Title of article
Overview of goals and performance of ITER and strategy for plasma–wall interaction investigation
Author/Authors
Shimada، نويسنده , , M. and Costley، نويسنده , , A.E. and Federici، نويسنده , , G. and Ioki، نويسنده , , K. and Kukushkin، نويسنده , , A.S. and Mukhovatov، نويسنده , , V. and Polevoi، نويسنده , , A. and Sugihara، نويسنده , , M.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2005
Pages
8
From page
808
To page
815
Abstract
Recent progress in experiments, modeling and theory has increased confidence that ITER can achieve its goal of high Q (>10) in inductive operation. Further, experimental results in the ‘improved hybrid’ regime suggest a possibility of high Q (>10) operation in a long pulse (>1000 s) with benign ELMs. However, considerable uncertainty still exists in the prediction of several key aspects; for example, tritium retention, disruption, impurity control, ELMs, SOL transport and dust. ITER requires flexibility of operation scenarios at least in the early operation phase to accommodate uncertainties in prediction, to explore wide operational spaces and to incorporate newly developed control schemes. Because of these uncertainties conservative assumptions are adopted in performance predictions, and step-wise implementation of reactor-relevant plasma-facing material, such as tungsten, are planned.
Keywords
Disruption , Impurity transport , ELM control , Tritium retention , ITER
Journal title
Journal of Nuclear Materials
Serial Year
2005
Journal title
Journal of Nuclear Materials
Record number
1362025
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