BRENDA: A Dynamic Simulator for a Sodium-cooled Fast Reactor Power PlantNuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety, 1978 - Digital computer simulation - 82 pages |
Other editions - View all
Common terms and phrases
60 SEC SEC Appendix Arizona AVERAGE CHANNEL BRENDA BTU/LBM CALCULATING CENTERLINE OF CORE CLAD OUTER SURFACE CONSTANT contains CORE CRBRP DARE DELAY DENSITY DENSITY AT NODE DERIVATIVE dynamic electric END OF RAMP ENDPRO ENTHALPY ENTHALPY AT NODE EVAPORATOR EXIT F/SEC FEEDWATER FETAG FORCED CHANGE FRICTION FUEL PIN FUNCTION GROUPING HEAD HEAT TRANSFER COEFFICIENT HOT CHANNEL included INITIAL INLET input LBM/HR LBM/SEC LENGTH LINE LIST LOCATION LOOP MASS FLOW RATE MAXIMUM TEMP MEASURED FROM CENTERLINE method NODE S2 Nuclear NUMBER output PAS2 PAS4 PIPE plant plots PRESSURE PRIMARY PRIMARY PUMP PROCED PUMP RAMP CHANGE RATE AT NODE reactivity REACTOR REGION REGION AS2 response SATURATED STEAM SATURATED WATER simulator SODIUM STEAM DRUM step SUPERHEATER SURFACE TEMP SWITCH PARAMETER TABLE TACL TEMP AT NODE temperature TERMS transient TURBOGENERATOR University values variable Wait