The Monte Carlo Simulation of Thermal Noise in Fast Reactors

  • G. Hughes
  • R. S. Overton


A safety concern for fast reactors is the possibility that a local flow blockage in a fuel pin bundle could lead to a more serious fault because of the high power density in the core. Experimental studies carried out in a number of countries (Weinkoetz, Krebs & Martin, 1982; Girard & Buravand, 1982; Firth & Conroy, 1986; Overton, Wey & Hughes, 1984) indicate that the monitoring of temperature fluctuations near the outlet of a fuel subassembly is one of the most sensitive ways of detecting a local flow blockage. These have been supported by theoretical modelling (Krebs & Bremhorst, 1983; Firth, 1977). In particular, a Monte Carlo computer program, STATEN, has been developed in the UK by the CEGB (Overton, Wey & Hughes, 1984; Hughes, Overton & Wey, 1986), and used to model the temperature fields in the outlet regions of reactor subassemblies under normal and fault conditions. This paper outlines the development and validation of the code and illustrates its use for the development of detection algorithms based on pattern recognition methods. In addition the modelling of the Superphenix-1 reactor at Creys-Malville, performed under the European Fast Reactor Agreement (Girard et al., 1987) is used to illustrate the comparison of its predictions against good experimental measurements.


Turbulence Intensity Radial Position Temperature Noise Pattern Recognition Method Outlet Region 
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Copyright information

© Plenum Press, New York 1989

Authors and Affiliations

  • G. Hughes
    • 1
  • R. S. Overton
    • 1
  1. 1.Central Electricity Generating BoardBerkeley Nuclear LaboratoriesBerkeley, GlosUK

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