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

Otsuka, Teppei; Masuzaki, S.; Ashikawa, N.; Torikai, Y.; Hatano, Yuji; Tokitani, M.; Oya, Yasuhisa; Hayashi, T.; Tanigawa, Hiroyasu; Asakura, N.; Iwai, Yasunori; Widdowson, A.; Rubel, M.

doi:10.1088/1402-4896/ac445b

Cited by 4 publications

(3 citation statements)

References 15 publications

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“…The core objective of this work is an application study of the migration, toward and across the magnetic separatrix, of statistically significant samples of W particulate released by certain divertor tiles in JET [5][6][7][8], and of its consequences on the density and temperature pedestals in L-H-L transitions.…”

Section: Framework Of Theoretical Models and Numerical Toolsmentioning

confidence: 99%

“…The plasma profiles in the SOL are modelled using a diffusive and convective ansatz [21,25]. The choice, for the test cases of the total amount of W and the size of the dust grains is based on the published results of JET experiments and measurements related to dust collection and analysis [1,[6][7][8]. The choice of initial energy (velocity) distribution corresponds to well known models of contact physics [22,23].…”

Section: Reference Configuration and Selection Of Test Casesmentioning

confidence: 99%

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Simulated effects of W dust ablation and deposition on the pedestal edge in JET D and DT experiments

Lazzaro¹,

Causa²,

Gervasini³

et al. 2022

Nucl. Fusion

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A modelling analysis is performed on JET D and DT discharges, where W dust inux across the separatrix, in the pedestal edge region may a ect L-H-L mode transition. The experimental basis of the proposed approach stems from the observation that transient impurity events (TIEs) are often associated with the presence of a shower of particles seen in the camera images and with strong optical emission. If the localised source of radiation is a number of heated or ablated large dust particles, then the questions addressed here are: how far will the ablated dust material penetrate and what effect will this have on the edge of the pedestal in relevant JET D and in a high fusion yield D-T discharges. The methodology is based on the use of an upgraded version of the ballistic code DUSTTRACK and a new code PELLYTIX for dust ablation modelling. Considering a reasonable amount of dust released from the tiles, the analysis shows that the ablation-penetration depth is visible in the density pro les modification, but not disastrous for tokamak operation in high regimes.

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Section: Framework Of Theoretical Models and Numerical Toolsmentioning

confidence: 99%

Section: Reference Configuration and Selection Of Test Casesmentioning

confidence: 99%

Simulated effects of W dust ablation and deposition on the pedestal edge in JET D and DT experiments

Lazzaro¹,

Causa²,

Gervasini³

et al. 2022

Nucl. Fusion

Self Cite

View full text Add to dashboard Cite

show abstract

“…Equally needed is the assessment of fuel content in individual grains in order to identify types of particles retaining hydrogen isotopes. Deuterium was studied by ion beam methods in vacuumed [ 15 ] and locally sampled dust [ 14 ], while tritium in vacuumed matter was determined using radiography [ 27 , 28 ]. All results have coherently indicated that fuel accumulation in the JET-ILW dust was predominantly associated with residual carbon particles being either legacy from JET-C or small debris from the rear side of W-coated carbon fibre composite (CFC) divertor tiles in JET-ILW.…”

Section: Introductionmentioning

confidence: 99%

Dust Monitors in JET with ITER-like Wall for Diagnosis of Mobilized Particles and Co-Deposited Layers

et al. 2022

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Silicon plates were installed above the inner and outer divertor of the JET with the ITER-like wall (ILW) after the second and third ILW campaigns to monitor dust generation and deposition with the aim to determine the morphology and content of individual particles and co-deposits, including deuterium content. Particular interest was in metal-based particles: Be, W, steel, Cu. Ex-situ examination after two ILW campaigns was performed by a set of microscopy and ion beam methods including micro-beam nuclear reaction analysis and particle-induced X-ray emission. Different categories of Be-rich particles were found: co-deposits peeled-off from plasma-facing components (PFC), complex multi-element spherical objects, and solid metal splashes and regular spherical droplets. The fuel content on the two latter categories was at the level of 1 × 1016 at/cm−2 indicating that Be melting and splashing occurred in the very last phase of the second experimental campaign. The splashes adhere firmly to the substrate thus not posing risk of Be dust mobilisation. No tungsten droplets were detected. The only W-containing particles were fragments of tungsten coatings from the divertor tiles.

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Characterization of helium retention in the inhomogeneous co-deposited layers using a long pulse laser induced ablation-quadrupole mass spectroscopy

Lyu

Wang

et al. 2022

Nuclear Materials and Energy

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

Cited by 4 publications

References 15 publications

Simulated effects of W dust ablation and deposition on the pedestal edge in JET D and DT experiments

Simulated effects of W dust ablation and deposition on the pedestal edge in JET D and DT experiments

Dust Monitors in JET with ITER-like Wall for Diagnosis of Mobilized Particles and Co-Deposited Layers

Characterization of helium retention in the inhomogeneous co-deposited layers using a long pulse laser induced ablation-quadrupole mass spectroscopy

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