Luiz Leal Contact LEALLC@ORNL.GOV All Publications 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... Covariances of Evaluated Nuclear Cross Section Data for (232)Th, (180,182,183,184,186)W and (55)Mn ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data ... 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... Resonance Evaluation of 48Ti Including Covariance for Criticality Safety Applications... Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development... Evaluation of the Chromium Resonance Parameters Including Resonance Parameter Covariance... Evaluation of (50)Cr, (52)Cr, (53)Cr, (54)Cr Neutron Cross Section Data for Energies up to 200 MeV... Cross-Section Covariance Data Processing with the AMPX Module PUFF-IV Computation of Temperature-Dependent Legendre Moments of a Double-Differential Elastic Cross Section... Retroactive Generation of Covariance Matrix of Nuclear Model Parameters Using Marginalization Techniques Astrophysical reaction rates for Ni-58,Ni-60(n,gamma) from new neutron capture cross section measurements... Comparison of Resonance Parameter Covariance Generation using CONRAD and SAMMY Computer Codes... Reevaluation of 58Ni and 60Ni Resonance Parameters in the Energy Range Thermal to 800 keV... Covariance Generation Using CONRAD and SAMMY Computer Codes R-Matrix Analysis of 238U High Resolution Neutron Transmissions and Capture Cross Sections in the Energy Range 0 keV to 20 keV Approximating large resonance parameter covariance matrices with group-wise covariance matrices for advanced nuclear fuel cyc... R-MATRIX ANALYSIS of 232Th NEUTRON TRANSMISSIONS and CAPTURE CROSS SECTIONS in the ENERGY RANGE THERMAL to 4 keV... Impact of the 235U Covariance Data in Benchmark Calculations 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
