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10-15 May 2021
Virtual Event
Europe/Vienna timezone
The Conference will be held virtually from 10-15 May 2021

In situ Study of Fuel Retention by Laser-Induced Breakdown Spectroscopy on the First Wall under Long-Pulse Operation of Experimental Advanced Superconducting Tokamak

11 May 2021, 14:00
4h 45m
Virtual Event

Virtual Event

Regular Poster Magnetic Fusion Experiments P2 Posters 2


Dr Cong Li (Dalian University of Technology)


Plasma-wall interaction (PWI) processes are important in long-pulse plasma operation of fusion devices due to the main issues of increased fuel retention, material erosion and redeposition which are induced by a large increase in particle fluence to the wall compared to present experiments. The in situ approach is an urgent requirement to be utilized to real-time measure the fuel content on the first wall during the tokamak operation. Meanwhile, the characteristic of fuel retention during PWI processes is strongly linked to edge particle flux and fluence. Therefore, the key challenge for fuel retention studies is to monitor not only the elemental composition on the PFCs but also the local plasma condition during experimental processes in fusion device in situ and real-time. Experimental Advanced Superconducting Tokamak (EAST), which is the world’s first fully superconducting magnetic confinement facility with ITER-like magnetic field configuration, provides a unique platform to investigate the physical and engineering issues of PWI research for the next H-mode long-pulse fusion devices such as ITER and beyond. Laser-induced breakdown spectroscopy (LIBS) as a well-established elemental composition analysis method has been demonstrated as one of the most promising approaches for in situ PWI studies on the first wall of fusion devices [1,2]. The in situ LIBS system in EAST 3 provide information about the elemental composition of the first wall on the high-field side (HFS) near mid-plane in EAST. There is a need to address the link between the fuel retention on the first wall and local plasma conditions. For this purpose, an in situ LIBS system combined with optical emission spectroscopy (OES) is used to not only measure the fuel retention on the first wall but also simultaneously monitor the edge conditions during long-pulse discharges of EAST.

The in situ LIBS diagnosis system is located at the H-port, which is one of the 16 main horizontal ports along the toroid in EAST. The schematic of the system is illustrated in Fig. 1. The detail of the optical system can be found in our previous works 3. The intensity of D retention on the first can be achieved and analyzed by the spectrometer. During the EAST long-pulse plasma discharges, the spectrometer is also used for measuring the edge OES spectra for analyzing the local plasma conditions and providing the photon flux of the Dα line emission from the region of scrape off layer (SOL) and edge plasma. The typical spectra of LIBS from the TZM first wall and edge OES in EAST are shown in Fig. 2. The LIBS spectrum is measured after Li wall conditioning and D discharge using single pulse LIBS on the surface of the mid-plane TZM first wall. It clearly shows Li and Dα spectral lines from fuel retention as well as Mo I emission from the first wall substrate. The H content in the core discharge plasma is very low due to the Li wall conditioning, thus the fuel retention on the wall is dominated by D implantation and codeposition. The H content is lower than the limit of detection of the spectrometer at these experimental conditions. The lines of Li I, Li II and Dα are observed by edge OES measurement. Some spectral lines of Mo impurity due to first wall erosion may be observed in some cases of edge localized modes burst or fast plasma shutdown. The spectral intensity ratio of Li II and Li I in the edge OES spectra is much higher than that in the LIBS spectra.

As shown in Fig. 3, the relationship between the edge OES Dα photons fluence and flux and LIBS Dα photons fluence from the unit area on the first wall could qualitatively reflects the correlation between the edge D particles fluence and D retention on the first wall. Five typical long-pulse operations (#73341, #73342, #73930, #73977, and #73978) with duration time from 20 s to 80 s are used to illustrate the correlation between the OES and LIBS measurements. The Dα photons fluxes from the SOL and edge plasma are from 2×10^21 photons/sm^2 to 8×1021 photons/sm^2 in five long-pulse plasma discharges. The edge Dα photons fluences are from 0.5×10^23 photons/m^2 to 4.0×10^23 photons/m^2. These result in that the Dα photons fluences from LIBS plasma on the D retention first wall are from 0.3×10^17 photons/m^2 to 1.2×10^17 photons/m^2. The Dα photons fluences from the first wall almost linearly increase as Dα photons fluence from OES. By calculating S/XB of the edge plasma and LIBS plasma, the edge D particle fluences and D retention amounts on the first wall are estimated from 0.67×10^24 m^-2 to 4.83×10^24 m^-2 and from 1.88×10^19 m^-2 to 5.59×10^19 m^-2, respectively. Thus, the correlation between the intensities of Dα from LIBS spectra on the first wall and the Dα intensity from the edge spectra is clearly demonstrated. This indicates that the D retention on the first wall strongly related to the edge D particles fluence. We conclude that the fuel retention on the HFS first wall is dominantly influenced by the local D particles implantation. The results could improve the understanding of fuel retention on the first wall in EAST and demonstrate the prospect of LIBS approach to in situ investigate PWI in the upcoming fusion device like ITER.

In the future, the fuel retention on the first wall as a function of the distance between HFS and LCFS will be studied to search for the features for the retention behavior in the transition from net erosion to net deposition zone. In addition, it is planned to use an endoscope system to upgrade and extend the LIBS and OES detectable area to the tungsten upper divertor region which is a strong PWI interaction zone. The wall Langmuir probe and infrared camera observation systems will be used to characterize the edge condition and wall surface temperature. Deposition and erosion in divertor zones will be in situ investigated using the upgrade LIBS system in EAST.

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1 V. Philipps et al, Development of laser-based techniques for in situ characterization of the first wall in ITER and future fusion devices, Nucl. Fusion 53, 093002 (2013).
2 C. Li et al, Review of LIBS application in nuclear fusion technology, Front. Phys. 11, 114214 (2016).
3 D. Zhao, C. Li et al, Remote in situ laser-induced breakdown spectroscopic approach for diagnosis of the plasma facing components on experimental advanced superconducting tokamak, Rev. Sci. Instrum. 89, 073501 (2018).

Country or International Organization China
Affiliation Dalian University of Technology

Primary author

Dr Cong Li (Dalian University of Technology)


Dr Dongye Zhao (Forschungszentrum Jülich - IEK-4) Dr Zhenhua Hu (Institute of Plasma Physics, Chinese Academy of Sciences) Ms Liying Sun (Dalian University of Technology) Dr Niels Gierse (Forschungszentrum Jülich GmbH) Dirk Nicolai (Forschungszentrum Jülich GmbH) Dr Ran Hai (Dalian University of Technology) Dr Ding Wu (Dalian University of Technology) Mr Huace Wu (Dalian University of Technology) Dr Fang Ding (Institute of Plasma Physics, Chinese Academy of Sciences) Prof. Guangnan Luo (Institute of Plasma Physics, Chinese Academy of Sciences) Sebastijan Brezinsek (Forschungszentrum Jülich) Prof. Christian Linsmeier (Forschungszentrum Jülich GmbH) Yunfeng Liang (Forschungszentrum Jülich GmbH, Germany) Prof. Hongbin Ding (Dalian University of Technology)

Presentation Materials