ITER divertor design
Creators
- 1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Description
This paper reviews the status of ITER divertor design as described in the Interim Design Report. The ITER divertor must exhaust 300 MW alpha heating power and helium ash. It must also withstand huge loads of electromagnetic force and heat flux associated with disruption. The divertor should also be efficiently replaced with remote maintenance. Recent divertor experiments and modelling suggest that the radiative divertor approach may provide a feasible solution to the power and particle exhaust. Compatibility of radiative divertor with good confinement (H∼2) and high purity (Zeff∼1.5) is yet to be demonstrated, and the physics of high density limit remains to be a challenge. The present divertor design based on a cassette scheme is feasible with remote maintenance. Mechanical loads predicted presently are very demanding, but recent progress in VDE (Vertical Displacement Event) control in JT-60U may bring out drastic reduction of its frequency and consequence. (author)
Additional details
Publishing Information
- Journal Title
- Purazuma, Kaku Yugo Gakkai-Shi
- Journal Volume
- 72
- Journal Issue
- 9
- Journal Page Range
- p. 858-865.
- ISSN
- 0918-7928
- CODEN
- PKYGE5
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28016725
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- ALPHA PARTICLES; DIVERTORS; HEAT FLUX; HELIUM ASH; ITER TOKAMAK; RADIANT HEAT TRANSFER; RADIATIVE COOLING; SPECIFICATIONS; THERMONUCLEAR REACTOR MATERIALS; WALL EFFECTS
- Descriptors DEC
- CHARGED PARTICLES; CLOSED PLASMA DEVICES; COOLING; ENERGY TRANSFER; HEAT TRANSFER; HELIUM IONS; IONIZING RADIATIONS; IONS; MATERIALS; RADIATIONS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS