A nuclear reload optimization approach using a real coded genetic algorithm with random keys
Creators
- 1. Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia. Programa de Engenharia Nuclear
Description
The fuel reload of a Pressurized Water Reactor is made whenever the burn up of the fuel assemblies in the nucleus of the reactor reaches a certain value such that it is not more possible to maintain a critical reactor producing energy at nominal power. The problem of fuel reload optimization consists on determining the positioning of the fuel assemblies within the nucleus of the reactor in an optimized way to minimize the cost benefit relationship of fuel assemblies cost per maximum burn up, and also satisfying symmetry and safety restrictions. The fuel reload optimization problem difficulty grows exponentially with the number of fuel assemblies in the nucleus of the reactor. During decades the fuel reload optimization problem was solved manually by experts that used their knowledge and experience to build configurations of the reactor nucleus, and testing them to verify if safety restrictions of the plant are satisfied. To reduce this burden, several optimization techniques have been used, included the binary code genetic algorithm. In this work we show the use of a real valued coded approach of the genetic algorithm, with different recombination methods, together with a transformation mechanism called random keys, to transform the real values of the genes of each chromosome in a combination of discrete fuel assemblies for evaluation of the reload optimization. Four different recombination methods were tested: discrete recombination, intermediate recombination, linear recombination and extended linear recombination. For each of the 4 recombination methods 10 different tests using different seeds for the random number generator were conducted 10 generating, totaling 40 tests. The results of the application of the genetic algorithm are shown with formulation of real numbers for the problem of the nuclear reload of the plant Angra 1 type PWR. Since the best results in the literature for this problem were found by the parallel PSO we will it use for comparison. (author)
Files
41115770.pdf
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Additional details
Publishing Information
- Imprint Pagination
- [10 p.]
- Report number
- INIS-BR--7463
Conference
- Title
- International nuclear atlantic conference. Innovations in nuclear technology for a sustainable future; 16. Brazilian national meeting on reactor physics and thermal hydraulics; 9. Brazilian national meeting on nuclear applications; 1. Meeting on nuclear industry
- Acronym
- INAC 2009
- Dates
- 27 Sep - 2 Oct 2009
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 41115770
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ALGORITHMS; ANGRA-1 REACTOR; CHROMOSOMES; COMPUTERIZED SIMULATION; EXPERIMENTAL DATA; FUEL MANAGEMENT; GENETICS; OPTIMIZATION; R CODES; REACTOR CORES; RELOADABLE FUEL ASSEMBLIES
- Descriptors DEC
- BIOLOGY; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; INFORMATION; MANAGEMENT; MATHEMATICAL LOGIC; NUCLEAR MATERIALS MANAGEMENT; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Published only in CD-Rom. Code: r17_500_fullpaper.pdf