Reactor and Nuclear Systems Division

Luiz Leal

Luiz Leal

Distinguished Scientist
Nuclear Data and Criticality Safety
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: 865.574.5281
Fax: 865.574.3527
leallc@ornl.gov

Curriculum Vitae

Research Interests

  • nuclear data evaluations
  • nuclear data processing and applications
  • nuclear criticality safety
  • reactor physics methods development
  • nuclear data sensitivity and uncertainty analyses
  • methods and code development for data applications
  • fusion and radiation shielding

Education

  • Ph.D., Nuclear Engineering, University of Tennessee, Knoxville, TN, May 1990
  • M.S., Nuclear Engineering, Federal University of Rio de Janeiro, Brazil, June 1980
  • B.Sc., Physics, Federal University of Rio de Janeiro, Brazil, December 1977

Publications

L. C. Leal, R. E. Macfarlane, A. Plompen, A. Negret, and C. Borcea, "56Fe Resonance Evaluation up to 1.5 MeV," WINS 2012, Boston, MA, September 17-19, 2012.

L. C. Leal, K. H. Guber, D. Wiarda, G. Arbanas, and M. E. Dunn, "ORNL Resonance Evaluation for ENDF/B-VII.1," Trans. Am. Nucl. Soc. 106, 784-785 (2012).

G. Arbanas, M. E. Dunn, N. M. Larson, L. C. Leal, M. L. Williams, B. Becker, and R. Dagan, "Convergence of Legendre Expansion of Doppler-Broadened Double-Differential Elastic Scattering Cross Section," PHYSOR 2012 - Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2012).

A. Santamarina, D. Bernard, N. Dos Santos, O. Leray, C. Vaglio and L. Leal, "Re-estimation of Nuclear Data and JEFF3.1.1 Uncertainty Calculations," PHYSOR 2012 - Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, Tenn., April 15-20, 2012, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2012).

M. B. Chadwick et al., "ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data," Nucl. Data Sheets 112(12), 2887-2996 (2011).

A. Trkov, R. Capote, E. Soukhovitskii, L. C. Leal, M. Sin, I. Kodeli, and D. W. Muir, "Covariances of Evaluated Nuclear Cross Section Data for 232Th, 180,182,183,184,186W and 55Mn," Nuclear Data Sheets 112(12), 3098-3119, December 2011.

E. A. Read, L. C. Leal, K. C. Bledsoe, B. L. Kirk, and C. R. E. de Oliveira, "Nuclear Data Error Propagation in Fusion Benchmark Calculations," Trans. Am. Nucl. Soc. 105, 464-465 (2011).

V. Sobes, R. Macdonald, L. Leal, B. Forget, K. Guber, and G. Kohse, "Thermal Total Cross Section Measurement for 63Cu and 65Cu at the MIT Reactor," Trans. Am. Nucl. Soc. 105, 557-558 (2011).

M. E. Dunn, L. C. Leal, K. H. Guber, G. Arbanas, D. Wiarda, R. O. Sayer, H. Derrien, and J. Harvey, "Resonance Region Cross-Section Data Advancements for Nuclear Criticality Safety Applications," in Proceedings of ICNC 2011, Edinburgh, U.K., September 19-22, 2011.

K. H. Guber, L. C. Leal, C. Lampoudis, S. Kopecky, P. Schillebeeckx, F. Emiliani, R. Wynants, and P. Siegler, "New Improved Nuclear Data for Nuclear Criticality and Safety," in Proceedings of ICNC 2011, Edinburgh, U.K., September 19-22, 2011.

L. C. Leal, K. H. Guber, G. Arbanas, D. Wiarda, P. E. Koehler, and A. Kahler, "Resonance Evaluation of 48Ti Including Covariance for Criticality Safety Applications," in Proceedings of ICNC 2011, Edinburgh, U.K., September 19-22, 2011.

G. Arbanas, B. Becker, R. Dagan, M. E. Dunn, N. M. Larson, L. C. Leal, and M. L. Williams, "Covariance Matrix of a Double-Differential Elastic Scattering Cross Section," presented at the 2nd Workshop on Neutron Cross Section Covariances, Vienna, Austria, September 14-16, 2011.

L. C. Leal, H. Derrien, K. H. Guber, G. Arbanas, and D. Wiarda, "Evaluation of the Chromium Resonance Parameters Including Resonance Parameter Covariance," Korean Phys. Soc. 59(2), 1644-1648, August 2011.

P. Pereslavtsev, A. Konobeyev, U. Fischer, and L. C. Leal, "Evaluation of 50Cr, 52Cr, 53Cr, 54Cr Neutron Cross Section Data for Energies up to 200 MeV," Korean Phys. Soc. 59(2), 931-934, August 2011.

J. C. Holmes, I. I. Al-Qasir, A. I. Hawari, and L. C. Leal, "Development of an ENDF Thermal Library for SiO2 and Testing of Criticality Effects," Trans. Am. Nucl. Soc. 104, 438-439 (2011).

V. Sobes, L. Leal, H. Derrien, D. Wiarda, D. Mueller, and B. Forget, "Processing and Testing New 240Pu Resolved Resonance and Covariance Evaluation," Trans. Am. Nucl. Soc. 104, 780-782 (2011).

D. Wiarda, L. C. Leal, and M. E. Dunn, "Cross-Section Covariance Data Processing with the AMPX Module PUFF-IV" (invited), Trans. Am. Nucl. Soc. 104, 772-773 (2011).

G. Arbanas, M. E. Dunn, N. M. Larson, L. C. Leal, M. L. Williams, B. Becker, and R. Dagan, "Computation of Temperature-Dependent Legendre Moments of a Double-Differential Elastic Cross Section," in Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12, 2011.

