Assessment of a heat transfer correlations package for water-cooled plasma-facing components in fusion reactors

Subcooled water at high velocity has been selected by the ITER and NET design teams as the coolant for the divertor plates in these new tokamak fusion reactors. This paper presents a thermalhydraulics package intended for the thermal design analysis of the plasma-facing components in these facilitie...

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Bibliographic Details
Published in:Nuclear engineering and design 1994-02, Vol.146 (1), p.311-323
Main Authors: Yin, S.T., Cardella, A., Abdelmessih, A.H., Jin, Z., Bromley, B.P.
Format: Article
Language:English
Subjects:
Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Installations for energy generation and conversion: thermal and electrical energy
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Summary:Subcooled water at high velocity has been selected by the ITER and NET design teams as the coolant for the divertor plates in these new tokamak fusion reactors. This paper presents a thermalhydraulics package intended for the thermal design analysis of the plasma-facing components in these facilities. The selection of heat transfer correlations was based on their performances against a bank of specially collected data bases. The results show that existing correlations for nuclear and process systems can be modified, with the aid of suitable data bases, to meet the interim design needs of these projects. Specific areas that require further validation and development are discussed.
ISSN:0029-5493
1872-759X
DOI:10.1016/0029-5493(94)90338-7