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| 001 | 834316 | ||
| 005 | 20240711114045.0 | ||
| 024 | 7 | _ | |a tecpub:2456 |2 tecpub |
| 024 | 7 | _ | |a 10.1088/1741-4326/aa4feb |2 doi |
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| 037 | _ | _ | |a FZJ-2017-04295 |
| 082 | _ | _ | |a 530 |
| 100 | 1 | _ | |a Linsmeier, Ch. |0 P:(DE-Juel1)157640 |b 0 |e Corresponding author |u fzj |
| 245 | _ | _ | |a Material testing facilities and programs for PFC testing |
| 260 | _ | _ | |a Vienna |c 2017 |b IAEA |
| 336 | 7 | _ | |a article |2 DRIVER |
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| 336 | 7 | _ | |a Journal Article |0 0 |2 EndNote |
| 520 | _ | _ | |a Component development for operation in a large-scale fusion device requires thorough testing and qualification for the intended operational conditions. In particular environments are necessary which are comparable to the real operation conditions, allowing at the same time for in situ/in vacuo diagnostics and flexible operation, even beyond design limits during the testing. Various electron and neutral particle devices provide the capabilities for high heat load tests, suited for material samples and components from lab-scale dimensions up to full-size parts, containing toxic materials like beryllium, and being activated by neutron irradiation. To simulate the conditions specific to a fusion plasma both at the first wall and in the divertor of fusion devices, linear plasma devices allow for a test of erosion and hydrogen isotope recycling behavior under well-defined and controlled conditions. Finally, the complex conditions in a fusion device (including the effects caused by magnetic fields) are exploited for component and material tests by exposing test mock-ups or material samples to a fusion plasma by manipulator systems. They allow for easy exchange of test pieces in a tokamak or stellarator device, without opening the vessel. Such a chain of test devices and qualification procedures is required for the development of plasma-facing components which then can be successfully operated in future fusion power devices. The various available as well as newly planned devices and test stands, together with their specific capabilities, are presented in this manuscript. Results from experimental programs on test facilities illustrate their significance for the qualification of plasma-facing materials and components. An extended set of references provides access to the current status of material and component testing capabilities in the international fusion programs |
| 536 | _ | _ | |a 113 - Methods and Concepts for Material Development (POF3-113) |0 G:(DE-HGF)POF3-113 |c POF3-113 |f POF III |x 0 |
| 588 | _ | _ | |a Dataset connected to tecpub |
| 700 | 1 | _ | |a Unterberg, B. |0 P:(DE-Juel1)6784 |b 1 |u fzj |
| 700 | 1 | _ | |a Coenen, J. W. |0 P:(DE-Juel1)2594 |b 2 |u fzj |
| 700 | 1 | _ | |a Doerner, R. P. |0 P:(DE-HGF)0 |b 3 |
| 700 | 1 | _ | |a Greuner, H. |0 P:(DE-HGF)0 |b 4 |
| 700 | 1 | _ | |a Kreter, A. |0 P:(DE-Juel1)130070 |b 5 |u fzj |
| 700 | 1 | _ | |a Linke, J. |0 P:(DE-Juel1)129747 |b 6 |u fzj |
| 700 | 1 | _ | |a Maier, H. |0 P:(DE-HGF)0 |b 7 |
| 773 | _ | _ | |a 10.1088/1741-4326/aa4feb |0 PERI:(DE-600)2037980-8 |p 092012 |t Nuclear fusion |v 57(9) |y 2017 |x 0029-5515 |
| 856 | 4 | _ | |y OpenAccess |u https://juser.fz-juelich.de/record/834316/files/Linsmeier_2017_Nucl._Fusion_57_092012.pdf |
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