Experimental Study of Thermal Crisis in Connection with Tokamak Reactor High Heat Flux Components
The results of an experimental research on high heat flux thermal crisis in forced convective subcooled water flow, under operative conditions of interest to the thermal-hydraulic design of TOKAMAK fusion reactors, are here reported. These experiments, carried out in the framework of a collaboration between the Nuclear Engineering Department of Palermo University and the National Institute of Thermal - Fluid Dynamics of the ENEA - Casaccia (Rome), were performed on the STAF (Scambio Termico Alti Flussi) water loop and consisted, essentially, in a high speed photographic study which enabled focusing several information on bubble characteristics and flow patterns taking place during the burnout phenomenology.
- Research Organization:
- Nuclear Engineering Department, University of Palermo, Palermo (IT); National Institute of Thermal - Fluid Dynamics, ENEA, Rome (IT); Nuclear Engineering Department and Energy Conversion, University La Sapienza, Rome (IT)
- Sponsoring Organization:
- None (US)
- OSTI ID:
- 784115
- Report Number(s):
- ISBN 1-56396-929-7; ISSN 0094-243X; CODEN APCPCS; ISBN 1-56396-929-7; ISSN 0094-243X; CODEN APCPCS; TRN: US0106063
- Resource Relation:
- Conference: Nuclear and Condensed Matter Physics: VI Regional CRRNSM Conference, Palermo (IT), 10/14/1999--10/15/1999; Other Information: PBD: 31 Dec 2000
- Country of Publication:
- United States
- Language:
- English
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