This title appears in the Scientific Report :
2000
Please use the identifier:
http://dx.doi.org/10.1016/S0022-3115(00)00292-0 in citations.
Neutron-irradiation effects on high heat flux components - examination of plasma-facing materials and their joints
Neutron-irradiation effects on high heat flux components - examination of plasma-facing materials and their joints
The neutron-irradiation experiments PARIDE 1 and PARIDE 2 have been performed at 350 degreesC and 700 degreesC with fluences of 0.35 dpa. The major part of the post-irradiation tests are high heat flux simulation experiments carried out in the electron beam facility JUDITH. These tests cover thermal...
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Personal Name(s): | Rödig, S. E. |
---|---|
Conrad, R. / Derz, H. / Duwe, R. / Linke, J. / Lodato, A. / Merola, M. / Pott, G. / Vieider, G. / Wiechers, B. | |
Contributing Institute: |
Institut für Werkstoffe und Verfahren der Energietechnik; IWV |
Published in: | Journal of nuclear materials, 283-287 (2000) S. 1161 - 1165 |
Imprint: |
Amsterdam [u.a.]
Elsevier Science
2000
|
Physical Description: |
1161 - 1165 |
DOI: |
10.1016/S0022-3115(00)00292-0 |
Document Type: |
Journal Article |
Research Program: |
Verbundwerkstoffe für thermisch hoch beanspruchte Komponenten |
Series Title: |
Journal of Nuclear Materials
283-287 |
Subject (ZB): | |
Publikationsportal JuSER |
The neutron-irradiation experiments PARIDE 1 and PARIDE 2 have been performed at 350 degreesC and 700 degreesC with fluences of 0.35 dpa. The major part of the post-irradiation tests are high heat flux simulation experiments carried out in the electron beam facility JUDITH. These tests cover thermal fatigue experiments with small-scale high heat flux components, and on the other hand, thermal shock tests on the plasma-facing materials. Actively cooled samples were made from CFC, or beryllium as plasma-facing materials and copper alloys as heat sink materials. Different designs (flat tile, monoblock) and joining techniques (brazing, welding) were used. Best performance was found for CFC/Cu monoblock mock-ups, but also the brazed Be/Cu hat tile mock-ups fulfill the operational requirements for first wall components. Thermal shock experiments show a higher erosion after neutron irradiation. This degradation is either due to a reduced thermal conductivity (carbon) or to a decreased ductility after irradiation (beryllium). (C) 2000 Elsevier Science B.V. All rights reserved. |