• DocumentCode
    3142964
  • Title

    Use of Meta-Heuristics for Design of Fuel Loading Pattern in Light Water Reactors Comprising Some Radial and Axial Heterogeneities

  • Author

    Do, J.-M. ; Lautard, J.-J. ; Baudron, A.-M. ; Douce, S. ; Gilles, A.

  • Author_Institution
    DEN/DM2S/SERMA, CEA Saclay, Saclay, France
  • fYear
    2011
  • fDate
    16-20 May 2011
  • Firstpage
    374
  • Lastpage
    380
  • Abstract
    The third generation nuclear core should be attractive from the nuclear fuel cycle management aspect. The main goal is to achieve a good conversion of fertile isotopes into fissile isotopes while respecting safety constraints. Preliminary studies have shown the interest of the core loaded with fertile and heterogeneous fissile assemblies. The purpose of this work is to find out an optimized loading pattern and axial repartition of fissile and fertile elements in regards to the following criteria: power peak and void coefficient minimization. Due to the huge number of possible combinations, we have replaced the global optimization by two simple forms: first optimization of the fertile / fissile repartitions on an assembly in 1D representation, and secondly optimization of the core\´s loading pattern in 3D representation. The evaluations of the criteria have been done using the neutron physics transport solver MINOS integrated in the new lattice-core APOLLO3 code. The research algorithms used in this study are of an evolutionary algorithm, a "Max Min ant system colony algorithm" and a particle swarm adapted to our multi criteria approach. These algorithms are distributed using the heterogeneous island\´s method. A second level of parallelism has been introduced inside each island. Therefore we could increase the number of evaluations while respecting the CPU time limitation of the batch queues available. There are several solutions that stand out from the simulations. Some of them are completely original and have proved to be relevant a posteriori. This method could then be used as a decision support tool for the exploitation reactors and also for the design of new reactors.
  • Keywords
    fission reactor design; fission reactor fuel; fission reactor safety; minimax techniques; nuclear engineering computing; parallel processing; particle swarm optimisation; APOLLO3 lattice-core code; MINOS neutron physics transport solver; evolutionary algorithm; fertile fissile assembly; fertile isotope; fissile isotope; fuel loading pattern design; heterogeneous island method; light water reactor; max-min ant system colony algorithm; nuclear fuel cycle management; particle swarm algorithm; power peak minimization; safety constraint; third generation nuclear core; void coefficient minimization; Assembly; Fuels; Genetics; Loading; Materials; Neutrons; Optimization;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Parallel and Distributed Processing Workshops and Phd Forum (IPDPSW), 2011 IEEE International Symposium on
  • Conference_Location
    Shanghai
  • ISSN
    1530-2075
  • Print_ISBN
    978-1-61284-425-1
  • Electronic_ISBN
    1530-2075
  • Type

    conf

  • DOI
    10.1109/IPDPS.2011.175
  • Filename
    6008854