Scientific Commons: V. Philipps

A bulk tungsten divertor row for the outer strike point in JET (2009)

Mertens, Ph., Altmann, H., Hirai, T., Knaup, M., Neubauer, O., Philipps, V., ...

In the frame of the ITER-like wall project, a new row of divertor tiles has been developed which consists of 96 bulk tungsten load-bearing septum replacement plates (LB-SRP). Exposed to the outer...

Development and qualification of a bulk tungsten divertor row for JET (2009)

Mertens, Ph., Altmann, H., Hirai, T., Philipps, V., Pintsuk, G., Rapp, J., ...

A bulk tungsten divertor row has been developed in the frame of the ITER-like Wall project at JET. It consists of 96 tiles grouped in 48 modules around the torus. The outer strike point is located on...

Analysis of fuel retention in plasma-facing components from controlled fusion devices (2009)

Rubel, M., Coad, J. P., Likonen, Jari, Philipps, V., JET-EFDA Contributors

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms Vol.267 Nr.4, 711 - 717

Development of divertor tungsten coatings for the JET ITER-like wall (2009)

Matthews, G. F., Coad, P., Greuner, H., Hill, M., Hirai, T., Likonen, Jari, ...

Journal of Nuclear Materials. In press

Testing of tungsten coatings in JET for the ITER-like wall (2009)

Coad, J. P., Hole, D. E., Kolodinska, E., Likonen, Jari, Lindig, S., Matthews, G. F., ...

Journal of Nuclear Materials. In press

Recent analysis of key plasma wall interactions issues for ITER (2009)

Roth, J., Tsitrone, E., Loarte, A., Loarer, T., Counsell, G., Neu, R., ...

Dynamics of erosion and deposition in tokamaks (2009)

Kreter, A., Brezinsek, S., Coad, J. P., Esser, H. G., Fundamenski, W., Philipps, V., ...

Effects of tungsten surface conditions on carbon deposition (2009)

Ueda, Y., Fukumoto, M., Yamawaki, A., Soga, Y., Ohtsuka, Y., Brezinsek, S., ...

Be wall sources and migration in L-mode discharges after Be evaporation in the JET tokamak (2009)

Krieger, K., Brezinsek, S., Jachmich, S., Lisgo, S., Stamp, M., Esser, H. G., ...

Estimations of erosion fluxes, material deposition and tritium retention in the divertor of ITER (2009)

Kirschner, A., Borodin, D., Philipps, V., Samm, U., Ding, R., Schmid, K., ...

The impact of divertor detachment on carbon sources in JET L-mode discharges (2009)

Brezinsek, S., Meigs, A. G., Jachmich, S., Stamp, M. F., Rapp, J., Felton, R., ...

Particle confinement control with resonant magnetic perturbations at TEXTOR (2009)

Schmitz, O., Coenen, J. W., Frerichs, H., Kantor, M., Lehnen, M., Unterberg, B., ...

Testing of tungsten coatings in JET for the ITER-like wall (2009)

Coad, J.P., Hole, D.E., Likonen, Jari, Lindig, S., Matthews, G.F., Mayer, M., ...

Journal of Nuclear Materials Vol.390-391, 992-995

Investigations of castellated structures for ITER: The effect of castellation shaping and alignment on fuel retention and impurity deposition in gaps (2009)

Litnovsky, A., Wienhold, P., Philipps, V., Krieger, K., Kirschner, A., Matveev, D., ...

The impact of large ELMs on JET (2009)

Pitts, R. A., Arnoux, G., Beurskens, M., Eich, T., Fundamenski, W., Huber, A., ...

Failure modes of vacuum plasma spray tungsten coating created on carbon fibre composites under thermal loads (2009)

Hirai, T., Bekris, N., Coad, J. P., Grisolia, C., Linke, J., Maier, H., ...

Influence of toroidal and vertical magnetic fields on Ion Cyclotron Wall Conditioning in tokamaks (2009)

Lyssoivan, A., Sergienko, G., Rohde, V., Philipps, V., Van Wassenhove, G., Vervier, M., ...

Plasma radiation distribution and radiation loads onto the vessel during transient events in JET (2009)

Huber, A., Pitts, R. A., Loarte, A., Philipps, V., Andrew, P., Brezinsek, S., ...

Development of divertor tungsten coatings for the JET ITER-like wall (2009)

Matthews, G. F., Coad, P., Greuner, H., Hill, M., Hirai, T., Likonen, J., ...

