Marco T Pigni Distinguished R&D Nuclear Data Scientist Contact PIGNIMT@ORNL.GOV All Publications Validation and Testing of ENDF/B-VII Decay Data Evaluation of Tungsten Neutron Cross Sections in the Resolved Resonance Regions... Validation and Testing of ENDF/B-VII Decay Data Validation and Testing of ENDF-B-VII Decay Data Validation and Testing of ENDF/B-VII Decay Data SCALE Uncertainty Quantification Methodology for Criticality Safety Analysis of Used Nuclear Fuel Measurement of resolved resonances of Th-232(n, gamma) at the n_TOF facility at CERN 183W Resonance Parameter Evaluation in the Neutron Energy Range Up to 5 keV... Resonance neutron-capture cross sections of stable magnesium isotopes and their astrophysical implications... Measurement and resonance analysis of the Np-237 neutron capture cross section Neutron-induced fission cross section of Cm-245: New results from data taken at the time-of-flight facility n_TOF Measurement of the neutron-induced fission cross-section of Am-243 relative to U-235 from 0.5 to 20 MeV ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data ... Measurement of the U-236(n, f) cross section from 170 meV to 2 MeV at the CERN n_TOF facility... Au-197(n,gamma) cross section in the unresolved resonance region... Neutron-induced fission cross-section of U-233 in the energy range 0.5 < E-n < 20 MeV... Low-fidelity Covariance Project... Pagination First page « First Previous page ‹‹ Page 1 Page 2 Current page 3 Key Links Curriculum Vitae ORCID 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 SCALE
Research Highlight Uncertainty Quantification in (α,n) Neutron Source Calculations in an Oxide Matrix
