SCDAP/RELAP5/MOD2 code manual
SCDAP/RELAP5/MOD2 code manual
The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, and the fission products and aerosols in the system during a severe accident transient as well as large and small break loss-of-coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. The modeling theory and associated numerical schemes are documented in Volumes I and II to acquaint the user with the modeling base and thus aid in effective use of the code.
- University of North Texas United States
Thermodynamic Properties, Boiling Water Cooled, Nonbreeding, Nonboiling Water Cooled, Hydraulics, Control Systems, 21 Specific Nuclear Reactors And Associated Plants, Reactor Accidents, Reactor Cooling Systems, Fuel Rods, 220200 -- Nuclear Reactor Technology-- Components & Accessories, Radioactive Materials, Isotopes, Radiation Transport, Analog Systems, Reactor Simulators, Energy Systems, Dispersions, Materials, Computerized Simulation, Fission Product Release, 220100 -- Nuclear Reactor Technology-- Theory & Calculation, R Codes, Reactor Kinetics, 22 General Studies Of Nuclear Reactors, After-Heat, Mathematical Models, Agglomeration, Pwr Type Reactors, Thermal Conductivity, Creep, Heat Transfer, Particulates, Particles, Reactor Instrumentation, Fission Products, Reactor Control Systems, Manuals, Safety, Computerized Models, Simulation, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Loss Of Coolant, 210100 -- Power Reactors, 990220 -- Computers, Fluid Mechanics, Mechanics, T Codes, Functional Models, Transients, Simulators, Mechanical Properties, Control Elements, Corium, Fuel Elements, Colloids, M Codes, Reactor Components, Light-Water Moderated, Aerosols, Reactor Safety, Computer Codes, S Codes, Computing, Cooling Systems, Bwr Type Reactors, Reactors, Document Types, 99 General And Miscellaneous//Mathematics, Reactor Protection Systems, Physical Properties, Kinetics, Fuel Cans, Energy Transfer, & Computer Programs-- (1987-1989), Sols, Accidents, And Information Science, 210200 -- Power Reactors, Water Cooled Reactors
Thermodynamic Properties, Boiling Water Cooled, Nonbreeding, Nonboiling Water Cooled, Hydraulics, Control Systems, 21 Specific Nuclear Reactors And Associated Plants, Reactor Accidents, Reactor Cooling Systems, Fuel Rods, 220200 -- Nuclear Reactor Technology-- Components & Accessories, Radioactive Materials, Isotopes, Radiation Transport, Analog Systems, Reactor Simulators, Energy Systems, Dispersions, Materials, Computerized Simulation, Fission Product Release, 220100 -- Nuclear Reactor Technology-- Theory & Calculation, R Codes, Reactor Kinetics, 22 General Studies Of Nuclear Reactors, After-Heat, Mathematical Models, Agglomeration, Pwr Type Reactors, Thermal Conductivity, Creep, Heat Transfer, Particulates, Particles, Reactor Instrumentation, Fission Products, Reactor Control Systems, Manuals, Safety, Computerized Models, Simulation, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety, Loss Of Coolant, 210100 -- Power Reactors, 990220 -- Computers, Fluid Mechanics, Mechanics, T Codes, Functional Models, Transients, Simulators, Mechanical Properties, Control Elements, Corium, Fuel Elements, Colloids, M Codes, Reactor Components, Light-Water Moderated, Aerosols, Reactor Safety, Computer Codes, S Codes, Computing, Cooling Systems, Bwr Type Reactors, Reactors, Document Types, 99 General And Miscellaneous//Mathematics, Reactor Protection Systems, Physical Properties, Kinetics, Fuel Cans, Energy Transfer, & Computer Programs-- (1987-1989), Sols, Accidents, And Information Science, 210200 -- Power Reactors, Water Cooled Reactors
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