Development and Assessment of CTF for Pin-resolved BWR Modeling
Conference
·
OSTI ID:1356920
- ORNL
- North Carolina State University (NCSU), Raleigh
- Pennsylvania State University
CTF is the modernized and improved version of the subchannel code, COBRA-TF. It has been adopted by the Consortium for Advanced Simulation for Light Water Reactors (CASL) for subchannel analysis applications and thermal hydraulic feedback calculations in the Virtual Environment for Reactor Applications Core Simulator (VERA-CS). CTF is now jointly developed by Oak Ridge National Laboratory and North Carolina State University. Until now, CTF has been used for pressurized water reactor modeling and simulation in CASL, but in the future it will be extended to boiling water reactor designs. This required development activities to integrate the code into the VERA-CS workflow and to make it more ecient for full-core, pin resolved simulations. Additionally, there is a significant emphasis on producing high quality tools that follow a regimented software quality assurance plan in CASL. Part of this plan involves performing validation and verification assessments on the code that are easily repeatable and tied to specific code versions. This work has resulted in the CTF validation and verification matrix being expanded to include several two-phase flow experiments, including the General Electric 3 3 facility and the BWR Full-Size Fine Mesh Bundle Tests (BFBT). Comparisons with both experimental databases is reasonable, but the BFBT analysis reveals a tendency of CTF to overpredict void, especially in the slug flow regime. The execution of these tests is fully automated, analysis is documented in the CTF Validation and Verification manual, and the tests have become part of CASL continuous regression testing system. This paper will summarize these recent developments and some of the two-phase assessments that have been performed on CTF.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility (OLCF); Consortium for Advanced Simulation of LWRs (CASL)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1356920
- Country of Publication:
- United States
- Language:
- English
Similar Records
Assessment of the Subchannel Code CTF for Single- and Two-Phase Flows
Development and Implementation of a CTF Code Verification Suite.
CTF Parallel Performance Improvements
Journal Article
·
Thu Sep 06 20:00:00 EDT 2018
· Nuclear Technology
·
OSTI ID:1545243
Development and Implementation of a CTF Code Verification Suite.
Journal Article
·
Sat Oct 31 20:00:00 EDT 2020
· Nuclear Engineering and Design
·
OSTI ID:1721598
CTF Parallel Performance Improvements
Journal Article
·
Fri Jul 01 00:00:00 EDT 2016
· Transactions of the American Nuclear Society
·
OSTI ID:23042909