Search Results - "Bekris, N"

Plasma current measurement at JET using polarimetry-based fibre optic current sensor by Leysen, W., Gusarov, A., Wuilpart, M., Beaumont, P., Boboc, A., Croft, D., Bekris, N., Batistoni, P.

“…•Fibre Optic Current Sensor (FOCS) was installed on JET.•A good agreement between the FOCS and the reference Continuous External Rogowski coils measurements…”
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Laser induced breakdown spectroscopy application in joint European torus by Semerok, A., L'Hermite, D., Weulersse, J.-M., Lacour, J.-L., Cheymol, G., Kempenaars, M., Bekris, N., Grisolia, C.

“…The results on the first successful application of Laser Induced Breakdown Spectroscopy (LIBS) for remote in situ diagnostics of plasma facing components (a…”
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Studies on the behaviour of titanium activation foils during long-term exposure at the JET tokamak by Wójcik-Gargula, A., Rubel, M., Batistoni, P., Bekris, N., Colling, B., Dutkiewicz, E., Laas, T., Nobs, C.R., Paju, J., Packer, L.W., Perzanowski, M., Petersson, P., Priimets, J., Vasilopoulou, T.

“…•First-ever long-term direct exposure of Ti in the tokamak environment.•Identification of different stages of Ti degradation up to complete…”
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2D tritium distribution on tungsten tiles used in JET ITER-like wall project by Hatano, Y., Widdowson, A., Bekris, N., Ayres, C., Baron-Wiechec, A., Likonen, J., Koivuranta, S., Ikonen, J., Yumizuru, K.

“…Post-mortem measurements of 2-dimensional tritium (T) distribution using an imaging plate (IP) technique were performed for tungsten (W) divertor tiles…”
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Modelling of the material transport and layer formation in the divertor of JET: Comparison of ITER-like wall with full carbon wall conditions by Kirschner, A., Matveev, D., Borodin, D., Airila, M., Brezinsek, S., Groth, M., Wiesen, S., Widdowson, A., Beal, J., Esser, H.G., Likonen, J., Bekris, N., Ding, R.

“…Impurity transport within the inner JET divertor has been modelled with ERO to estimate the transport to and the resulting deposition at remote areas. Various…”
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Material migration and fuel retention studies during the JET carbon divertor campaigns by Coad, J.P., Rubel, M., Likonen, J., Bekris, N., Brezinsek, S., Matthews, G.F., Mayer, M., Widdowson, A.M.

“…•Operations using four carbon divertor configurations in JET are described.•Carbon with Be, Ni, etc eroded in the main chamber deposit at the inner…”
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Implementation and exploitation of JET enhancements at different fuel mixtures in preparation for DT operation and next step devices by Murari, A., Bekris, N., Figueiredo, J., Kim, H.-T., Perez Von Thun, C., Balboa, I., Batistoni, P., Giegerich, T., Huddleston, T., Rubel, M., Vila, R., Villari, R., Widdowson, A.

“…In the framework of the ITER Physics Department of the EUROfusion Consortium, JET mission is focused on preparing for the next step devices by developing high…”
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Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997 by Likonen, J., Bekris, N., Coad, J.P., Ayres, C., Gotts, N., Jepu, I., Zayachuk, Y., Widdowson, A., Wilson, I., Catarino, N., de Alves, E.

“…•In 2019 two MkIIA divertor tiles (6IN3 and 4BN4) exposed during DTE1 were retrieved at CCFE for Thermal Desorption Spectroscopy (TDS) and pyrolysis…”
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Upgrades of Diagnostic Techniques and Technologies for JET Next D-T Campaigns by Murari, A., Figueiredo, J., Bekris, N., Perez von Thun, C., Batistoni, P., Marocco, D., Belli, F., Tardocchi, M., Garcia Munoz, M., Silva, A., Soare, S., Craciunescu, T., Santala, M., Blanchard, P., Croft, D.

“…In the perspective of reducing ITER risks, JET next DT campaign presents a unique potential, since the device can combine the right first wall material mix,…”
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Overview of R&D at TLK for process and analytical issues on tritium management in breeder blankets of ITER and DEMO by Demange, D., Alecu, C.G., Bekris, N., Borisevich, O., Bornschein, B., Fischer, S., Gramlich, N., Köllö, Z., Le, T.L., Michling, R., Priester, F., Röllig, M., Schlösser, M., Stämmler, S., Sturm, M., Wagner, R., Welte, S.

