BWR in-core fuel management optimization using parallel simulated annealing in FORMOSA-B
Creators
- 1. Department of Nuclear Engineering, North Carolina State University, Campus Box 7909, Raleigh, NC 27695-7909 (United States)
Description
The process of finding optimized fuel reload patterns for boiling water reactors is complicated by a number of factors including the large number of fuel assemblies involved, the three-dimensional neutronic and thermal-hydraulic variations, and the interplay of coolant flow rate with control rod programming. The FORMOSA-B code was developed to provide an automated method for finding fuel loading patterns, control rod programs and coolant flow rate schedules to minimize certain quantitative metrics of core performance while satisfying given operational constraints. One drawback of this code has been the long runtimes required for a complete cycle optimization on a desktop workstation (oftentimes several days or more). To address this shortcoming, a parallel simulated annealing algorithm has been added to the FORMOSA-B code, so that the runtimes may be greatly reduced by using a multiprocessor computer cluster. Tests of the algorithm on a sample problem indicate that it is capable of parallel efficiencies exceeding 80% when using four processors.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2010.09.002Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2010.09.002;
- PII
- S0149197010001423;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 53
- Journal Issue
- 6
- Journal Page Range
- p. 600-606
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51010809
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALGORITHMS; ARRAY PROCESSORS; BWR TYPE REACTORS; COMPUTER CODES; CONTROL ELEMENTS; COOLANTS; FLOW RATE; FUEL ASSEMBLIES; FUEL MANAGEMENT; PROGRAMMING; REACTOR CORES; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTERS; DIGITAL COMPUTERS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MANAGEMENT; MATHEMATICAL LOGIC; MECHANICS; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Copyright © 2010 Elsevier Ltd. All rights reserved.