L. Leal and K. Shibata, Assessment of the Unresolved Resonance Treatment for Cross-section and Covariance Representation, Nuclear Science/NEA/WPEC-32, NEA/NSC/WPEC/DOC(2011)430, a report by the working Party of International Evaluation Co-operation of the NEA Nuclear Science Committee, Nuclear Energy Agency, Organisation for Economic Co-operation and Development, April 2011.

L. C. Leal, C. De Saint Jean, and G. Noguere, "Comparison of Resonance Parameter Covariance Generation Using CONRAD and SAMMY Computer Codes," Trans. Am. Nucl. Soc. 102, 506-508 (2010).

K. H. Guber, H. Derrien, L. C. Leal, G. Arbanas, D. Wiarda, P. Koehler, and J. A. Harvey, "Astrophysical Reaction Rates for 58,60Ni(n,?) from New Neutron Capture Cross Section Measurements," Phys. Rev. C 82, 057601 (2010).

B. Habert, C. De Saint Jean, L. C. Leal, and Y. Rugama, "Retroactive Generation of Covariance Matrix of Nuclear Model Parameters Using Marginalization Techniques," Nucl. Sci. Eng. 166(3), 276-287, November 2010.

L. C. Leal, H. Derrien, C. De Saint Jean, G. Noguere, and J. M. Ruggieri, "Covariance Generation using CONRAD and SAMMY Computer Codes," in Proceedings of Wonder 2009-2nd International Workshop on Nuclear Data Evaluation for Reactor Applications, Cadarache, France, September 29-October 2, 2009.

H. Derrien, L. C. Leal, K. H. Guber, D. Wiarda, and G. Arbanas, "Reevaluation of 58Ni and 60Ni Resonance Parameters in the Energy Range Thermal to 800 keV" in Proceedings of Wonder 2009-2nd International Workshop on Nuclear Data Evaluation for Reactor Applications, Cadarache, France, September 29-October 2, 2009.

H. Derrien, L. C. Leal, and N. M. Larson, "R-Matrix Analysis of 238U High Resolution Neutron Transmissions and Capture Cross Sections in the Energy Range 0 keV to 20 keV," Nucl. Sci. Eng. 161(2), 131-159, February 2009.

L. C. Leal, G. Arbanas, H. Derrien, and D. Wiarda, "Resonance Region Covariance Analysis Method and New Covariance Data for Th-232, U-233, U-235, U-238, and Pu-239, Nuclear Data Sheets 109(12), 2868-2873, December 2008.

A. Trkov, R. Capote, I. Kodeli, and L. C. Leal, "Evaluation of Tungsten Nuclear Reaction Data with Covariances," Nuclear Data Sheets 109(12), 2905-2909, December 2008.

D. Wiarda, G. Arbanas, L. C. Leal, and M. E. Dunn, "Recent Advances with the AMPX Covariance Processing Capabilities in PUFF-IV," Nuclear Data Sheets 109(12), 2791-2795, December 2008.

H. Derrien, L. C. Leal, and N. M. Larson, "R-Matrix Analysis of 232Th Neutron Transmissions and Capture Cross Sections in the Energy Range Thermal to 4 keV," Nucl. Sci. Eng. 160(2), 149-167, October 2008.

H. Derrien, L. C. Leal, N. M. Larson, K. H. Guber, D. Wiarda, and G. Arbanas, "Neutron Resonance Parameters of 55Mn from Reich-Moore Analysis of Recent Experimental Neutron Transmission and Capture Cross Sections," in Proceedings of PHYSOR 2008 - International Conference on the Physics of Reactor, Interlaken, Switzerland, September 14-19, 2008.

L. C. Leal, D. Mueller, G. Arbanas, D. Wiarda, H. Derrien, "Impact of the 235U Covariance Data in Benchmark Calculations," in Proceedings of PHYSOR 2008 - International Conference on the Physics of Reactor, Interlaken, Switzerland, September 14-19, 2008.

H. Derrien, L. C. Leal, and N. M. Larson, Neutron Resonance Parameters and Covariance Matrix of 239Pu, ORNL/TM-2008/123, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2008.

K. H. Guber, D. Wiarda, L. C. Leal, H. Derrien, C. Ausmus, D. Brashear, and J. A. White, "New Neutron-Induced Cross-Section Measurements for Weak s-process Studies," NIC X_214.pdf in Proceedings of Science, 10th Symposium on Nuclei in the Cosmos, Mackinac Island, Michigan, July 27-August 1, 2008.

L. C. Leal and C.-S. Gil, "Comparison of the Uncertainties of keff Using the Recently Developed Covariance Data," Trans. Am. Nucl. Soc. 98, 207-208 (2008).

L. C. Leal, D. Wiarda, and G. Arbanas, "Covariance Representation in the Resonance Region: Application to 233U," Trans. Am. Nucl. Soc. 98, 651-653 (2008).

L. C. Leal, D. Wiarda, B. T. Rearden, and H. Derrien, 233U Cross-Section and Covariance Data Update for SCALE 5.1 Libraries, ORNL/TM-2007/115, Oak Ridge National Laboratory, Oak Ridge, Tenn., January 2008.

M. E. Dunn, G. Arbanas, L. C. Leal, and D. Wiarda, "Approximating large resonance parameter covariance matrices with group-wise covariance matrices for advanced nuclear fuel cycle applications," p. 139-142, NEMEA-4óNeutron Measurements, Evaluations and Applications, Nuclear Data Needs for Generation IV and Accelerator Driven Systems, in Proceedings of the CANDIDE Workshop, October 16-18, 2007, Prague, Czech Republic (January 2008).