“…► We present advanced processes and analytics to improve tritium management. ► Membranes and membrane reactors can minimise tritium residence time and…”
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Tritium retention of plasma facing components in tokamaks by Tanabe, T, Bekris, N, Coad, P, Skinner, C.H, Glugla, M, Miya, N

“…The areal distribution of tritium retention in tiles from TEXTOR, TFTR, JT-60U and JET has been measured via the imaging plate technique and the results are…”
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In-situ tokamak laser applications for detritiation and co-deposited layers studies by Grisolia, C., Semerok, A., Weulersse, J.M., Le Guern, F., Fomichev, S., Brygo, F., Fichet, P., Thro, P.Y., Coad, P., Bekris, N., Stamp, M., Rosanvallon, S., Piazza, G.

“…Treatment of plasma facing components (PFCs) is a major issue for ITER operations and may be applied for different reasons. As a most important application,…”
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Water detritiation processing of JET purified waste water using the TRENTA facility at Tritium Laboratory Karlsruhe by Michling, R., Bekris, N., Cristescu, I., Lohr, N., Plusczyk, C., Welte, S., Wendel, J.

“…•Operation of a water detritiation facility under optimized conditions for high detritiation performances.•Improvement of operational procedures to process…”
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Experimental assessment of a catalytic hydrogen oxidation system for the off-gas processing of the ITER WDS by Plusczyk, C., Bekris, N., Cristescu, I., Lohr, N., Michling, R., Moosmann, H., Welte, S.

“…•Setup of a hydrogen oxidation facility using a Pd reactor.•Commissioning of a hydrogen oxidation facility using a Pd reactor.•Computational Fluid Dynamic…”
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Erosion/deposition issues at JET by Coad, J.P., Bekris, N., Elder, J.D., Erents, S.K., Hole, D.E., Lawson, K.D., Matthews, G.F., Penzhorn, R.-D., Stangeby, P.C.

“…Deposition and H-isotope retention in JET is highly asymmetric, with deposition predominantly in the inner divertor, where flaking deposits form on…”
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Fusion Technology related studies at JET: Post-mortem tile analysis with MKII-HD geometry, In situ laser detritiation and Molecular Sieve Bed detritiation by Bekris, N., Coad, J.P., Grisolia, C., Likonen, J., Semerok, A., Dylst, K., Widdowson, A.

“…The JET Task Force Fusion Technology (TF-FT) has been launched with the aim of addressing issues related to JET and ITER. In this regard, studies related to…”
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Failure modes of vacuum plasma spray tungsten coating created on carbon fibre composites under thermal loads by Hirai, T., Bekris, N., Coad, J.P., Grisolia, C., Linke, J., Maier, H., Matthews, G.F., Philipps, V., Wessel, E.

“…Vacuum plasma spray tungsten (VPS-W) coating created on a carbon fibre reinforced composite (CFC) was tested under two thermal load schemes in the electron…”
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Efficacy of photon cleaning of JET divertor tiles by Widdowson, A., Coad, J.P., Bekris, N., Counsell, G., Forrest, M.J., Gibson, K.J., Hole, D., Likonen, J., Parsons, W., Renvall, T., Rubel, M.

“…Photon cleaning by means of a flash-lamp was used for in-situ detritiation of the inner wall tiles of the JET divertor in May 2004. Additional trials were also…”
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Comparison of tritium retention and carbon deposition in JET and JT-60U by Tanabe, T., Sugiyama, K., Coad, P., Bekris, N., Glugla, M., Miya, N.

“…Profiles of T retention in the Mark IIA divertor of JET and H/D and T retention in the W-shaped divertor of JT-60U are compared. Hydrogen (H, D and T) is…”
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Tritium removal from JET and TFTR tiles by a scanning laser by Skinner, C.H., Bekris, N., Coad, J.P., Gentile, C.A., Glugla, M.

“…Fast and efficient tritium removal is needed for future DT machines with carbon plasma facing components. A novel method for tritium release has been…”
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