"Transients." . . "United States. Department of Energy. Office of Scientific and Technical Information." . . "Temperature Measurement." . . "Liquid Metal Cooled Reactors." . . "Reactors." . . "After-heat Removal." . . "Fast Reactors." . . "Epithermal Reactors." . . "Validation." . . "Hydraulics." . . "S Codes." . . "N Codes." . . "Safety Analysis." . . . . . . . . . . . . . . "Code validation with EBR-II test data"@en . "Code validation with EBR-II test data" . . . . . . . . . "An extensive system of computer codes is used at Argonne National Laboratory to analyze whole-plant transient behavior of the Experimental Breeder Reactor 2. Three of these codes, NATDEMO/HOTCHAN, SASSYS, and DSNP have been validated with data from reactor transient tests. The validated codes are the foundation of safety analyses and pretest predictions for the continuing design improvements and experimental programs in EBR-II, and are also valuable tools for the analysis of innovative reactor designs."@en . "An extensive system of computer codes is used at Argonne National Laboratory to analyze whole-plant transient behavior of the Experimental Breeder Reactor 2. Three of these codes, NATDEMO/HOTCHAN, SASSYS, and DSNP have been validated with data from reactor transient tests. The validated codes are the foundation of safety analyses and pretest predictions for the continuing design improvements and experimental programs in EBR-II, and are also valuable tools for the analysis of innovative reactor designs." . . . "An extensive system of computer codes is used at Argonne National Laboratory to analyze whole-plant transient behavior of the Experiment Breeder Reactor 2. Three of these codes, NATDEMO/HOTCHAN, SASSYS, and DSNP have been validated with data from reactor transient tests. The validated codes are the foundation of safety analyses and pretest predictions for the continuing design improvements and experimental programs in EBR-2, and are also valuable tools for the analysis of innovative reactor designs. 29 refs., 6 figs."@en . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . "Fermions." . . "Sodium Cooled Reactors." . . "Lmfbr Type Reactors." . . "Argonne National Lab." . . "Energy Transfer." . . "Breeder Reactors." . . "Testing." . . "Safety." . . "Nucleons." . . . . "Power Reactors." . . "Chang, L.K." . . "Mohr, D." . . "Planchon, H.P." . . "Fluid Mechanics." . . "Removal." . . "Hill, D.J." . . "Design." . . "Modifications." . . "Hadrons." . . "Reactor Safety." . . "Baryons." . . "Dean, E.M." . . "Heat Transfer." . . "Fbr Type Reactors." . . "General Studies Of Nuclear Reactors." . . "Computer Codes." . . "Experimental Reactors." . . "Mechanics." . . "Ebr-2 Reactor." . . "Feldman, E.E." . . "Elementary Particles." . . "Neutrons." . . "United States. Department of Energy." . . "Herzog, J.P." . . "D Codes." . . "Specific Nuclear Reactors And Associated Plants." . . "Research And Test Reactors." . .