L. C. Leal, H. Derrien, M. E. Dunn, and D. Mueller, Assessment of Fission Product Cross-Section Data for Burnup Credit Applications, ORNL/TM-2005/065, Oak Ridge National Laboratory, Oak Ridge, Tenn., December 2007.

C. Myers, B. L. Kirk, and L. C. Leal, "Comparative Analysis of Nuclear Cross Sections in Monte Carlo Methods for Medical Physics Applications," in Proceedings of the Computational Medical Physics Working Group Workshop II, Gainesville, FL, September 30-October 3, 2007.

L. Leal, R. Westfall, D. Eghbali, and F. Trumble, "Assessment of Titanium Cross Sections and Uncertainties for Application in Criticality Safety," p. 50-52 in Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. II, St. Petersburg, Russia, May 28-June 1, 2007.

L. Leal, H. Derrien, N. Larson, G. Arbanas, and R. Sayer, "ORNL Methodology for Covariance Generation for Sensitivity/Uncertainty Analysis," p. 25-29 in Proceedings of the 8th International Conference on Nuclear Criticality Safety (ICNC 2007), Vol. II, St. Petersburg, Russia, May 28-June 1, 2007.

R. Capote, A. Trkov, I. Kodeli, E. Soukhovitskii, L. C. Leal, M. Herman, and D. Muir, "Evaluation of Cross Sections of Tungsten Isotopes Including Covariance Estimation," in Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Nice, France, April 22-27, 2007.

H. Derrien, L. C. Leal, and N. M. Larson, "239Pu Neutron Resonance Parameters Revisited and the Covariance Matrix in the Neutron Energy Range Thermal to 2.5 keV," in Proceedings of International Conference on Nuclear Data for Science and Technology (ND-2007), Nice, France, April 22-27, 2007.

M. E. Dunn, N. M. Larson, H. Derrien, and L. C. Leal, "Perspective on Advances in Resonance-Region Nuclear Modeling and Opportunities for Future Research," invited paper in Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Nice, France, April 22-27, 2007.

K. H. Guber, P. Koehler, D. Wiarda, J. A. Harvey, T. E. Valentine, R. O. Sayer, L. C. Leal, N. M. Larson, and T. S. Bigelow, "New Neutron Cross-Section Measurements from ORELA and New Resonance Parameter Evaluations," in Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Nice, France, April 22-27, 2007.

N. M. Larson, L. C. Leal, R. O. Sayer, H. Derrien, D. Wiarda, and G. Arbanas, "Current Status of the R-Matrix Code SAMMY, with Emphasis on the Relationship to ENDF Formats," in Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Nice, France, April 22-27, 2007.

L. C. Mihailescu, I. Sirakov, R. Capote, A. Borella, K. H. Guber, S. Kopecky, L. C. Leal, P. Schillebeeckx, P. Siegler, R. Wynants, and E. Soukhovitskii, "Evaluation of the 103Rh Neutron Cross Section Data in the Unresolved Resonance Region for Improved Criticality Safety," in Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Nice, France, April 22-27, 2007.

L. Leal and H. Derrien, "Evaluation of 231Pa and 233Pa Resonance Parameters and Covariance in the Resolved Resonance Region," Trans. Am. Nucl. Soc. 95, 768-769 (2006).

D. Wiarda, M. E. Dunn, N. M. Larson, and L. C. Leal, "Processing of ENDF/B-VII Covariance Data for Use of Sensitivity/Uncertainty Analysis," Trans. Am. Nucl. Soc. 95, 290-291 (2006).

H. Derrien, L. C. Leal, and N. M. Larson, Evaluation of 232Th Neutron Resonance Parameters in the Energy Range 0 keV to 4000 keV, ORNL/TM-2006/53, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2006.

L. Leal, H. Derrien, G. Arbanas, N. Larson, and D. Wiarda, "Covariance Data for 232Th in the Resolved Resonance Region 0 to 4 keV," in Proceedings of PHYSOR 2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, Vancouver, British Columbia, Canada, September 10-14, 2006.

G. Arbanas, L. C. Leal, N. M. Larson, and H. Derrien, "Retroactive Covariance Matrix for 235U in the Resolved-Resonance Region," in Proceedings of PHYSOR 2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, Vancouver, British Columbia, Canada, September 10-14, 2006.

H. Derrien, L. C. Leal, and N. M. Larson, "New Evaluation of the 232Th Neutron Resonance Parameters in the Energy Range 0 to 4000 keV," in Proceedings of PHYSOR 2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, Vancouver, British Columbia, Canada, September 10-14, 2006.

D. Wiarda, M. E. Dunn, N. M. Greene, N. M. Larson, and L. C. Leal, "New Capabilities for Processing Covariance Data in Resonance Region," in Proceedings of PHYSOR 2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, Vancouver, British Columbia, Canada, September 10-14, 2006.

K. H. Guber, L. C. Leal, R. O. Sayer, P. E. Koehler, D. Wiarda, T. E. Valentine, H. Derrien, J. A. Harvey, S. Kopecky, P. Siegler, P. Schillebeeckx, R. Wynants, I. Ivanov, A. Borella, R. Nelson, M. Devlin, and N. Fotiadis, "New Neutron Cross-Section Measurements on 19F, 39,41K, 55Mn, and 103Rh for Improved Nuclear Criticality Safety," C033.pdf in Proceedings of PHYSOR 2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, Vancouver, British Columbia, Canada, September 10-14, 2006.

M. Herman, P. Oblozinsky, D. Rochman, T. Kawano, and L. Leal, "Fast Neutron Covariances for Evaluated Data Files," in Proceedings of PHYSOR 2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation, Vancouver, British Columbia, Canada, September 10-14, 2006.

