Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry

Lee, S. E.; Hatano, Yuji; Hara, Masanori; Masuzaki, S.; Tokitani, M.; Oyaizu, Makoto; Kurotaki, H.; Hamaguchi, Dai; Nakamura, Hirofumi; Asakura, N.; Oya, Yasuhisa; Likonen, J.; Widdowson, A.; Jachmich, S.; Helariutta, K.; Rubel, M.

doi:10.1016/j.fusengdes.2020.111959

Cited by 6 publications

(5 citation statements)

References 18 publications

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“…In contrast, IWGL and DP specimens showed no T enrichment at the top region. As reported in previous papers [12,13], the T retention on PFSs of OPL specimens was higher by an order of magnitude than that on IWGL and DP specimens due to the retention mechanism for high energy (∼MeV) T ions by implantation. This is in contrast to the D retention reported where retention is dominated by co-deposition.…”

Section: Discussionsupporting

confidence: 75%

“…The values of T retention on all four castellation sides of each specimen were averaged and then compared for respective limiters and operation periods. This is shown in figure 10 which also contains data for PFSs presented in previous papers [12,13]. The T retention is higher after ILW1 than ILW3 in the castellation sides and comparable retention values are observed regardless of tile location after each campaign.…”

Section: Two-dimensional Tritium Distributionsupporting

confidence: 63%

“…Pajuste et al examined T retention in Be tile PFSs by the dissolution method [11]. The T retention reported was smaller by a factor of 2-10 depending on the specimen location than the values evaluated in our previous papers [12,13] and those given in figure 10. This difference can be ascribed, at least in part, to non-uniformity of T distributions in the tokamak and to differences in the measurement techniques.…”

Section: Two-dimensional Tritium Distributionmentioning

confidence: 68%

“…On the other hand, on the PFSs of Be limiters in the main chamber, there was no clear correlation between the deposition and T distributions. The T concentration was higher in the erosion-dominated areas than in the deposition zone on the outer poloidal limiter (OPL) [10][11][12][13] because deep implantation (micrometer range) of high-energy T was a dominant retention mechanism in PFSs of Be limiters [12]. As a consequence, the T retention in the erosion zone of those tiles was determined by the balance between the amount of T implanted at high energy and the amount removed by erosion and/or thermal desorption [12].…”

Section: Introductionmentioning

confidence: 99%

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Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments

et al. 2023

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Tritium (T) retention in the castellated structure of beryllium limiters used in JET with the ITER-like wall (ILW) during the first (ILW1), third (ILW3) and all three (ILW1-3) campaigns were examined and evaluated. Tritium was deposited on the surfaces inside the castellation grooves together with deuterium, beryllium, oxygen, carbon and small amounts of metallic impurities such as nickel, copper and tungsten. The T content after ILW1 was greater than after ILW3. This is attributed to the steadily decreasing amount of carbon impurities in JET from campaign to campaign. The majority of T was retained in shallow regions in the grooves, up to 2 mm from the entrance to the gap. It was comparable on all sides of the castellation, i.e. no difference has been detected between the toroidal and poloidal gaps. Secondly, the T retention in the gaps was similar on all specimens independently on their position in the tokamak while the retention on the plasma-facing surfaces was clearly depended on the tile position. The tritium deposition patterns in the castellation were also compared with the deuterium distribution determined in earlier studies.

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Section: Discussionsupporting

confidence: 75%

Section: Two-dimensional Tritium Distributionsupporting

confidence: 63%

Section: Two-dimensional Tritium Distributionmentioning

confidence: 68%

Section: Introductionmentioning

confidence: 99%

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Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments

et al. 2023

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“…X-ray photoelectron spectrometry [30] has a high resolution (nm), however it is limited only to near surface tritium measurement: 3 μm and 0.3 μm for Be and W, respectively. Method has been applied to the JET vacuum vessel tiles retrieved during ILW shutdowns [29,31].…”

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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Non-destructive radiological characterization applied to fusion waste management

Marzo

Lepore

Levizzari

et al. 2021

Fusion Engineering and Design

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Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry

Cited by 6 publications

References 18 publications

Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments

Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments

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

Non-destructive radiological characterization applied to fusion waste management

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