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Abstract

The similar poloidal patterns of divertor erosion and redeposition of the ASDEX Upgrade, DIII-D and JET tokamaks are examined by comparing hydrogen isotope retention at the surfaces of divertor tiles. The outer divertor strike point undergoes net erosion. The inner divertor is a region of net redeposition, with deuterium co-deposition rates for all three devices; despite their differences in geometry, size and plasma facing material. This extrapolates to an unacceptably high tritium retention rate in a DT burning steady state tokamak

Additional information

Authors: MAX-PLANCK-INSTITUT FUR PLASMAPHYSIK, ;GARCHING BEI MUNCHEN (DE),
Bibliographic Reference: Article: Nuclear Fusion, 39 (1999) 8, 1025-1029
Record Number: 199911310 / Last updated on: 1999-09-03
Category: PUBLICATION
Original language: en
Available languages: en
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