N. M. Larson, L. C. Leal, H. Derrien, G. Arbanas, R. O. Sayer, and D. Wiarda, "A Systematic Description of the Generation of Covariance Matrices," in Proceedings of PHYSOR 2006, American Nuclear Society Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation,Vancouver, British Columbia, Canada, September 10-14, 2006.

R. O. Sayer, K. H. Guber, L. C. Leal, N. M. Larson, and T. Rauscher "R-Matrix Analysis of C1 Neutron Cross Sections up to 1.2 MeV," Phys. Rev. C 73, 044603 (2006).

K. H. Guber, L. C. Leal, R. O. Sayer, P. E. Koehler, H. Derrien, D. Wiarda, and J. A. Harvey, "Neutron Cross-Section Measurements at ORELA," pp. 25-34 in Proceedings of the Oak Ridge Electron Linear Accelerator (ORELA) Workshop, held at Oak Ridge National Laboratory, Oak Ridge, Tennessee, July 14-15, 2005; ORNL/TM-2005/272, comp. Michael E. Dunn, Oak Ridge National Laboratory, Oak Ridge, Tenn., February 2006.

L. C. Leal, G. Arbanas, H. Derrien, N. M. Larson, and B. Rearden, "Covariance Data for 233U in the Resolved Resonance Region for Criticality Safety Applications," 262.pdf in Proceedings of M&C 2005 International Topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications, Palais Des Papes, Avignon, France, September 12-15, 2005, on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2005).

A. Courcelle, H. Derrien, L. Leal, and N. Larson, "Analysis of the 238U Resonance Parameters Using Random-Matrix Theory," 167.pdf in Proceedings of M&C 2005 International Topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications, Palais Des Papes, Avignon, France, September 12-15, 2005, on CD-ROM, American Nuclear Society, LaGrange Park, Illinois (2005).

L. C. Leal, H. Derrien, N. M. Larson , and A. Courcelle, "An Unresolved Resonance Evaluation for 233U from 600 eV to 40 keV," Trans. Am. Nucl. Soc. 92, 665-666 (June 2005).

G. Arbanas, L. C. Leal, and N. M. Larson, "Impact of Missing Resonances in Determining Group Cross Sections and Uncertainties," Trans. Am. Nucl. Soc. 92, 672-673 (June 2005).

C. S. Melhus, M. S. Rivard, B. L. Kirk, and L. C. Leal, "Clinical Brachytherapy Dosimetry Parameters and Mixed-Field Dosimetry for a High Rate Cf-252 Brachytherapy Source," in Proceedings of The Monte Carlo 2005 Topical Meeting, The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, Tennessee, April 17-21, 2005; on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2005).

C. S. Melhus, M. S. Rivard, B. L. Kirk, and L. C. Leal, "Storage Safe Shielding Assessment for a HDR Californium-252 Brachytherapy Source," usr-cmelhus-1-paper.pdf in Proceedings of The Monte Carlo 2005 Topical Meeting, The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World, Chattanooga, Tennessee, April 17-21, 2005; on CD-ROM, American Nuclear Society, LaGrange Park, Ill. (2005).

L. C. Leal and H. Derrien, "Statistical Properties of the s- and p-Wave Resonances for 238U," Trans. Am. Nucl. Soc. 91, 566-567 (November 2004).

K. H. Guber, L. C. Leal, R. O. Sayer, P. E. Koehler, T. E. Valentine, H. Derrien, and J. A. Harvey, "New Neutron Cross-Section Measurements at ORELA and Their Application in Nuclear Criticality Calculations," presented at the 18th International Conference on the Application of Accelerators in Research and Industry (CAARI), October 10-15, 2004, Ft. Worth, Texas.

R. O. Sayer, K. H. Guber, L. C. Leal, and N. M. Larson, "New Resonance Parameter Evaluation of C1 Neutron Cross Sections" pp. 386-389, Vol. 769 in Proceedings of the International Conference on Nuclear Data for Science and Technology, Santa Fe, New Mexico, September 26-October 1, 2004.

K. Volev, N. Koyumdjieva, A. Brusegan, A. Borella, P. Siegler, N. Janeva, A. Lukyanov, L. Leal, and P. Schillebeechx, "Evaluation of the 232Th Neutron Cross Sections between 4 keV and 140 keV," pp. 87-90, Vol. 769 in Proceedings of the International Conference on Nuclear Data for Science and Technology, Santa Fe, New Mexico, September 26-October 1, 2004.

L. C. Leal, H. Derrien, K. H. Guber, R. O. Sayer, and N. M. Larson, "Recent Cross-Section Evaluations in the Resonance Region at the Oak Ridge National Laboratory," pp. 332-337, Vol. 769, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Santa Fe, New Mexico, September 26-October 1, 2004.

L. C. Leal, N. M. Larson, H. Derrien, T. Kawano, and M. B. Chadwick, "A New Approach for Nuclear Data Covariance and Sensitivity Generation," pp. 338-341, Vol. 769, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Santa Fe, New Mexico, September 26-October 1, 2004.

K. H. Guber, L. C. Leal, R. O. Sayer, P. E. Koehler, T. E. Valentine, H. Derrien, and J. A. Harvey, "New Neutron Cross-Section Measurements at ORELA for Improved Nuclear Data Calculations," pp. 1706-1711, Vol. 769, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Santa Fe, New Mexico, September 26-October 1, 2004.

