Advanced Course in Heat Transfer in Nuclear Reactor Safety
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf
ISBN Print: 978-0-89116-223-0
3.10 FRAMATOME Research Areas in Reactor Thermalhydraulics
pages 585-592
DOI: 10.1615/ICHMT.1982.AdvCourHeatTransfNucReactSaf.360
ABSTRAKT
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
- 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.