Simulation of a U-tube steam generator with COBRA-IV and COBRA-TF. Interim report
The results of thermal-hydraulic simulations of a Combustion Engineering System 80 U-tube steam generator are presented. Both steady-state and transient conditions are considered to compare the results of the Battelle COBRA-IV homogeneous-equilibrium code and a newly developed two-fluid (UVUT) two-phase flow model called COBRA-TF (EPRI). The details of formulating the code input to simulate the primary and secondary flows are discussed. All results presented here must be considered as only a demonstration and not as actual steam generator behavior.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- DOE Contract Number:
- EY-76-C-06-1830
- OSTI ID:
- 5746117
- Report Number(s):
- EPRI-NP-1211; TRN: 80-000737
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of single- and two-phase flow fields around PWR steam generator tube support plates
Core thermal model: COBRA-IV development and applications. [PWR and BWR]
CASL COBRA-TF improvements for PWR DNB analysis
Technical Report
·
Wed Aug 01 00:00:00 EDT 1979
·
OSTI ID:5746117
Core thermal model: COBRA-IV development and applications. [PWR and BWR]
Technical Report
·
Sat Jan 01 00:00:00 EST 1977
·
OSTI ID:5746117
+4 more
CASL COBRA-TF improvements for PWR DNB analysis
Conference
·
Fri Jul 01 00:00:00 EDT 2016
·
OSTI ID:5746117
+3 more
Related Subjects
20 FOSSIL-FUELED POWER PLANTS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
C CODES
PWR TYPE REACTORS
STEAM GENERATORS
COMPUTERIZED SIMULATION
OPERATION
ENTHALPY
FLOW RATE
GRAPHS
MATHEMATICAL MODELS
TEMPERATURE DISTRIBUTION
THEORETICAL DATA
TWO-PHASE FLOW
BOILERS
DATA
DATA FORMS
FLUID FLOW
INFORMATION
NUMERICAL DATA
PHYSICAL PROPERTIES
REACTORS
SIMULATION
THERMODYNAMIC PROPERTIES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
200104* - Fossil-Fueled Power Plants- Components
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
C CODES
PWR TYPE REACTORS
STEAM GENERATORS
COMPUTERIZED SIMULATION
OPERATION
ENTHALPY
FLOW RATE
GRAPHS
MATHEMATICAL MODELS
TEMPERATURE DISTRIBUTION
THEORETICAL DATA
TWO-PHASE FLOW
BOILERS
DATA
DATA FORMS
FLUID FLOW
INFORMATION
NUMERICAL DATA
PHYSICAL PROPERTIES
REACTORS
SIMULATION
THERMODYNAMIC PROPERTIES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
200104* - Fossil-Fueled Power Plants- Components
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled