Heat removal by the divertor plate and limiter materials in fusion reactors
- 1 June 1993
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 202 (1-2) , 1-9
- https://doi.org/10.1016/0022-3115(93)90023-r
Abstract
No abstract availableKeywords
This publication has 15 references indexed in Scilit:
- Effects of short pulse high heat fluxes on carbon base plasma facing materials for ITERJournal of Nuclear Materials, 1992
- Optimising X-point target platesJournal of Nuclear Materials, 1992
- The effect of ELMs on edge plasma scaling in DIII-DJournal of Nuclear Materials, 1992
- Summary of ITER panel discussionsJournal of Nuclear Materials, 1992
- Resistance of carbon-based materials for the ITER divertor under different radiation fluxesJournal of Nuclear Materials, 1992
- Temperature-dependent sputtering of doped graphites and boron carbideJournal of Nuclear Materials, 1992
- Simulation and analysis of the response of carbon materials to off-normal heat loads accompanying plasma disruptionsJournal of Nuclear Materials, 1991
- Edge plasma and surface conditions in ITERJournal of Nuclear Materials, 1990
- Scaling laws for thermal behavior of inertially cooled limiters allowing for temperature-dependent material propertiesJournal of Nuclear Materials, 1982
- Evaporation for heat pulses on Ni, Mo, W and ATJ graphite as first wall materialsJournal of Nuclear Materials, 1980