Improvements, enhancements, and optimizations of COBRA-TF
- 1. Pennsylvania State University, University Park, PA (United States)
- 2. Sandia National Laboratory, Albuquerque, NM (United States)
- 3. Core Physics, Inc., Wilmington, NC (United States)
- 4. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
Description
The Reactor Dynamics and Fuel Management Group (RDFMG) at The Pennsylvania State University (PSU) has become active in the Consortium for Advanced Simulation of Light Water Reactors (CASL) program by delivering, supporting, and further developing CTF, the PSU version of the Coolant Boiling in Rod Arrays - Two Fluids (COBRA-TF) Thermal/Hydraulic (T/H), sub-channel program. New development work on CTF was primarily geared towards decreasing the execution time of the code so that it may eventually be used for performing pin-by-pin, full-core simulations. Great gains have been made through targeting sections of source code for optimization. For example, wall clock time has been reduced for a one-assembly, three-dimensional model, containing ∼9,400 mesh cells, from 9.2 min to 1 min. A further improvement has been reduction in code memory usage, which was previously prohibitive for large models. In conjunction with the run time speedups, this has enabled the simulation of a refined quarter-core model (∼460,000 mesh cells), which saw a reduction in memory usage from over 130 GB to less than 3 GB. In addition to the optimization work, RDFMG has also created a preprocessor utility for the fast and less error-prone generation of CTF input decks. Furthermore, basic post-processing capabilities have been implemented by creating a CTF subroutine for producing Visualization Tool-Kit (VTK) files that output mesh data and associated simulation results. These VTK files can be opened with visualization software. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-700-2
- Imprint Title
- Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
- Imprint Pagination
- 3016 p.
- Journal Page Range
- p. 2170-2181
Conference
- Title
- 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
- Acronym
- M and C 2013
- Dates
- 5-9 May 2013
- Place
- Sun Valley, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 45033823
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Quality check status
- Yes
- Descriptors DEI
- BOILING; C CODES; FUEL MANAGEMENT; OPTIMIZATION; REACTOR CORES; REACTOR KINETICS; SIMULATION; THREE-DIMENSIONAL CALCULATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS;
- Descriptors DEC
- COMPUTER CODES; KINETICS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; PHASE TRANSFORMATIONS; REACTOR COMPONENTS; REACTORS;
Optional Information
- Lead record
- cgjt4-fyf07
- Notes
- 12 refs.