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Three-Dimensional Numerical Simulation of Flow and Heat Transport in High-Temperature Nuclear Reactors

In: High Performance Computing in Science and Engineering ’02

Author

Listed:
  • Sascha Becker

    (University of Stuttgart, Institute for Nuclear Technology and Energy Systems (IKE))

  • Eckart Laurien

    (University of Stuttgart, Institute for Nuclear Technology and Energy Systems (IKE))

Abstract

In next generation nuclear High-Temperature Reactors an annular nuclear core consisting of a central column of graphite spheres and a surrounding ring of fuel pebbles is employed. Due to the complex feeding and shutdown mechanisms three-dimensional effects of heat production, gas flow and heat transport may become important for safety analysis. To simulate flow and heat transport in the core and the surrounding graphite reflector a new code system based on CFX-4 has been developed and run on the NEC-SX4 and NEC-SX5 supercomputers. The simulations are performed with the Heterogeneous Model of porous media. The program has been verified by comparison with two-dimensional simulations of the HTR-MODUL using the well established thermal analysis code THERMIX. A sensitivity study of several models for pressure drop and heat transfer on a simplified model of an HTR-MODUL is performed. Additionally the influence of the variation of the volume porosity near walls on flow and heat transport is analysed. In order to demonstrate the simulation of three-dimensional effects the influence of a package of fuel pebbles located asymmetrically in the central column is investigated. A significant influence on the temperature distribution and the maximum temperature core is found.

Suggested Citation

  • Sascha Becker & Eckart Laurien, 2003. "Three-Dimensional Numerical Simulation of Flow and Heat Transport in High-Temperature Nuclear Reactors," Springer Books, in: Egon Krause & Willi Jäger (ed.), High Performance Computing in Science and Engineering ’02, pages 367-378, Springer.
  • Handle: RePEc:spr:sprchp:978-3-642-59354-3_30
    DOI: 10.1007/978-3-642-59354-3_30
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