Application of a Tritium Imaging Plate Technique to Depth Profiling of Hydrogen in Metals and Determination of Hydrogen Diffusion Coefficients

Otsuka, Teppei; Tanabe, T.

doi:10.2320/matertrans.m2017175

Cited by 10 publications

(5 citation statements)

References 31 publications

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“…Imaging plate technique is based on tritium beta radiation interaction with radiosensitive material. Due to small beta radiation range in solid samples method gives information only on the near surface tritium [32].…”

Section: Tritium Measurement Methodsmentioning

confidence: 99%

Tritium in plasma-facing components of JET with the ITER-Like-Wall

et al. 2021

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The ITER-Like-Wall project has been carried out at the Joint European Torus (JET) to test plasma facing materials relevant to ITER. Materials being tested include both bulk metals (Be and W) and coatings. Tritium accumulation mechanisms and release properties depend both on the wall components, their location in the vacuum vessel, conditions of exposure to plasma and to the material itself. In this study, bulk beryllium limiter tiles, plasma-facing beryllium coated Inconel components from the main chamber, bulk tungsten and tungsten coated carbon fibre composite divertor tiles were analysed. A range of methods have been developed and applied in order to obtain a comprehensive overview on tritium retention and behaviour in different materials of plasma facing components (PFCs). Tritium content and chemical state were studied by the means of chemical or electrochemical dissolution methods and thermal desorption spectroscopy. Tritium distribution in the vacuum vessel and factors affecting its accumulation have been assessed and discussed.

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Section: Tritium Measurement Methodsmentioning

confidence: 99%

Tritium in plasma-facing components of JET with the ITER-Like-Wall

et al. 2021

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“…The advantage of using such substrate is a negligible intensity of background carbon, while most types of adhesive tapes used to attach samples for analysis include carbon [15]. Tritium retained in the dust particles was assessed by TIPT with the spatial resolution of 25 µm [16,17]. The emission of β --rays from T to the IP was measured over the whole surface of the In disc for 1 h at room temperature.…”

Section: Tritium Measurement In Dust By Tipt Combined With Sem/epmamentioning

confidence: 99%

Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall

Torikai,

Kikuchi,

Owada

et al. 2023

Nucl. Fusion

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Divertor tiles after JET-ILW campaigns and dust collected after JET-C and JET-ILW operation were examined by a set of complementary techniques (full combustion and radiography) to determine the total, specific and areal tritium activities, poloidal tritium distribution in the divertor and the presence of that isotope in individual dust particles. In the divertor tiles, the majority of tritium is detected in the surface region and, the areal activities in the ILW divertor are in the 0.5 – 12 kBq cm-2 range. The activity in the ILW dust is associated mainly with the presence of carbon particles being a legacy from the JET-C operation. The total tritium activities show significant differences between the JET operation with ILW and the earlier phase with the carbon wall (JET-C) indicating that tritium retention has been significantly decreased in the operation with ILW.

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“…To perform the combined TIPT with EPMA [10] for examination of T in individual particles, a small dust sample was placed in a disk made of indium (In) [11]. Distribution of the T intensity and elemental composition in dust particles was evaluated by TIPT [12,13] and EPMA, respectively, in the same area of the In disk surface, and with the same spatial resolution of 25 μm. T intensity was defined as intensity of Photo-Stimulated Luminescence (PSL) measured in one pixel in IP, which corresponded well with deposited energy in IP exposed to total fluence of T β electrons for 1 h. Depending on density of materials from carbon to tungsten, less than around 1 Bq in the materials could be detected by 1 h measurement with TIPT.…”

Section: Tritium Retention Characteristics In Individual Ilw-3 Dust P...mentioning

confidence: 99%

An overview of tritium retention in dust particles from the JET-ILW divertor

et al. 2022

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Tritium (T) retention characteristics in dust collected from the divertor in JET with ITER-like wall (JET-ILW) after the third campaign in 2015-2016 (ILW-3) have been examined in individual dust particles by combining radiography (tritium imaging plate technique) and electron probe micro-analysis. The results are summarized and compared with the data obtained after the first campaign in 2011-2012 (ILW-1). The dominant component in ILW-1 dust was carbon (C) originating from tungsten-coated carbon fibre composite (CFC) tiles in JET-ILW divertor and/or legacy of C dust after the JET operation with carbon wall. Around 85 % of the total tritium retention in ILW-1 dust was attributede to the C dust. The retention in tungsten (W) and beryllium (Be) dominated particles was 100 times smaller than the highest T retention in carbon-based particles. After ILW-3 the main component contributing to the T retention was W. The number of small W particles with T increased, in comparison to ILW-1, most probably by the exfoliation and fragmentation of W coatings on CFC tiles though T retention in individual W particles was smaller than in C particles. The detection of only very few Be-dominated dust particles found after ILW-1 and ILW-3 could imply stable Be deposits on the divertor tiles.

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Application of a Tritium Imaging Plate Technique to Depth Profiling of Hydrogen in Metals and Determination of Hydrogen Diffusion Coefficients

Cited by 10 publications

References 31 publications

Tritium in plasma-facing components of JET with the ITER-Like-Wall

Tritium in plasma-facing components of JET with the ITER-Like-Wall

Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall

An overview of tritium retention in dust particles from the JET-ILW divertor

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