Assessment of a heat transfer correlations package for water-cooled plasma-facing components in fusion reactors
| Autor: | A. Cardella, S.T. Yin, Z. Jin, A.H Abdelmessih, B.P. Bromley |
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| Rok vydání: | 1994 |
| Předmět: |
Nuclear and High Energy Physics
Engineering Tokamak business.industry Mechanical Engineering Nuclear engineering Divertor Mechanical engineering Plasma Fusion power law.invention Coolant Subcooling Nuclear Energy and Engineering law Heat transfer Thermal General Materials Science Safety Risk Reliability and Quality business Waste Management and Disposal |
| Zdroj: | Nuclear Engineering and Design. 146:311-323 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/0029-5493(94)90338-7 |
| Popis: | 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. |
| Databáze: | OpenAIRE |
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