Autor: |
B. Böswirth, H. Greuner, S. Elgeti, T. Höschen, K. Hunger, H. Maier, R. Neu |
Jazyk: |
angličtina |
Rok vydání: |
2024 |
Předmět: |
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Zdroj: |
Nuclear Materials and Energy, Vol 38, Iss , Pp 101563- (2024) |
Druh dokumentu: |
article |
ISSN: |
2352-1791 |
DOI: |
10.1016/j.nme.2023.101563 |
Popis: |
Highly loaded divertor regions in fusion experiments are exposed to high particle and power fluxes. Therefore, tungsten with its excellent thermal and physical properties is a preferred plasma facing material for this application. For divertor areas with moderate steady-state heat flux up to 10 MW/m2 the excellent high-temperature resistance of W is not absolutely necessary. 95–97 % W heavy alloys containing Ni, Cu or Fe could be used from the aspects of plasma wall interaction and their thermomechanical properties. In this study we present results of thermo-mechanical characterisations like measurement of thermal conductivity and tensile tests at elevated temperatures as well as results of high heat flux performance tests at adiabatic and steady-state loading. Finally, we discuss results of deuterium retention measurements. |
Databáze: |
Directory of Open Access Journals |
Externí odkaz: |
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