Developing a futuristic multi-objective optimization of the fuel management problems for the nuclear research reactors
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A. Hedayat
Abstract
In this paper, at the same time, two separate objectives and two safety and operational constraints are chosen to optimize fuel reloading pattern of a Material Testing Reactor (MTR), independently and coherently. This is one of the most difficult type of engineering problems as a constrained, non-continuous, combinatorial, and fully multi-objective optimization problem. Decision space is a non-continuous multimodal space restricted by both of the combinatorial and safety constraints. A smart software application and a robust hybrid algorithm have been developed to get Pareto optimal set with respect to both of the economy of irradiating utilizations and nuclear safety based on the heuristic soft computing. The hybrid algorithm is composed of a fast and elitist Multi-Objective Genetic Algorithm (MOGA) and a fast fitness function evaluating system based on the semi-deep learning cascade feed forward Artificial Neural Networks (ANNs). The smart software is used to produce database automatically required for the ANN training and test data. It can be also used to revise data accurately, impose further irradiating benefits or Operating Limits and Conditions (OLCs), and to advise the reactor supervisor on the most desire pattern based on the smart searches and filtering. The results are highly promising. For more details, optimization results dominate conventional operating core parameters, significantly. Also chosen OLCs are protected. Furthermore, this is very good practice to reach a fully developed practical application of the complex soft computing for the nuclear fuel management problems.
© 2020 by Walter de Gruyter Berlin/Boston
Articles in the same Issue
- CONTENTS
- CALENDAR OF EVENTS · VERANSTALTUNGSKALENDER
- Verification of the stationary module of the ShIPR software system for modelling experiments of the ASTRA HTGR type critical facility
- Appraisal of new density coefficient on integrated-nanoparticles concrete in nuclear protection
- Comparison of back propagation network and radial basis function network in Departure from Nucleate Boiling Ratio (DNBR) calculation
- Developing a futuristic multi-objective optimization of the fuel management problems for the nuclear research reactors
- Sensitivity of the neutron multiplication factor to water ingress into a spent fuel cask
- Evaluation of single heated channel and subchannel modeling of a nuclear once through steam generator (OTSG)
- Note · Imprint
Articles in the same Issue
- CONTENTS
- CALENDAR OF EVENTS · VERANSTALTUNGSKALENDER
- Verification of the stationary module of the ShIPR software system for modelling experiments of the ASTRA HTGR type critical facility
- Appraisal of new density coefficient on integrated-nanoparticles concrete in nuclear protection
- Comparison of back propagation network and radial basis function network in Departure from Nucleate Boiling Ratio (DNBR) calculation
- Developing a futuristic multi-objective optimization of the fuel management problems for the nuclear research reactors
- Sensitivity of the neutron multiplication factor to water ingress into a spent fuel cask
- Evaluation of single heated channel and subchannel modeling of a nuclear once through steam generator (OTSG)
- Note · Imprint