, R. T. Primm III, M. W. Waddell, C. C. Webster, R. M. Westfall, and R. Q. Wright, “Preparation and Benchmarking of ANSL-V Cross Sections for Advanced Neutron Source Reactor Studies,” Trans. Am. Nucl. Soc. 55, 614–616 (1987).

Petrie, L. M., and G. E. Whitesides, Report of Foreign Travel by L. M. Petrie and G. E. Whitesides, ORNL/CSD/FTR-2545, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1987.

Ugolini, D., L. M. Petrie, and H. L. Dodds, Jr., “Evaluation of a Simplified Version of KENO-V.a on a Parallel Processor Computer,” Trans. Am. Nucl. Soc. 55, 326–327 (1987).

1986

Jordan, W. C., N. F. Landers and L. M. Petrie, Validation of KENO-V.a: Comparison with Critical Experiments, ORNL/CSD/TM-238, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1986.

Parks, C. V., L. M. Petrie, N. F. Landers, and J. A. Bucholz, “Computational Methods for Criticality Safety Analysis within the SCALE System,” 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.

Petrie, L. M., and G. E. Whitesides, Report of Foreign Travel by L. M. Petrie and G. E. Whitesides, ORNL/CSD/FTR-2300, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1986.

Bates, L. D., J. E. Van Cleve, Jr., J. P. Belk, G. W. Dahlberg, O. W. Hermann, R. W. McClung, R. K. Nanstad, and L. M. Petrie, 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, 1986.

1985

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

Parks, C. V., L. M. Petrie, O. W. Hermann, J. C. Turner, and J. S. Tang, Final Report on Review of TN-REG SARP: Criticality Safety Shielding, and Decay Heat Generation, ORNL/CSD/INF-85/4, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

Parks, C. V., L. M. Petrie, O. W. Hermann, and J. C. Turner, Final Report on Review of TN-BRPSARP: Criticality Safety, Shielding, and Decay Heat Generation, ORNL/CSD/INF-85/3, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

Petrie, L. M., Report of Foreign Travel by L. M. Petrie, ORNL/CSD/FTR-2175, Martin Marietta Energy Systems, Oak Ridge National Laboratory, 1985.

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

1984

Landers, N. F., and L. M. Petrie, “CSAS4: An Enhanced Criticality Safety Analysis Module with an Optimum Pitch Search Option,” ORNL/NUREG/CSD-2/Vol. 1, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Westfall, R. M., L. M. Petrie, N. M. Greene, and J. L. Lucius, “NITAWL-S: SCALE System Module for Performing Resonance Shielding and Working Library Production,” ORNL/NUREG/CSD-2/Vol. 2, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Greene, N. M., and L. M. Petrie, “XSDRNPM-S: A One-Dimensional Discrete-Ordinates Code for Transport Analysis,” ORNL/NUREG/CSD-2/Vol. 2, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Petrie, L. M., and N. F. Landers, “KENO-IV/S: An Improved Monte Carlo Criticality Program,” ORNL/NUREG/CSD-2/Vol. 2, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Greene, N. M., L. M. Petrie, and S. K. Fraley, “ICE-S: Module to Mix Multigroup Cross Sections,” ORNL/NUREG/CSD-2/Vol. 2, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Petrie, L. M., and N. F. Landers, “KENO-V.a: An Improved Monte Carlo Criticality Program with Supergrouping,” ORNL/NUREG/CSD-2/Vol. 2, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Petrie, L. M., “SCALE Driver System,” ORNL/NUREG/CSD-2/Vol. 3, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Petrie, L. M., “SCALE Subroutine Library,” ORNL/NUREG/CSD-2/Vol. 3, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Petrie, L. M., “SCALE Free-Form Reading Routines,” ORNL/NUREG/CDS-2/Vol. 3, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Bucholz, J. A., J. R. Knight, C. V. Parks, L. M. Petrie, J. C. Turner, and R. M. Westfall, “Standard Composition Library,” ORNL/NUREG/CSD-2/Vol. 3, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

Petrie, L. M., “FIDO Input System,” ORNL/NUREG/CSD-2/Vol. 3 (1984). M. B. Emmett, L. M. Petrie, and J. T. West, “JUNEBUG-II: A Three-Dimensional Geometry Plotting Code,” ORNL/NUREG/CSD-2/Vol. 2, prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn. (1984).

1983

Parks, C. V., O. W. Hermann, L. M. Petrie, T. J. Hoffman, J. S. Tang, N. F. Landers, and W. D. Turner, “Standardized Analyses of Nuclear Shipping Containers,” Seventh International Symposium on Packaging and Transportation of Radioactive Materials, CONF-830528-Summ. (1983).

1982

Ford, W. E., III, B. R. Diggs, L. M. Petrie, C. C. Webster, and R. M. Westfall, CSRL-V: Processed ENDF/B-V 227-Neutron-Group and Pointwise Cross-Section Libraries for Criticality Safety, Reactor and Shielding Studies, NUREG/CR-2306 (ORNL/CSD/TM-160), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., June 1982.

1981

Eakes, R. G., K. W. Gwinn, G. H. Lamoreaux, W. B. Leisher, J. M. Ortman, L. M. Petrie, R. B. Pope, L. B. Shappert, R. W. Rhode, L. E. Romesberg, A. A. Trujillo, and C. D. Watson, “Conceptual Design of the Clinch River Breeder Reactor Spent Fuel Shipping Cask,” TCC-0251 (1981).

1979

West, J. T., L. M. Petrie and S. K. Fraley, KENO-IV/CG, the Combinatorial Geometry Version of the KENO Monte Carlo Criticality Safety Program, NUREG/CR-0709 (ORNL/NUREG/CSD-7), prepared for the U.S. Nuclear Regulatory Commission by Oak Ridge National Laboratory, Oak Ridge, Tenn., September 1979.

Lorek, M. J., H. L. Dodds, L. M. Petrie, and R. M. Westfall, “Improved Criticality Search Techniques for Low and High Enriched Systems,” Trans. Am. Nucl. Soc., 33, 372 (1979).

1978

Hoffman, T. J., and L. M. Petrie, “Calculation of the Reactivity Due to Bubble Collapse with the Probability Table Method,” Nucl. Sci. Eng . , 66, 67 (1978).

Hoffman, T. J., L. M. Petrie, and N. F. Landers, “ Monte Carlo Perturbation Source Method for Reactivity Calculations,” Nucl. Sci. Eng., 66, 60 (1978).

Westfall, R. W., and L. M. Petrie, “Standardized Safety Analysis of Nuclear Fuel Shipping Containers,” Fifth Symposium on Packaging and Transportation of Radioactive Materials, CONF-780506-23 (1978).

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

West, J. T., and L. M. Petrie, “Shipping Cask Criticality Analysis Utilizing Combinatorial Geometry with KENO-IV,” Fifth Symposium on Packaging and Transportation of Radioactive Materials, CONF-780506-37 (1978).

Croff, A. G., M. A. Bjerke, G. W. Morrison, and L. M. Petrie, Revised Uranium-Plutonium Cycle PWR and BWR Models for the ORIGEN Computer Code, ORNL/TM-6051 (1978).

Hoffman, T. J., L. M. Petrie, S. N. Cramer, D. E. Bartine, and S. K. Fraley, “Monte Carlo Calculations of Radiation Transport in Upper Atmosphere,” Trans. Am. Nucl. Soc., 30, 595 (1978).

1977

Hoffman, T. J., and L. M. Petrie, “Bubble Worth Calculations with the Probability Table Method,” Trans. Am. Nucl. Soc., 26, 549 (1977).

Hoffman, T. J., and L. M. Petrie, “Calculation of Reactivity Changes Due to Bubble Collapse,” Trans. Am. Nucl. Soc., 26, 85 (1977).

Vondy, D. R., T. B. Fowler, G. W. Cunningham, and L. M. Petrie, Computation System for Nuclear Reactor Core Analysis, ORNL-5158, Union Carbide Corporation (Nuclear Division), Oak Ridge National Laboratory, 1977.

1976

Greene, N. M., J. L. Lucius, L. M. Petrie, W. E. Ford, III, J. E. White, and R. Q. Wright, AMPX: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B, ORNL-TM-3706, Union Carbide Corporation (Nuclear Division), Oak Ridge National Laboratory, 1976.

1975

Petrie, L. M., and N. F. Cross, KENO-IV: An Improved Monte Carlo Criticality Program, ORNL-4938, Union Carbide Corporation (Nuclear Division), Oak Ridge National Laboratory, November 1975.

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

1974

Petrie, L. M., and N. F. Cross, “Energy- and Region-Dependent Bucklings for the FFTF Engineering Mockup Core from Monte Carlo,” Trans. Am. Nucl. Soc., 18, 348 (1974).

Rhoades, W. A., M. B. Emmett, G. W. Morrison, J. V. Pace, III, and L. M. Petrie, Vehicle Code System (VCS) User’s Manual, ORNL-TM-4648 (1974).

1973

Petrie, L. M., and P. G. McCarty, “Validation of Monte Carlo Calculations of Shipping Cask Systems,” Trans. Am. Nucl. Soc., 17, 527 (1973).

Morrison, G. W., L. M. Petrie, and F. R. Mynatt, “ Monte Carlo Analysis of Neutron and Gamma-Ray Transport in Concrete,” Trans. Am. Nucl. Soc., 17, 524 (1973).

1972

Hoffman, T. J., and L. M. Petrie, “Monte Carlo Reactivity Calculations Using a Perturbation Source,” Trans. Am. Nucl. Soc., 15, No. 2, 912 (1972).

1971

Thompson, C. L., J. R. Stockton, L. M. Petrie, R. Q. Wright, and S. K. Penny, EDITOR: A Processing Code for ENDF/B Format Data, ORNL-TM-3266 (1971).

Morrison, G. W., L. M. Petrie, and R. S. Carlsmith, “Use of Thermal-Neutron Scattering Law in Monte Carlo Calculations,” Trans. Am. Nucl. Soc., 14, No. 2, 827 (1971).

Petrie, L. M., and G. W. Morrison, “Calculation of Several 238U Thermal Systems by Monte Carlo Using ENDF/B Material 103,” Trans. Am. Nucl. Soc., 14, No. 2, 827 (1971).