Published 2013 | Version v1
Book

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.