Luiz Leal Contact LEALLC@ORNL.GOV All Publications Impact of the 235U Covariance Data in Benchmark Calculations New Neutron-Induced Cross-Section Measurements for Weak s-process Studies... Recent Advances with the AMPX Covariance Processing Capabilities in PUFF-IV Evaluation of Tungsten Nuclear Reaction Data with Covariances Resonance Region Covariance Analysis Method and New Covariance Data for Th-232, U-233, U-235, U-238, and Pu-239... (239)Pu neutron resonance parameters revisited and covariance matrix in the neutron energy range from thermal to 2.5 keV... New Neutron Cross-Section Measurements from ORELA and New Resonance Parameter Evaluations Current Status of the R-Matrix Code SAMMY, with Emphasis on the Relationship to ENDF Formats Comparative Analysis of Nuclear Cross Sections in Monte Carlo Methods for Medical Physics Applications Perspective on Advances in Resonance-Region Nuclear Modeling and Opportunities for Future Research New Neutron Cross-Section Measurements at ORELA for Improved Nuclear Criticality Calculations... Neutron Cross Section Measurements at ORELA for Improved Nuclear Data and Their Application... New Neutron Cross Section Measurements at ORELA for Improved Nuclear Data Neutron Capture Reaction Rates for Silicon and Their Impact on the Origin of Presolar Mainstream SiC Grains... High-Resolution Transmission Measurements of <sup>233</sup>U Using a Cooled Sample at the Temperature T=11 K Pagination First page « First Previous page ‹‹ Page 1 Page 2 Current page 3 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
