DEMO4; CRBR reactor and plant transient analysis. [CDC7600; FORTRAN IV]

Technical Report ·

OSTI ID:6403807

DEMO4 is a simulation model used to generate thermal-hydraulic transients for the Clinch River LMFBR demonstration plant. The three heat transport loops of the plant are simulated by a two-loop model. One loop, the L-loop, represents two of the actual plant loops, and the second loop, the S-loop, represents a single plant loop. Thermal power is generated by point neutron kinetics and decay heat tables. The vessel internals are represented by a lower plenum, lower axial blanket, active core, upper axial blanket, radial blanket, bypass channel and an upper plenum with a variable sodium level and a cover gas. Plenum stratification on reduced flow can be modelled. The heated sodium leaves the vessel upper plenum to the primary heat transport system and returns to the vessel lower plenum. The overflow nozzle of the sodium purification system effects the vessel upper plenum level, as well as a user-input return flow from this system. Each primary heat transport system is represented by piping, valves, the primary pump tank with a free surface and cover gas, and the shell side of the IHX. Each intermediate heat transport system is represented by piping, the tube side of the IHX, the shell side of the superheater and evaporator, and the intermediate pump. Each water-steam system is represented by piping, recirculation pumps, the tube side of the superheater and evaporator, and a steam drum. The steam leaving all superheaters enters a common steam header, flows through piping to the turbine throttle valve and a steam dump valve. Limited modelling is provided for the feedwater system.CDC7600; FORTRAN IV; SCOPE 2.0; 1 user-defined tape or disk is required for optional plotting in addition to the standard input/output devices.

• Research Organization: Argonne National Lab., IL (USA)
• OSTI ID: 6403807
• Report Number(s): ANL/NESC-676R; ON: DE83048676
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BLOWDOWN
BOILERS
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPUTER CODES
COMPUTERIZED SIMULATION
D CODES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
POWER REACTORS
REACTORS
SIMULATION
SODIUM COOLED REACTORS
STEAM GENERATORS
THERMAL POWER PLANTS
TRANSIENTS
VAPOR GENERATORS