Title of article
High heat flux testing of plasma facing materials and components – Status and perspectives for ITER related activities
Author/Authors
Linke، نويسنده , , J. and Escourbiac، نويسنده , , F. and Mazul، نويسنده , , I.V. and Nygren، نويسنده , , R. and Rِdig، نويسنده , , M. and Schlosser، نويسنده , , J. and Suzuki، نويسنده , , S.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2007
Pages
10
From page
1422
To page
1431
Abstract
A broad spectrum of high heat flux test facilities are being used worldwide to investigate the thermal response of plasma facing materials and components to fusion relevant thermal loads. These tests cover both normal operation scenarios with cyclic thermal loads and power densities in the range of several MW m−2 and transient heat load tests to simulate short events such as edge localized modes, plasma disruptions and vertical displacement events. There is an urgent need for reliable quality control methods and non-destructive analyses during the procurement phase of ITER; most of these techniques are based on heat flux methods. To quantify irradiation induced property changes and to evaluate the overall performance of neutron irradiated components, miniaturized plasma facing components have been irradiated in fission reactors and post-irradiation tested. Furthermore, in-pile tests have been carried out in order to study the synergetic effects of heat loads and neutron loads.
Journal title
Journal of Nuclear Materials
Serial Year
2007
Journal title
Journal of Nuclear Materials
Record number
1365802
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