Development of an accelerator-based diagnostic for plasma-facing surfaces in magnetic confinement devices
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
The focus of this work was the development of the Accelerator-based In-situ Material Surveillance (AIMS) diagnostic. The understanding of plasma-material interaction processes in fusion devices has been greatly hampered by the lack of ability to measure the surface ~micron layers of solid surfaces that are in contact with and greatly modified by the boundary fusion plasma. AIMS was the first diagnostic developed and deployed that allowed non-destructive surface measurements with adequate spatial and time resolution. The deployment was primarily carried out on the Alcator C-Mod tokamak. AIMS diagnostic goal is to remotely generate isotopic concentration maps on a plasma shot-to-shot timescale that cover a large fraction of the plasma-facing surface inside of a magnetic fusion device without the need for vacuum breaks or physical access to the material surfaces. The diagnostic used a compact (~ 1 m), high-current (~ 1 milliamp) radio-frequency quadrupole accelerator to inject 0.9 MeV deuterons into the Alcator C-Mod tokamak. The tokamak magnetic fields were controlled – in between plasma shots – to steer the deuterons to material surfaces where the deuterons cause high-Q nuclear reactions with low-Z isotopes up to 5 microns into the material. The induced neutrons and gamma rays are measured with scintillation detectors; energy spectra analysis provides quantitative reconstruction of surface compositions. Experimental validation showed that low-Z isotopes such as deuterium and boron can be quantified on the material surfaces, and that magnetic steering provides access to different measurement locations. AIMS measurements of D retention on inner wall PFCs were acquired during diverted and limited plasma operations and during wall conditioning experiments om Alcator C-Mod. Intershot measurements demonstrate the local erosion and co-deposition of boron films on PFC surfaces with a constant D-B ratio. This is consistent with previous results suggesting that D co-=deposition with boron is insufficient to account for the net retention observed in Alcator C-Mod. Changes in deuterium concentration during boronization, electron cyclotron and glow cleanings were also measured. These initial results were limited to studying low-Z surface properties, because the Coulomb barrier precludes nuclear reactions between high-Z elements and the ~1 MeV AIMS deuteron beam. In order to measure the high-Z erosion of interest in Alcator C-Mod and future fusion devices, a new technique using deuteron-induced gamma emission and a low-Z depth marker was developed using implanted depth markers as a method of measuring bulk erosion and redeposition. This method is dubbed DEA: Depth marker Erosion with AIMS. DEA simulations and experiments were used to validate this technique, both in the laboratory and via experiments in the EAST tokamak. Based on these results, the DEA technique, using ion beam implanted depth markers as a reference to the surface in order to monitor surfaces for erosion and redeposition, is a viable option as a diagnostic, both in and ex situ. These markers show stability to temperature, the tokamak environment, and multiple probing beams. The ex-situ (eDEA) method, which uses resonances in the cross sections of gamma producing reactions to track the surface, was used to successfully measure erosion in samples that were exposed in the EAST tokamak. The in-situ (iDEA) method, which uses the gamma yield ratio to monitor changes to the surface, was used to differentiate between markers implanted to different depths. Both techniques were successfully simulated, and both presented unique challenges experimentally and in data analysis. In particular, the eDEA probing beam was found to have energy variations leading to initial experimental uncertainty, and the iDEA gamma spectra had conflicting gamma peaks which make data analysis difficult. However, the end result is a promising framework for a diagnostic technique that supplements the abilities of AIMS and expands the possibilities of surface diagnostics in fusion devices. While the results of this work are overwhelmingly encouraging for further development of AIMS in general, and the DEA technique specifically, several areas require significant development before this diagnostic is as robust and widely applicable as a surface diagnostic ought to be. Recommended future work includes the development of a cross section/yield measurement database, erosion tests with secondary verification of results using a fiducial mark from a focused ion beam, and acquiring a new accelerator with a more reliable high energy proton and deuterium beam The project resulted in 14 publications, including the PhD theses of three MIT graduate students, cited in the included bibliography.
- Research Organization:
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
- Sponsoring Organization:
- USDOE Office of Environment, Health, Safety and Security (AU), Office of Nuclear Safety; USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- DOE Contract Number:
- SC0009833
- OSTI ID:
- 1760345
- Report Number(s):
- DOE-MIT-0009833; MIT #6927447; TRN: US2214844
- Country of Publication:
- United States
- Language:
- English
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