ENDF/B-VIII.0-based fast neutron removal cross sections database in Z = 1 to 92 generated via multi-layered spherical geometry
Frederick C. Hila, J.F.M. Jecong, Cheri Anne M. Dingle, Alvie Asuncion-Astronomo, Charlotte V. Balderas, Jennifer A. Sagum, Neil Raymund D. Guillermo
Topics & Concepts
Neutron transportNuclear dataNeutronNuclear physicsPhysicsNeutron sourceNeutron cross sectionComputational physicsNeutron temperatureChemistryRadiation Shielding Materials AnalysisNuclear Physics and ApplicationsGraphite, nuclear technology, radiation studies