Luiz Leal Contact LEALLC@ORNL.GOV All Publications 235U Resolved Resonance Evaluation for Benchmark Calculations in the Intermediate Energy Region 239Pu Resonance Evaluation for Thermal Benchmark System Calculations... ORNL Resolved Resonance Covariance Generation for ENDF/B-VII.1... ORNL Resonance Evaluation for ENDF/B-VII.1... Covariance Matrix of a Double-Differential Doppler-broadened Elastic Scattering Cross Section... Convergence of Legendre Expansion of Doppler-Broadened Double Differential Elastic Scattering Cross Section... Re-estimation of Nuclear Data and JEFF 3.1.1 Uncertainty Calculations... ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data ... Covariances of Evaluated Nuclear Cross Section Data for (232)Th, (180,182,183,184,186)W and (55)Mn Resonance Evaluation of 48Ti Including Covariance for Criticality Safety Applications... Resonance Region Cross-Section Data Advancements for Nuclear Criticality Safety Applications and ENDF/B-VII.1 New Improved Nuclear Data for Nuclear Criticality and Safety... Evaluation of (50)Cr, (52)Cr, (53)Cr, (54)Cr Neutron Cross Section Data for Energies up to 200 MeV... Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development... Evaluation of the Chromium Resonance Parameters Including Resonance Parameter Covariance... Cross-Section Covariance Data Processing with the AMPX Module PUFF-IV Computation of Temperature-Dependent Legendre Moments of a Double-Differential Elastic Cross Section... Astrophysical reaction rates for Ni-58,Ni-60(n,gamma) from new neutron capture cross section measurements... Retroactive Generation of Covariance Matrix of Nuclear Model Parameters Using Marginalization Techniques Comparison of Resonance Parameter Covariance Generation using CONRAD and SAMMY Computer Codes... Covariance Generation Using CONRAD and SAMMY Computer Codes Reevaluation of 58Ni and 60Ni Resonance Parameters in the Energy Range Thermal to 800 keV... R-Matrix Analysis of 238U High Resolution Neutron Transmissions and Capture Cross Sections in the Energy Range 0 keV to 20 keV R-MATRIX ANALYSIS of 232Th NEUTRON TRANSMISSIONS and CAPTURE CROSS SECTIONS in the ENERGY RANGE THERMAL to 4 keV... Approximating large resonance parameter covariance matrices with group-wise covariance matrices for advanced nuclear fuel cyc... Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 Next page ›â¶Äº Last page Last » Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Data, Criticality Safety, and Radiation Transport Section Nuclear Data Group
