CTF Validation and Verification Manual

Technical Report · Wed May 25 00:00:00 EDT 2016

DOI:https://doi.org/10.2172/1342678· OSTI ID:1342678

Salko, Robert K. ^[1]; Blyth, Taylor S. ^[2]; Dances, Christopher A. ^[2]; Magedanz, Jeffrey W. ^[2]; Jernigan, Caleb ^[3]; Kelly, Joeseph ^[4]; Toptan, Aysenur ^[5]; Gergar, Marcus ^[2]; Gosdin, Chris ^[2]; Avramova, Maria ^[2]; Palmtag, Scott ^[6]; Gehin, Jess C. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. Pennsylvania State Univ., University Park, PA (United States)
3. Holtec International, Marlton, NJ (United States)
4. U.S. Nuclear Regulatory Commission (NRC), Rockville, MD (United States)
5. North Carolina State Univ., Raleigh, NC (United States)
6. Core Physics, Inc., Cary, NC (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) 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 nine conservation equations are available for LWR modeling. The code was originally developed by Pacific Northwest Laboratory in 1980 and has been used and modified by several institutions over the last several decades. COBRA-TF is also used at the Pennsylvania State University (PSU) by the Reactor Dynamics and Fuel Management Group (RDFMG), and has been improved, updated, and subsequently became the PSU RDFMG version of COBRA-TF (CTF). One part of the improvement process includes validating the methods in CTF. This document seeks to provide a certain level of certainty and confidence in the predictive capabilities of the code for the scenarios it was designed to model--rod bundle geometries with operating conditions that are representative of prototypical Pressurized Water Reactor (PWR)s and Boiling Water Reactor (BWR)s in both normal and accident conditions. This is done by modeling a variety of experiments that simulate these scenarios and then presenting a qualitative and quantitative analysis of the results that demonstrates the accuracy to which CTF is capable of capturing specific quantities of interest.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Consortium for Advanced Simulation of LWRs (CASL)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1342678
• Report Number(s): ORNL/TM-2016/433; CASL-U-2016-1113-000; TRN: US1701893
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
97 MATHEMATICS AND COMPUTING
PWR TYPE REACTORS
BWR TYPE REACTORS
SIMULATION
MANUALS
FUEL ELEMENT CLUSTERS
RODS