The key to ITER : The divertor and the first wallFunded under: FP2-FUSION 10C
Present experimental results and model predictions suggest that impurity dilution is a major threat to a reactor. The divertor concept for impurity control, plasma fuelling and helium ash exhaust needs to be developed further. The operating domain of a tokamak that uses a particular divertor concept must be demonstrated for both normal and abnormal conditions, for example, when MHD events or runaway electrons release energy over a short period of time. The cooling of plasma facing components in the divertor, and more generally in the first wall and blanket, also raises questions, particularly over the choice of a coolant that complies with the safety regulations. Since the flux of 14 MeV neutrons will be about 1-3 MW/m2 and the power flux at the divertor plate will be about 5 MW/m2, an efficient cooling system is essential for the operation of the device. These questions are reviewed in the context of ITER and directions for future research and development work and concept development are indicated.
Bibliographic Reference: Report: JET-P(93)06 EN (1993) 21 pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
Record Number: 199310599 / Last updated on: 1994-11-29
Original language: en
Available languages: en