Nuclear Data Evaluations for Fusion Technology and High Energy Applications
{"Image DocumentName": "Nuclear Data Evaluations for Fusion Technology and High Energy Applications", "Image ImageDescription": "Objectives: To provide cross-section data evaluations required for fusion neutronics calculations (transport and transmutation/activation) Evaluation of neutron induced cross-sections for EFF/JEFF (Joint Evaluated Fusion Fission File) up to 150 MeV neutron energy. Production of complete data files (ENDF6 data format) for processing with NJOY (use with MC & SN codes) Suitable for fusion and other applications. Complete data files for 182,183,184,186W, 181Ta, 55Mn, 52Cr evaluation. Largely with co-variance data. Contributions to FENDL-3 project co-ordinated by IAEA/NDS. Evaluation of d + 6,7Li data up to 50 MeV for IFMIF D-Li source term simulation using McDeLicious MC code.", "Image XResolution": "37", "Image YResolution": "37", "Image ResolutionUnit": "Pixels/Centimeter", "Image Software": "SlidePlayer", "Image YCbCrPositioning": "Centered"}