Marco T Pigni Distinguished R&D Nuclear Data Scientist Contact PIGNIMT@ORNL.GOV All Publications R-matrix analysis of n+natCl reactions up to 1.2 MeV R-MATRIX SCHOOL 2025: INTRODUCTION TO R-MATRIX THEORY... Unresolved resonance parameter evaluation and uncertainty quantification of n+181Ta reactions Integral Experiment Request 554: CED-2 Summary Report A new Ta-181 neutron resolved resonance region evaluation... Effective R-Matrix Parameterizations for Nuclear Data Resonance Parameter Evaluation of n+88Sr reactions for ENDF/B-VIII.1 Library R-matrix Resolved Resonance Region Evaluation of 140,142Ce Measurement of the neutron-induced capture-to-fission cross section ratio in 233U at LANSCE R-MATRIX ANALYSIS AND STATISTICAL PROPERTIES OF DYSPROSIUM ISOTOPES IN THE NEUTRON ENERGY RANGES UP TO A FEW KEV Evaluation of light-element reactions in the resolved resonance region Modernization efforts for the R-Matrix code SAMMY 140,142Ce Neutron Cross Section Resolved Resonance Region Evaluation... Quantification of the 35Cl (n,p) reaction channel Integral Experiment Request 554 CED-1 Summary Report... First near-threshold measurements of the 13C(α,n1)16O reaction for low-background-environment characterization Standardizing a Renewed Fission Product Yield Library and Related Covariances (Part II)... Low-Energy Reactions of the n+233U Nuclear Compound System and Its Initial Validation Progress on the reevaluation and validation of the n+ 233 U neutron cross sections Updates to Improve the Evaluated Nuclear Data of Copper Isotopes in the Resolved and Unresolved Resonance Regions Newly Evaluated Neutron Reaction Data on Chromium Isotopes Fission Product Yield Data Adjustment in a Prototype Version of TSURFER (alpha,n) nuclear data scoping study... Nuclear Data Scoping Studies for Nonproliferation - paper Consistency of 16O(n,α) cross sections Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » 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