H. Derrien, A. Courcelle, L. C. Leal, N. M. Larson, and A. Santamarina, "Evaluation of 238U Resonance Parameters from 0 to 20 keV," pp. 276-281, Vol. 769, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Santa Fe, New Mexico, September 26-October 1, 2004.

H. Derrien, J. A. Harvey, K. H. Guber, L. C. Leal, and N. M. Larson, Average Neutron Total Cross Sections in the Unresolved Energy Range from ORELA High Resolution Transmission Measurements, ORNL/TM-2003/291, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2004.

K. H. Guber, L. C. Leal, R. O. Sayer, P. E. Koehler, T. E. Valentine, H. Derrien and J. A. Harvey, "Neutron Cross-Sections Measurements at ORELA for Improved Nuclear Data and their Application," in Proceedings of ICRS-10 RPS 2004: 21st Century Challenges in Radiation Protection and Shielding, Funchal, Madeira Island, Portugal, May 9-14, 2004.

R. O. Sayer, K. H. Guber, L. C. Leal, N. M. Larson, and T. Rauscher, "R-Matrix Evaluation of Cl Neutron Cross Sections up to 1.2 MeV," in Proceedings of ICRS-10 RPS 2004: 21st Century Challenges in Radiation Protection and Shielding, Funchal, Madeira Island, Portugal, May 9-14, 2004.

L. C. Leal, H. Derrien, N. M. Larson, and F. A. Alpan, "Covariance and Sensitivity Data Generation at ORNL," in Proceedings of ICRS-10 RPS 2004: 21st Century Challenges in Radiation Protection and Shielding, Funchal, Madeira Island, Portugal, May 9-14, 2004.

F. A. Alpan, L. C. Leal, and A. Courcelle, "Effect of Energy Self-Shielding Methods on 238U for Criticality Safety Problems," 95398.pdf in Proceedings of PHYSOR 2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, Ill., April 25-29, 2004, on CD-ROM, American Nuclear Society, La Grange Park, Ill. (2004).

L. C. Leal, H. Derrien, and N. M. Larson, "An Unresolved Resonance Evaluation for 235U," in Proceedings of PHYSOR 2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, Ill., April 25-29, 2004, on CD-ROM, American Nuclear Society, La Grange Park, Ill. (2004).

K. H. Guber, L. C. Leal, R. O. Sayer, P. E. Koehler, T. E. Valentine, H. Derrien, and J. A. Harvey, "New Neutron Cross Section Measurements at ORELA for Improved Nuclear Data," in Proceedings of PHYSOR 2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, Ill., April 25-29, 2004, on CD-ROM, American Nuclear Society, La Grange Park, Ill. (2004).

H. Derrien, L. C. Leal, and N. M. Larson, "Status of a New Evaluation of the Neutron Resonance Parameters of 238U at ORNL," 94991.pdf in Proceedings of PHYSOR 2004 - The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments, Chicago, Ill., April 25-29, 2004, on CD-ROM, American Nuclear Society, La Grange Park, Ill. (2004).

M. J. Rivard, K. E. Evans, L. C. Leal, and B. L. Kirk, "Selective Perturbation of in Vitro Linear Energy Transfer Using High-Z Vaginal Applicators for Cf-252 Brachytherapy," Nuclear Instruments and Methods in Physics Research Section B: Beam Interaction with Materials and Atoms 213, 621-625, January 2004.

K. H. Guber, P. E. Koehler, H. Derrien, T. E. Valentine, L. C. Leal, R. O. Syer, and T. Rauscher, "Neutron Capture Reaction Rates for Silicon and Their Impact on the Origin of Presolar Mainstream SiC Grains," Phys. Rev. C. 57(6), 062802, June 2003.

L. C. Leal and H. Derrien, "R-Matrix Evaluation of 19F Neutron Cross Sections up to 1 MeV," American Nuclear Society, San Diego, California, June 2003.

"ORNL Tools for Cross Section Measurements and Evaluation," presented at the Workshop on Nuclear Data Needs for Generation IV Nuclear Energy Systems Brookhaven National Laboratory, Upton, New York, April 24-25, 2003.

K. H. Guber, P. E. Koehler, H. Derrien, T. E. Valentine, L. C. Leal, R. O. Sayer, and T. Rauscher, "Maxwellian Average Neutron Capture Cross Sections for Silicon and their Impact on the Origin of Presolar Mainstream SiC Grains," Phys. Rev. C.

K. H. Guber, L. C. Leal, R. O. Sayer, P. E. Koehler, T. E. Valentine, H. Derrien, and J. A. Harvey, "Neutron Cross Sections Measurements at ORELA for Improved Nuclear Data and Their Applications," in Proceedings of International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002, Seoul, South Korea, October 7-10, 2002.

S.-Y. Oh, J. Chang, and L. Leal, "Statistical Assignment of Neutron Orbital Angular Momentum to a Resonance," in Proceedings of International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002, Seoul, South Korea, October 7-10, 2002.

M. E. Dunn and L. C. Leal, "Calculating Probability Tables for the Unresolved-Resonance Region Using Monte Carlo Methods," in Proceedings of International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002, Seoul, South Korea, October 7-10, 2002.

L. C. Leal, H. Derrien, K. H. Guber, J. A. Harvey, and N. M. Larson, "Evaluation of the 233U Neutron Cross Sections in the Resolved Resonance," in Proceedings of Energy Range, International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002, Seoul, South Korea, October 7-10, 2002.

H. Derrien, L. C. Leal, K. H. Guber, T. Valentine, N. M. Larson, and T. Rauscher, Evaluation of Silicon Neutron Resonance Parameters in the Energy Range Thermal to 1800 keV, ORNL/TM-2001/271, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2002.

