ITER structural design criteria and their extension to advanced fusion reactor blankets [electronic resource].

Published:: Washington, D.C. : United States. Dept. of Energy, 1999.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: 17 pages : digital, PDF file
Additional Creators:: Argonne National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

Application of the new low-temperature-design rules of the ITER Structural Design Criteria (ISDC) is illustrated by considering copper alloys that, according to recent data, are particularly prone to irradiation embrittlement at relatively low fluences at certain temperatures, Allowable stresses are derived and the impact of the embrittlement on allowable surface heat flux of a simple first-wall/limiter design is demonstrated. High-temperature-design rules of ISDC are applied to EVOLVE (Evaporation Of Lithium and Vapor Extraction), a blanket design concept currently being investigated under the U.S. APEX (Advanced Power Extraction) program. One version of this concept envisions the use of a series of parallel tungsten tubes (first-wall) that are cooled internally by lithium vapor, typically. at 1200 C. A single tungsten first-wall tube is considered for thermal and stress analyses by finite-element method.

Report Numbers:

E 1.99:anl/td/cp-99404
anl/td/cp-99404

Subject(s):

Materials Science

Other Subject(s):

Note:

Published through SciTech Connect.
09/03/1999.
"anl/td/cp-99404"
ICFRM (9th International Conference on Fusion Reactor Materials), Colorado Springs, CO (US), 10/10/1999--10/15/1999.
Majumdar, S.; Kalnin, G.

Funding Information:

W-31109-ENG-38

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