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Abstract

Thermal hydraulic tests were carried out in collaboration between NET, CEA Cadarache and JET in order to find a cooling method capable of removing the high heat fluxes expected for the NET/ITER divertor. The goal was to evaluate, by experiments, the critical heat flux (CHF) and heat transfer in the subcooled boiling regime using twisted tapes as turbulence promoters and testing them under relevant thermal-hydraulic conditions. The CEA 200 kW electron beam facility and the 10 MW JET neutral beam test bed were used to heat up the NET relevant test sections consisting of rectangular copper elements, with circular internal channels. The test sections were exposed to the electron or ion beams under normal incidence. This paper reports the results of the experiments and of thermal analyses performed in support of the tests. The experimental CHF values were benchmarked with the Tong-75 correlation.

Additional information

Authors: SCHLOSSER J, CEA, CEN Cadarache, Saint-Paul-lez-Durance (FR);DESCHAMPS P, CEA, CEN Cadarache, Saint-Paul-lez-Durance (FR);CHAPPUIS P, CEA, CEN Cadarache, Saint-Paul-lez-Durance (FR);CARDELLA A, NET TEAM, Garching (DE);MASSMANN P, JET Joint Undertaking, Abingdon, Oxon. (GB);FALTER H D, JET Joint Undertaking, Abingdon, Oxon. (GB);DESCHAMPS G H, JET Joint Undertaking, Abingdon, Oxon. (GB)
Bibliographic Reference: Report: EUR-CEA-FC-1450 EN (1992) 20 pp.
Availability: Available from CEA, Département de Recherches sur la Fusion Contrôlée, Saint-Paul-lez-Durance (FR)
Record Number: 199211216 / Last updated on: 1994-11-29
Category: PUBLICATION
Original language: en
Available languages: en
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