FLOWTRAN-TF software design
FLOWTRAN-TF was created to analyze an individual Mk22 fuel assembly during a large break Loss Of Coolant Accident (LOCA) scenario involving the Savannah River Site K-reactor after the initial few seconds of the transient. During the initial few seconds reactor cooling is limited by the static or Ledinegg flow instability phenomenon. The predecessor FLOWTRAN code was developed to analyze this portion of a LOCA. In the several seconds following the break, a significant fraction of the reactor coolant inventory leaks out the break, Emergency Cooling System (ECS) flow is initiated, and air enters the primary coolant circulation loops. Reactor fuel assemblies are cooled by a low flowrate air-water downflow. Existing commercial nuclear industry thermal-hydraulic codes were judged inadequate for detailed modeling of a Mk22 fuel assembly because the application involves a ribbed annular geometry, low pressure, downflow and an air-water mixture. FLOWTRAN-TF is a two-phase thermal-hydraulics code of similar technology to existing commercial codes such as RELAP and TRAC but customized for Savannah River Site applications. The main features and capabilities of FLOWTRAN-TF are detailed Mk22 fuel assembly ribbed annular geometry; conjugate heat transfer; detailed neutronic power distribution; three-dimensional heat conduction in Mk22 fuel and target tubes; two-dimensional coolant flow in channels (axial, azimuthal); single-phase and/or two-phase fluid (gas, liquid and/or gas-liquid); two-component (air, water); constitutive models applicable to low pressure air-water downflow in ribbed annular channels. The design of FLOWTRAN-TF is described in detail in this report which serves as the Software Design Report in accordance with Quality Assurance Procedure IV-4, Rev. 0 Software Design and Implementation'' in the 1Q34 manual.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 6538896
- Report Number(s):
- WSRC-TR-92-532; ON: DE93012824
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
F CODES
DESIGN
PRODUCTION REACTORS
COMPUTER PROGRAM DOCUMENTATION
FLUID FLOW
HEAT TRANSFER
LOSS OF COOLANT
MATHEMATICAL MODELS
REACTOR COOLING SYSTEMS
SAVANNAH RIVER PLANT
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY TRANSFER
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors