Spatial analysis of impurities on the surface of flange and optical window of the tokamak using laser induced breakdown spectroscopy
Introduction
Laser-induced breakdown spectroscopy (LIBS) is a very popular technique from the last decades due to its numerous advantages described in several books [1], [2] and research articles [3], [4], [5]. In nanosecond laser, the laser pulse vanishes within 10–20 ns and within the first 100 ns the LIBS spectra of ablated material are dominated by continuum radiation [6]. But after 1 μs delay, their characteristic spectral emission lines start appearing and therefore the light detection should be delayed to improve signal to background ratio. This timing known as gate delay changes with different target materials and laser properties (power density and wavelength of the laser) [5]. Due to its unique properties, LIBS is a potential tool for in-situ and real-time analysis of the plants, bio- and nuclear material [7], [8], [9], [10], [11].
Aditya tokamak is a moderate field and the first indigenously built medium size non-superconducting tokamak capable of producing 250 kA of plasma current with 300 ms of flattop duration. Its working fuel gas is hydrogen at pressure 1.06×10-4–1.33×10-4 hPa. It was designed, fabricated, erected and commissioned at the Institute for Plasma Research, Bhat, Gandhinagar (IPR) [12]. In the tokamak like International Thermonuclear Experimental Reactor (ITER), LIBS has been started as a potential diagnostic tool for characterization of the wall conditions which is performed under ultrahigh vacuum conditions and the toroidal magnetic field [5]. The LIBS has also been used for identification of impurities in Aditya tokamak [13]. In the present study, we have taken the optical window and the flange samples for studying spatial distribution of impurity materials on their surfaces. In the tokamak due to plasma–wall interaction, a small amount material from the plasma facing components is eroded and re-deposited at relatively cooler area/parts of the vacuum vessel in the form of a thin layer. To increase the lifetime and maintain the optical components ready for further study, it is desirable to identify these deposited impurities. Because of long term contamination, the lifetime of optical components unprotected from reactor grade plasmas will be very short [14]. In addition to this, the visibility of the optical window and other optical parts decreases due to deposition of thin film [15], [16]. Mirrors and optical windows are essential components in spectroscopy and imaging systems both in industrial instruments for plasma processing and in controlled thermonuclear fusion devices (e.g., tokamak) [14], [17], [18], [19]. In the last couple of years, work has been initiated in our laboratory. In the present manuscript, an attempt has been made to identify the impurities spatially distributed on the surface of optical window and flange using the LIBS technique.
Section snippets
Material and method
The contaminated optical window and flange of Aditya tokamak are used as samples and the photograph of their exposed surfaces can be seen in Fig. 1a and b respectively. The experimental arrangement to record the LIBS spectra of tokamak optical window and flange described in our previous work [6], [20] is shown in Fig. 2. It consists of a laser source, which is a frequency-doubled (532 nm) Nd:YAG laser (Continuum Surelite III-10) capable of delivering maximum energy of 425 mJ with pulse width 4 ns
Results and discussion
As the Aditya tokamak is constructed from stainless steel (SS316L material), a small amount of this material is eroded due to plasma–wall interaction. When the tokamak plasma comes in contact with its other cooler parts such as optical window, flange, and mirror, the eroded impurity elements get deposited on their surfaces.
Conclusion
The present manuscript clearly reveals the presence of impurities like Fe, Ni, Cr, Mo, Mn, Cu and C [which are the constituents of tokamak vacuum vessel wall material (SS316L)] on the exposed surface of the tokamak flange as well as optical window. It further demonstrates the capability of LIBS for in-situ study of spatial distribution of deposited material in the form of thin film on the surface of the flange and optical window. The variation of spectral intensity with radial distance from the
Acknowledgment
The Board of Research in Fusion Science and Technology (BRFST)Institute for Plasma Research, Gandhinagar, Gujarat, India, are gratefully acknowledged for financial assistance. We are thankful to Mr. Rohit Kumar for his help and valuable suggestions. Authors Mr. Gulab Singh Maurya and Ms. Aradhana Jyotsana acknowledge BRFST (NFP-DIAG-F11-03) for providing financial assistance as JRF.
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A review of the LIBS analysis for the plasma-facing components diagnostics
2020, Journal of Nuclear MaterialsCitation Excerpt :Maurya et al. [23-25, 63, 95], have performed a LIBS study of an optical window, flange, and limiter of the Aditya tokamak. The same plasma contaminated all the PFCs of the Aditya tokamak, and hence the impurity elements identified were the same i.e., Fe, Ni, Cr, Mo, Mn, Cu, and C [23-25, 63, 95]. The limiter of the Aditya tokamak is made up of graphite, and the PWI contaminates its surface, therefore its surface contains spectral intensities of C along with impurity elements Fe, Ni, Cr, Mo, Mn, Cu, Ca, and Mg.
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2016, Kexue Tongbao/Chinese Science BulletinAtomic spectrometry update. Review of advances in the analysis of metals, chemicals and functional materials
2014, Journal of Analytical Atomic Spectrometry