Testing of tungsten coatings in JET for the ITER-like wall (2009)

Coad, J. P., Hole, D. E., Kolodinska, E., Likonen, J., Lindig, S., Matthews, G. F., ...

Industrial Scale 10 µm W Coating of CFC tiles for ITER-like Wall Project at JET (2009)

Ruset, C., Grigore, E., Munteanu, I., Maier, H., Greuner, H., Hopf, C., ...

Castellated structures for ITER: Differences of impurity deposition and fuel accumulation in the toroidal and poloidal gaps (2009)

Litnovsky, A., Philipps, V., Wienhold, P., Krieger, K., Kirschner, A., Borodin, D., ...

Impact of large type I ELMs on plasma radiation in JET (2009)

Huber, A., Arnoux, G., Beurskens, M. N. A., Brezinsek, S., Coad, P., Eich, T., ...

Impact of large type I ELMs on plasma radiation in JET (2009)

Huber, A., Arnoux, G., Brezinsek, S., Coad, P., Eich, T., Fuchs, J. C., ...

Effect of surface roughness and substrate material on carbon deposition in tokamak TEXTOR (2008)

Kreter, A., Brezinsek, S., Hirai, T., Kirschner, A., Krieger, K., Mayer, M., ...

Tritium inventory in ITER plasma-facing materials and tritium removal procedures (2008)

Roth, J., Tsitrone, E., Loarer, T., Philipps, V., Brezinsek, S., Loarte, A., ...

Modelling of carbon migration during JET 13C injection experiments (2008)

Strachan, J. D., Likonen, J., Coad, P., Rubel, M., Widdowson, A., Airila, M., ...

Plasma radiation during transient events in JET (2008)

Huber, A., Pitts, R. A., Loarte, A., Philipps, V., Andrew, P., Arnoux, G., ...

Modelling of carbon migration during JET 13C injection experiments (2008)

Strachan, J. D., Likonen, Jari, Coad, P., Rubel, M., Widdowson, A., Airila, M., ...

Nuclear Fusion Vol.48 Nr.10, art. no. 105002

The impact of large ELMs on JET (2008)

Pitts, R.A., Alonso, A., Arnoux, G., Brezinsek, S., Beurskens, M., Eich, T., ...

Development and testing of a bulk tungsten tile for the JET divertor (2007)

Hirai, T., Bondarchuk, E., Borovkov, A.I., Koppitz, Th., Linke, J., Mertens, Ph., ...

The ITER-like wall project has been launched to design, manufacture and test all the necessary components in view of their installation in a dedicated shutdown 2008–09. One of the R&D activities in...

R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project (2007)

Hirai, T., Maier, H., Rubel, M., Mertens, Ph., Neu, R., Gauthier, E., ...

The ITER reference materials have been tested separately in tokamaks, plasma simulators, ion beams and high heat flux test beds. In order to perform a fully integrated material test JET has launched...

Tungsten and beryllium armour development for the JET ITER-like wall project (2007)

Maier, H., Hirai, T., Rubel, M., Mertens, Ph., Greuner, H., Hopf, Ch., ...

For the ITER-like wall project at JET, the present main chamber CFC tiles will be exchanged with Be tiles and in parallel a fully tungsten-clad divertor will be prepared. Three R&D programmes were...

Overview of the ITER-like Wall Project (2007)

Matthews, G., Edwards, P., Hirai, T., Kear, M., Lioure, A., Lomas, P., ...

DiMES studies of temperature dependence of carbon erosion and re-deposition in DIII-D divertor (2007)

Rudakov, D.L., Jacob, W., Krieger, K., Litnovsky, A., Philipps, V., West, W.P., ...

Long-term erosion and deposition studies of the main graphite limiter in TEXTOR (2007)

Kreter, A., Kirschner, A., Wienhold, P., Likonen, J., Mayer, M., Philipps, V., ...

Tungsten and Beryllium Armour Development for the JET ITER-like Wall Project (2007)

Maier, H., Hirai, T., Rubel, M., Neu, R., Mertens, P., Greuner, H., ...

Investigation of Tungsten Coatings on Graphite and CFC (2007)

Neu, R., Maier, H., Gauthier, E., Greuner, H., Hirai, T., Hopf, C., ...

Divertor and Midplane Materials Evaluation System in DIII-D (2007)

Wong, C., Rudakov, D., Allain, J., Bastasz, R., Brooks, N., Brooks, J., ...

