Heuristic rules embedded genetic algorithm for in-core fuel management optimization
Abstract (Summary)
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The objective of this study was to develop a unique methodology and a practical
tool for designing loading pattern (LP) and burnable poison (BP) pattern for a given
Pressurized Water Reactor (PWR) core. Because of the large number of possible
combinations for the fuel assembly (FA) loading in the core, the design of the core
configuration is a complex optimization problem. It requires finding an optimal FA
arrangement and BP placement in order to achieve maximum cycle length while
satisfying the safety constraints.
Genetic Algorithms (GA) have been already used to solve this problem for LP
optimization for both PWR and Boiling Water Reactor (BWR). The GA, which is a
stochastic method works with a group of solutions and uses random variables to make
decisions. Based on the theories of evaluation, the GA involves natural selection and
reproduction of the individuals in the population for the next generation. The GA works
by creating an initial population, evaluating it, and then improving the population by
using the evaluation operators.
To solve this optimization problem, a LP optimization package, GARCO (Genetic
Algorithm Reactor Code Optimization) code is developed in the framework of this thesis.
This code is applicable for all types of PWR cores having different geometries and
structures with an unlimited number of FA types in the inventory. To reach this goal, an
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innovative GA is developed by modifying the classical representation of the genotype. To
obtain the best result in a shorter time, not only the representation is changed but also the
algorithm is changed to use in-core fuel management heuristics rules. The improved GA
code was tested to demonstrate and verify the advantages of the new enhancements.
The developed methodology is explained in this thesis and preliminary results are
shown for the VVER-1000 reactor hexagonal geometry core and the TMI-1 PWR. The
improved GA code was tested to verify the advantages of new enhancements. The core
physics code used for VVER in this research is Moby-Dick, which was developed to
analyze the VVER by SKODA Inc. The SIMULATE-3 code, which is an advanced twogroup
nodal code, is used to analyze the TMI-1.
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Bibliographical Information:
Advisor:
School:Pennsylvania State University
School Location:USA - Pennsylvania
Source Type:Master's Thesis
Keywords:
ISBN:
Date of Publication: