Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data

Catarino, N.; Barradas, N.P.; Corregidor, V.; Widdowson, A.; Baron-Wiechec, A.; Coad, J. P.; Heinola, K.; Rubel, M.

doi:10.1016/j.nme.2016.10.027

Cited by 29 publications

(24 citation statements)

References 15 publications

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“…The surfaces of Be limiter and upper dump plate tiles removed from JET after each operating period have been studied at the ion beam facility based at IPFN, Instituto Superior Técnico. The following ion beam analysis techniques have been used; Elastic Back Scattering (EBS) using 2.3 MeV H + , Nuclear Reaction Analysis (NRA) using 2.3 MeV 3 He + reactions, 9 Be( 3 He, p) 11 Be, 12 C( 3 He, p) 14 N, 2 H( 3 He, p) 4 He, and Particle Induced X-ray Emission (PIXE). The scattering angle for the EBS detector and PIXE detector is 150°.…”

Section: Methodsmentioning

confidence: 99%

“…In addition the cross sections used are C( 3 He,p) 14 N [10] and calculated D( 3 He,p) 4 He and D( 3 He, 4 He)p following the methods of [11]. Further details of the detectors used may be found in [12]. At this facility the large vacuum chamber with glove box attached enables whole JET tile samples contaminated with Be and tritium (T) to be handled.…”

Section: Methodsmentioning

confidence: 99%

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Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

et al. 2020

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Fuel retention and material migration results from JET ITER-like wall beryllium limiter tiles are presented for three operating periods. Ion beam analysis results support the general picture of erosion during limiter configurations with local deposition on tile ends far into the scrape off layer. Similar trends of fuel concentrations are observed in all JET operating periods; (i) low on surfaces exposed to high heat flux and erosion and (ii) higher in deposits. The pattern of fuel retention and deposition correlates with heat flux and distribution of limiter plasmas touching inner and outer limiters. The D/Be ratio in the thickest deposit is ~0.01. Global fuel retention attributed to limiters is < 0.01% of injected fuel. Marker coatings reveal a rapid transition from strong erosion to deposition within 15 mm. This work highlights the need to carefully consider the requirements of marker coatings for long exposure studies in high erosion areas.

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Section: Methodsmentioning

confidence: 99%

Section: Methodsmentioning

confidence: 99%

Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

et al. 2020

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“…To give some perspective on the efficacy of cleaning, isotopic exchange experiments with gas balance analysis have shown an accessible reservoir of 3×10 23 atoms in the ILW2 operating period [29]. Isotope exchange between H and D has also been demonstrated by ex situ analysis of Be and W components where H displaces D in components removed after ILW2 operations which ended in H plasmas and resulted in H rich surfaces [30].…”

Section: Operationsmentioning

confidence: 99%

Evaluation of tritium retention in plasma facing components during JET tritium operations

et al. 2021

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An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T & DT operations is presented based on the most comprehensive ex-situ fuel retention data set on JET PFCs from the 2015-2016 ILW3 operating period is presented. The global fuel retention is 4.19 x 1023 D atoms, 0.19% of injected fuel. The inner divertor remains the region of highest fuel retention (46.5%). The T inventory in PFCs at the end of JET operations is calculated as 7.48 x 1022 atoms and is informative for accountancy, clean-up efficacy and waste liability assessments. The T accumulation rate at the upper inner divertor during JET deuterium-tritium (DT) operations has been used to assess the requirements and frequency of operation of a new laser induced desorption diagnostic to be installed on JET for the final DT experiments in 2023.

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“…techniques such as nuclear reaction analysis (NRA) and elastic back scattering of protons (EBS) has revealed Be concentrations in the deposit ~3.8x10 19 atoms cm -2 [49,50,51]. The deposit is layered as shown in Figure 18.…”

Section: Hot Spot On the Partly Delaminated Divertor Tilesmentioning

confidence: 99%

Real-time protection of the JET ITER-like wall based on near infrared imaging diagnostic systems

et al. 2018

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In JET with ITER-like wall (JET-ILW), the first wall was changed to metallic materials (tungsten and beryllium) [1] which require a reliable protection system to avoid damage of the plasma-facing components (PFCs) due to beryllium melting or cracking of tungsten owing to thermal fatigue. To address this issue, a protection system with real time control, based on imaging diagnostics, has been implemented on JET-ILW in 2011.

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Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data

Cited by 29 publications

References 15 publications

Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

Evaluation of tritium retention in plasma facing components during JET tritium operations

Real-time protection of the JET ITER-like wall based on near infrared imaging diagnostic systems

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