K. H. Guber, R. O. Sayer, T. E. Valentine, L. C. Leal, R. R. Spencer, P. E. Koehler, J. A. Harvey, and T. Rauscher, "New Maxwellian Average Neutron Capture Cross Sections for 35,37Cl," Phys. Rev. C 65, April 2002.

L. C. Leal, K. H. Guber, R. R. Spencer, H. Derrien, and R. Q. Wright, "Aluminum Data Measurements and Evaluation for Criticality Safety Applications," SNS Workshop, Oak Ridge, TN, March 2002.

M. J. Rivard, K. E. Evans, L. C. Leal, B. L. Kirk, "Selective Perturbation of in vivo Linear Energy Transfer Using High-Z Vaginal Applicators for Cf-252 Brachytherapy," in Proceedings 5th Industrial Radiation and Radioisotope Measurement Applications (IRRMA-V), Bologna, Italy, June 9-14, 2002, Beam Interactions with Materials and Atoms Section B of Nuclear Instruments & Methods in Physics Research.

H. Derrien, K. Guber, J. Harvey, N. Larson, and L. Leal, "Average Cross Section of 233U, 235U, and 239Pu from ORELA Transmission Measurements and Statistical Model Analysis of the Data," Nuclear Science and Technology, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Tsukuba, Ibaraki, Japan, October 7-12, 2001.

R. Sayer, L. Leal, N. Larson, R. Spencer, and R. Q. Wright, "R-Matrix Evaluation of 16O Cross Sections up to 6.3 MeV," Nuclear Science and Technology, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Tsukuba, Ibaraki, Japan, October 7-12, 2001.

K. Guber, L. Leal, R. Sayer, R. Spencer, P. Koehler, T. Valentine, H. Derrien, and J. Harvey, "Neutron Cross Sections Measurements for Light Elements at ORELA and their Application in Nuclear Criticality," Nuclear Science and Technology, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Tsukuba, Ibaraki, Japan, October 7-12, 2001.

K. Guber, P. Koehler, T. Valentine, and L. Leal, "Neutron Cross Section Measurements at the Spallation Neutron Source," Nuclear Science and Technology, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Tsukuba, Ibaraki, Japan, October 7-12, 2001.

C. Y. Fu, F. B. Guimaraes, and L. Leal, "Combining Semi-Classical and Quantum Mechanical Methodologies for Nuclear Cross-Sections Calculations between 1 MeV and 5 GeV," Nuclear Science and Technology, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Tsukuba, Ibaraki, Japan, October 7-12, 2001.

L. Leal, H. Derrien, N. Larson, K. Guber, T. Valentine, and R. Sayer, "Nuclear Data Measurements, Analysis and Evaluation at the Oak Ridge National Laboratory in Support of Nuclear Criticality Safety," Nuclear Science and Technology, in Proceedings of the International Conference on Nuclear Data for Science and Technology, Tsukuba, Ibaraki, Japan, October 7-12, 2001.

L. C. Leal, "Data Analysis and Evaluation with SAMMY," in Proceedings of the Workshop "Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety," Vol. I and II, ICTP, Trieste, Italy, eds. N. Paver, M. Herman, A. Gandini (2001). Vol. I: Theory and Practice in Nuclear Data Evaluation.

C. Y. Fu, F. B. Guimaraes, and L. Leal, Combining Semi-Classical and Quantum Mechanical Methodologies for Nuclear Cross-Sections Calculations between 1 MeV and 5 GeV, ORNL/TM-2001/191 (ENDF-366), Oak Ridge National Laboratory, Oak Ridge, Tenn. (2001).

H. Derrien, J. A. Harvey, N. M. Larson, L. C. Leal, and R. Q. Wright, Neutron Total Cross Sections of 235U from Transmission Measurements in the Energy Range 2 kev to 300 kev and Statistical Model Analysis of the Data, ORNL/TM-2000/129, Oak Ridge National Laboratory, Oak Ridge, Tenn. (2000).

K. H. Guber, L. C. Leal, R. O. Sayer, R. R. Spencer, P. E. Koehler, T. A. Valentine, H. Derrien, J. Andrzejewski, Y. M. Gledenov, and J. A. Harvey, "Neutron Cross Sections Measurements for Light Elements at ORELA and Their Application in Nuclear Criticality and Astrophysics," World Scientific (2000).

R. O. Sayer, L. C. Leal, N. M. Larson, R. R. Spencer, and R. Q. Wright, R-Matrix Evaluation of 16O Neutron Cross Sections up to 6.3 MeV, ORNL/TM-2000/212, Oak Ridge National Laboratory, Oak Ridge, Tenn. (2000).

R. Q. Wright, L. C. Leal, H. Derrien, N. M. Larson, and W. C. Jordan, "Data Testing of the ORNL Aluminum Evaluation," ANS Annual Meeting (2000).

L. C. Leal, H. Derrien, and N. M. Larson, "Nuclear Data Evaluation for Reactor Applications," ANS Annual Meeting, Milwaukee, Wisconsin, June 2001.

L. C. Leal, O. W. Hermann, S. M. Bowman, and C. V. Parks, "Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries," Nucl. Technol. 127, 1, July 1999. Also as ORNL/TM 13584.

L. C. Leal, H. Derrien, N. M. Larson, and R. Q. Wright, "R-Matrix Analysis of 235U Neutron Transmission and Cross-Section Measurements in the 0- to 2.25-keV Energy Range," Nucl. Sci. Eng. 131, 230, February 1999. Also as ORNL/TM 13516.

L. C. Leal, N. M. Larson, D. C. Larson and D. M. Hetrick, "R-Matrix Evaluation of 28Si, 29Si, 30Si up to 1.8 MeV," in Proceedings of International Conference on Nuclear Data for Science and Technology, Part I, p. 929, Trieste, Italy, May 19-24, 1997.

