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3.10 FRAMATOME Research Areas in Reactor Thermalhydraulics

DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.360
pages 585-592

J. Noailly
Core Thermalhydraulics, FRAMATOME, France

要約

The principal areas of FRAMATOME on going research in the field of the reactor thermalhydraulics may be categorized as :

  • core design
  • tests related to hypothetical accidents and the effectiveness of engineered safeguard features
  • safety design of the vessel internals and piping supports
We do not intend in this paper to cover and detail all the experimental and analytical studies undertaken by Framatome in thermalhydraulics. We will only focus on the following selected research topics corresponding to the main previously mentioned areas :
  • critical flux, pressure and flow core boundaries,
  • stratified flow tests and steam generator behavior with primary side boiling to substantiate our knowledge of small break loss of coolant accident
  • hydraulic loads on piping supports.
These examples illustrate the subjects of interest of a PWR manufacturer as far as thermalhydraulics is concerned for reactor safety and design purposes.

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