CTF Theory Manual
- Pennsylvania State Univ., University Park, PA (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Coolant-Boiling in Rod Arrays|Two Fluids (COBRA-TF) is a thermal/ hydraulic (T/H) simulation code designed for light water reactor (LWR) vessel analysis. It uses a two-fluid, three-field (i.e. fluid film, fluid drops, and vapor) modeling approach. Both sub-channel and 3D Cartesian forms of 9 conservation equations are available for LWR modeling. The code was originally developed by Pacific Northwest Laboratory in 1980 and had been used and modified by several institutions over the last few decades. COBRA-TF also found use at the Pennsylvania State University (PSU) by the Reactor Dynamics and Fuel Management Group (RDFMG) and has been improved, updated, and subsequently re-branded as CTF. As part of the improvement process, it was necessary to generate sufficient documentation for the open-source code which had lacked such material upon being adopted by RDFMG. This document serves mainly as a theory manual for CTF, detailing the many two-phase heat transfer, drag, and important accident scenario models contained in the code as well as the numerical solution process utilized. Coding of the models is also discussed, all with consideration for updates that have been made when transitioning from COBRA-TF to CTF. Further documentation outside of this manual is also available at RDFMG which focus on code input deck generation and source code global variable and module listings.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Consortium for Advanced Simulation of LWRs (CASL)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1340446
- Report Number(s):
- ORNL/TM--2016/430; CASL-U-2016-1110-000
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BOILING
C CODES
COMPUTERIZED SIMULATION
COOLANTS
DRAG
FILMS
FUEL RODS
HEAT TRANSFER
MANUALS
NUMERICAL SOLUTION
PRESSURE VESSELS
REACTOR ACCIDENTS
REACTOR CORES
REACTOR KINETICS
THERMAL HYDRAULICS
TWO-PHASE FLOW
VAPORS
WATER COOLED REACTORS
WATER MODERATED REACTORS