Community Research and Development Information Service - CORDIS

Abstract

The main options for the control of the power exhaust, plasma - wall interactions and impurities in TORE SUPRA are: 1. A complete water cooled first wall for long operation (30 s) at 250 degrees c during baking plasma heating operations and 15 MW of radiated power load on the inner chamber of 80 m**2. 2. (a) Six conventional poloidal limiters covered with low-Z materials (graphite) bolted or brazed on the cooling pipes which are designed to handle up to 200 W/cm**2 of thermal flux and 8 MW of total power. (b) A low-Z material wall located 3 cm behind the main limiter radius to sustain a thermal load of 50 to 100 W/cm**2. This wall includes thermal shields facing the neutral injectors and protectors for inner RF antennae. 3. The recycling of impurities and the plasma density during the neutral injection are controlled by two sections of moving and pumped limiters with a pumping plasma core. Reduction of the impurity influx is envisaged by the use of three sets of ergodic divertors, located in the outer part of the torus. The use of an ergodic divertor could increase the boundary layer thickness, decrease the plasma edge temperature at the wall and drag the impurities back to the wall through a large-scale hydrogen recycling.

Additional information

Authors: DESCHAMPS P, CEA, FONTENAY-AUX-ROSES (FRANCE);GROSMAN A, CEA, FONTENAY-AUX-ROSES (FRANCE);LIPA M, CEA, FONTENAY-AUX-ROSES (FRANCE);SAMAIN A CEA, FONTENAY-AUX-ROSES (FRANCE), CEA, FONTENAY-AUX-ROSES (FRANCE)
Bibliographic Reference: JOURNAL OF NUCLEAR MATERIALS, VOL. 128&129 (1984), PP. 38-47
Record Number: 1989123044700 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en