L. C. Leal, H. Derrien, and N. M. Larson, "Statistical Properties of the S-wave Resonances of 235U," in Proceedings of International Conference on Nuclear Data for Science and Technology, Part I, p. 864, Trieste, Italy, May 19-24, 1997.

L. C. Leal, O. W. Hermann, J. C. Ryman, and B. L. Broadhead, "An Alternative to the SAS2H/ORIGEN-S Sequence to Account for Water-Density Effects in BWR Systems," American Nuclear Society/European Nuclear Society International Meeting, Washington, DC, November 10-14, 1997.

O. Bouland, H. Derrien, N. M. Larson, and L. C. Leal, "R-Matrix Analysis of the 240Pu Neutron Cross Sections in the Thermal to 5700 eV Energy Range," Nucl. Sci. Eng. 127, 105, October 1997.

H. Derrien, N. M. Larson, and L. C. Leal, Covariance Matrices for Use in Criticality Safety Predictability Studies, ORNL/TM-13492, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 1997.

D. M. Hetrick, D. C. Larson, N. M. Larson, L. C. Leal, and S. J. Epperson, Evaluation of 28,29,30Si Neutron Induced Cross Sections for ENDF/B-VI, ORNL/TM-11825, Oak Ridge National Laboratory, Oak Ridge, Tenn., April 1997.

L. C. Leal and R. Q. Wright, Assessment of the Available 233U Cross-Section Evaluation in the Calculation of Critical Benchmark Experiments, ORNL/TM-13313, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 1996.

L. C. Leal, R. R. Spencer, D. T. Ingersoll and T. A. Gabriel, "Assessment of the Neutron Cross-Section Database for Mercury for the ORNL Spallation Source," in Proceedings of International Workshop on the Technology and Thermal Hydraulics of Heavy Liquid Metals, Schurns, Montafon Valley, Austria, March 25-28, 1996.

R. Q. Wright, L. C. Leal and J. M. Rammsy, "Data Testing of ORNL 235U Evaluation," American Nuclear Society Annual Meeting, Reno, Nevada, June 16-20, 1996.

L. C. Leal, R. Q. Wright and J. M. Rammsy, "Self-Shielded Reaction-Rate Calculations for 235U from 0 to 2250 eV," American Nuclear Society Annual Meeting, Reno, Nevada, June 16-20, 1996.

L. C. Leal and N. M Larson, SAMDIST: A Computer Code for Calculating Statistical Distributions for R-Matrix Resonance Parameters, ORNL/TM-13092, Oak Ridge National Laboratory, Oak Ridge, Tenn., September 1995.

J. M. Rammsy, L. C. Leal, and N. M. Greene, "Resonance Integral Generated Using the Multipole Approach," American Nuclear Society Winter Meeting, San Francisco, CA, November 1995.

L. C. Leal, N. M. Larson, and H. Derrien, "Re-evaluation of the 235U Cross Section for ENDF/B-VI," American Nuclear Society Winter Meeting, San Francisco, CA, November 1995.

O. Bouland, H. Derrien, N. M. Larson, and L. C. Leal, "Reich-Moore Evaluation of the 240Pu Resonance Parameters," American Nuclear Society Winter Meeting, San Francisco, CA, November 1995.

L. C. Leal, J. R. Deen, and W. L. Woodruff, "Validation of the WIMSD4M Cross-Section Generation Code with Benchmark Results," in Proceedings of International Conference on Mathematics and Computations, Reactor Physics, and Environment Analyses, Portland, Oregon, May 1995.

J. Vujic, E. Greenspan, S. Slater, T. Postma, L. Leal, G. Casher, and I. Soares, "Development of Coupled SCALE4.2/GTRAN2 Computational Capability for Advanced MOX Fueled Assembly Designs," in Proceedings of International Conference on Mathematics and Computations, Reactor Physics, and Environment Analyses, Portland, Oregon, May 1995.

L. C. Leal, O. W. Hermann, and C. V. Parks, "Automatic Rapid Processing Cross-Section Libraries for the Prediction of PWR Spent Fuel Isotopic Composition," in Proceedings of International Conference on Mathematics and Computations, Reactor Physics, and Environment Analyses, Portland, Oregon, May 1995.

L. C. Leal, "Revision and Reevaluation of the 235U Cross Sections for ENDF/B-VI to Address Integral Data Measurements," ENFIR/ENAN Joint Conferences, Aguas de Lindoia, Brazil, August 1995.

L. C. Leal, R. M. Westfall, W. C. Jordan, and R. Q. Wright, "Nuclear Data Needs for Application in Nuclear Criticality Safety Programs," in Proceedings of the Fifth International Conference on Nuclear Criticality Safety, Albuquerque, New Mexico, September 1995.

L. C. Leal, O. W. Hermann, and C. V. Parks, "ARP: A PC-Compatible Scheme for Generating ORIGEN-S Cross Section Library," in Proceedings of Sixth Annual International Conference, High Level Radioactive Waste Management, Las Vegas, Nevada, April 30-May 5, 1995.

L. C. Leal, O. W. Hermann, and C. V. Parks, "Automatic Rapid Processing SCALE/SAS2H Produced Parameter-Dependent Cross Sections for ORIGEN-S," American Nuclear Society, Annual Meeting, New Orleans June 1994.

L. C. Leal, R. N. Hill and H. S. Khalil, "An Evaluation of Neutron and Gamma Heating in Fission Product Isotopes," American Nuclear Society Annual Meeting, San Diego, CA, 1993.

L. C. Leal, T A. Daly, J. R. Liaw and E. K. Fujita, "Neutron Source From Spontaneous Fission and (_,n) Reactions in Mixture," American Nuclear Society Winter Meeting, San Francisco, CA, November 1991.

L. C. Leal, G. de Saussure and R. B. Perez, "An R-Matrix Analysis of the 235U Neutron Induced Cross Sections up to 500 eV," Nucl. Sci. Eng. 103, 1-17 (1991).

L. C. Leal, R. N. Hwang and C. G. Stenberg, "Computation of Multiple Parameters Using Preliminary ENDF/B-VI Data," American Nuclear Society Winter Meeting, Washington, DC, November 1990.

L. C. Leal, "Resonance Analysis and Evaluation of the 235U Neutron Induced Cross Sections," Ph.D. Thesis, presented to the Nuclear Engineering Department of The University of Tennessee, Knoxville, TN; also published as ORNL/TM-11547.

L. C. Leal, G. de Saussure and R. B. Perez, "Calculation of Resonance Self-shielding in 235U," American Nuclear Society Annual Meeting, Nashville, Tenn. (1990).

G. de Saussure, L. C. Leal, and R. B. Perez, Reich-Moore and Adler-Adler Representation of the 235U Cross Sections in the Resolved Resonance Region," in Proceedings of International Conference on Physics of Reactors: Operation, Design, and Computation, Marseille-France, April 23-26, 1990.

L. C. Leal, G. de Saussure, and R. B. Perez, URR Computer Code: A Code to Calculate Resonance Neutron Cross-Section Probability Tables, Bondarenko Self- Shielding Factors, and Self-Shielding Ratios for Fissile and Fertile Nuclide, ORNL/TM-11297/R1, Oak Ridge National Laboratory, Oak Ridge, Tenn.

L. C. Leal, G. de Saussure, R. B. Perez and R. Q. Wright, "Test of the ENDF/B Unresolved Resonance Formalism for 235U," American Nuclear Society Winter Meeting, San Francisco, CA, 1989.

L. C. Leal, G. de Saussure, R. R. Winters and R. B. Perez, "Statistical Properties of the 235U Resonance Parameters up to 300 eV," American Nuclear Society, Atlanta, GA, June 1989.

G. de Saussure, L. C. Leal, R. B. Perez, N. M. Larson and M. S. Moore, "A New Resonance-Region Evaluation of Neutron Cross Sections for 235U," Nucl. Sci. Eng. 103, 109-118 (1989).

M. S. Moore, L. C. Leal, G. de Saussure, R. B. Perez and N. M. Larson, "Resonance Structure in the Fission of (235U+n)," in Proceedings of the International Conference Fifty Years Research in Nuclear Fission, Berlin, Germany, April 1989.

L. C. Leal, G. de Saussure, R. B. Perez, "Analysis of the 235U Neutron Cross Sections in the Resolved Resonance Range," Fifty Years with Nuclear Fission 2, 939-945, April 1989.

R. B. Perez, G. de Saussure, L. C. Leal and Roger L. Macklin, "On the Unresolved Resonance Region Representation of Neutron Induced Cross Sections," in Proceedings of the International Reactor Physics Conference, Jackson Hole, WY, Sept 1988.

G. de Saussure, L. C. Leal, and R. B. Perez, "A New Resonance-Region Evaluation of Neutron Cross Sections for 235U," in Proceedings of the International Reactor Physics Conference, Jackson Hole, WY, Sept 1988.

J. A. Harvey, N. W. Hill, F. G. Perey, G. L. Tweed and L. C. Leal, "High-Resolution Neutron Transmission Measurements on 235U, 239Pu, and 238U," in Proceedings of the International Conference on Nuclear Data for Science and Technology, Mito, Japan, May 1988.

H. Derrien, G. de Saussure, N. M. Larson, L. C. Leal, and R. B. Perez, "R-Matrix Analysis of the 235U and 239Pu Neutron Cross Sections," Proceedings of the International Conference on Nuclear Data for Science and Technology, Mito, Japan, May 1988.

L. C. Leal, G. de Saussure, R. B. Perez, "R-Matrix Analysis of the 235U Neutron Cross Sections," American Nuclear Society, San Diego, CA, June 1988.

L. C. Leal and R. N. Hwang, "A Finite Difference Method for Treating the Doppler Broadening of Neutron Cross Sections," American Nuclear Society, Los Angeles, CA, Nov 1987.

L. C. Leal, KERNELBUT Computer Code, INIS-BR-028967/1983 (in Portuguese).

L. C. Leal, 1DX and Generator Computer Code, INIS-BR-028966/1983 (in Portuguese).

L. C. Leal and J. A. W. Nobrega, HAMMER, LITHE and HELP computer code, INIS-BR-028964/1983 (in Portuguese).

L. C. Leal and J. A. W. Nobrega, EXTERMINATOR-2 computer code, S-BR-028965/1983 (in Portuguese).

J. A. W. Nobrega, C. F. Silva, and L. C. Leal, "Conversion and Implementation of Nuclear Computer Code, INIS-BR- 1 19/1983 1 (in Portuguese).

L. C. Leal and J. T. Assis, "Scattering Kernel Computation for Thermal Neutron in H20 and D20," Second Meeting of Reactor Physics, Itaipava/Rio de Janeiro Brazil, April 1981.

L. C. Leal, "Utilization of The Nelkin Model in the HAMMER Code for Calculation of Reactor Parameters," M.Sc. Thesis, presented to the Nuclear Engineering Department/COPPE of The Federal University of Rio de Janeiro/Brazil, July 1980 (in Portuguese).