14th IEEE/NPSS Symposium on Fusion Engineering : San Diego (USA), 30.9 - 3.10.1991 : Papers presented by DRFC/STIF
High heat flux plasma facing components are under development and experimental evaluation for operation during cycles of several hundred seconds. In Tore Supra, a large tokamak with a plasma nominal duration in excess of 30 seconds, solutions are tested that could be later applied to the NET/ITER tokamak, where peaked heat flux values of 15 MW/m2 on the divertor plates are foreseen. The proposed concept is a swirl square tube design protected with brazed CFC flat tiles. Development programmes and validation tests are presented and the test results are compared with calculations.
Bibliographic Reference: Report: EUR-CEA-FC-1435 EN (1992) 55 pp.
Availability: Available from CEA, Départment de Recherches sur la Fusion Contrôlée, Saint-Paul-lez Durance (FR)
Record Number: 199210858 / Last updated on: 1994-12-02
Original language: en
Available languages: en