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LIBS experiments for quantitative detection of retained fuel
Author(s) -
F. Colao,
S. Almaviva,
Luisa Caneve,
G. Maddaluno,
T. Fornal,
P. Gąsior,
M. Kubkowska,
M. Rosiński
Publication year - 2017
Publication title -
nuclear materials and energy
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 1.324
H-Index - 25
ISSN - 2352-1791
DOI - 10.1016/j.nme.2017.05.010
Subject(s) - laser induced breakdown spectroscopy , tokamak , deuterium , materials science , vaporization , atomic emission spectroscopy , analytical chemistry (journal) , spectrometer , impurity , resolution (logic) , plasma , laser , spectroscopy , chemistry , optics , nuclear physics , inductively coupled plasma , chromatography , artificial intelligence , quantum mechanics , physics , computer science , organic chemistry
Laser Induced Breakdown Spectroscopy (LIBS) provides chemical information from atomic and ionic plasma emissions generated by laser vaporization of a sample. At the ENEA research center, in collaboration with IPPLM, an equipment has been set up to qualitatively and quantitatively determine the chemical composition of impurities deposited on Plasma Facing Components (PFC). The strength of the LIBS, for its capability of light elements detection, is fully exploited to determine the deuterium content since this element can be considered as the best choice proxy for tritium; the latter being is of great importance in assessing safe conditions to assure the continuous operation in nuclear fusion tokamak.Here we present the results of the Double Pulse LIBS (DP-LIBS) probing of deuterated samples with the simultaneous optical detection by medium-resolution and high-resolution spectrometer. Deuterium emission at 656.1nm has been detected then the elemental composition has been quantified by applying the Calibration Free (CF) approach. The obtained results demonstrate that the DP-LIBS technique combined with CF analysis is suitable for the quantitative determination of tritium content inside the PFCs of next fusion devices like ITER

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