Material Erosion and Redeposition during the JET MkIIGB-SRP Divertor Campaign. Invited paper (2007)

Kirschner, A., Philipps, V., Balden, M., Bonnin, X., Brezinsek, S., Coad, J. P., ...

Plasma-surface interaction, scrape-off layer and divertor physics: Implications for ITER. Invited paper (2007)

Lipschultz, B., Asakura, N., Bonnin, X., Coster, D., Counsell, G., Doerner, R., ...

Gas Balance and Fuel Retention in Fusion Devices (2007)

Loarer, T., Brosset, C., Bucalossi, J., Coad, P., Esser, G., Hogan, J., ...

Tungsten and Beryllium Armour Development for the JET ITER-like Wall Project (2007)

Maier, H., Hirai, T., Rubel, M., Neu, R., Mertens, P., Greuner, H., ...

Improved radiation measurements on JET - First results from an upgraded bolometer system (2007)

Huber, A., McCormick, K., Andrew, P., De Baar, M. R., Beaumont, P., Dalley, S., ...

Carbon transport, deposition and fuel accumulation in castellated structures exposed in TEXTOR (2007)

Litnovsky, A., Philipps, V., Kirschner, A., Wienhold, P., Sergienko, G., Kreter, A., ...

Gas balance and fuel retention in fusion devices (2007)

Loarer, T., Brosset, C., Bucalossi, J., Coad, P., Esser, G., Hogan, J., ...

Chapter 4: Power and particle control (2007)

Loarte, A., Lipschultz, B., Kukushkin, A. S., Matthews, G. F., Stangeby, P. C., Asakura, N., ...

Hydrocarbon injection for quantification of chemical erosion yields in tokamaks (2007)

Brezinsek, S., Pospieszczyk, A., Borodin, D., Stamp, M.F., Pugno, R., McLean, A.G., ...

Plasma-surface interaction, scrape-off layer and divertor physics: implications for ITER (2007)

Lipschultz, B., Bonnin, X., Counsell, G., Kallenbach, A., Kukushkin, A., Krieger, K., ...

Tungsten Coatings for the JET ITER-like Wall Project (2007)

Maier, H., Neu, R., Greuner, H., Hopf, C., Matthews, G., Piazza, G., ...

R&D on full tungsten divertor and beryllium wall for JET ITER-like Wall Project (2007)

Hirai, T., Maier, H., Rubel, M., Mertens, P., Neu, R., Gauthier, E., ...

Upgraded bolometer system on JET for improved radiation measurements (2007)

Huber, A., McCormick, K., Andrew, P., Beaumont, P., Dalley, S., Fink, J., ...

Castellated structures for ITER: the influence of the shape of castellation on the impurity deposition and fuel accumulation in gaps (2007)

Litnovsky, A., Philipps, V., Wienhold, P., Krieger, K., Sergienko, G., Kreter, A., ...

New scenarios of ICRF wall conditioning in TEXTOR and ASDEX Upgrade (2007)

Lyssoivan, A., Koch, R., Van Eester, D., Van Wassenhov, G., Vervier, M., Weynants, R., ...

Development of steady-state scenarios compatible with ITER-like wall conditions. Invited Paper (2007)

Litaudon, X., Arnoux, G., Beurskens, M., Brezinsek, S., Challis, C. D., Crisanti, F., ...

Divertor radiation distribution during ELMs in JET (2007)

Huber, A., Pitts, R.A., Philipps, V., Loarte, A., Andrew, P., Brezinsek, S., ...

Chapter 4: Power and particle control (2007)

Loarte, A., Lipschultz, B., Kukushkin, A. S., Matthews, G. F., Stangeby, P. C., Asakura, N., ...

Progress, since the ITER Physics Basis publication (ITER Physics Basis Editors et al 1999 Nucl. Fusion 39 2137-2664), in understanding the processes that will determine the properties of the plasma...

Diagnostic mirrors for ITER: A material choice and the impact of erosion and deposition on their performance (2007)

Litnovsky, A., Wienhold, P., Philipps, V., Sergienko, G., Schmitz, O., Kirschner, A., ...

Metal mirrors will be implemented in about half of the ITER diagnostics. Mirrors in ITER will have to withstand radiation loads, erosion by charge-exchange neutrals, deposition of impurities,...

Development and testing of a bulk tungsten tile for the JET divertor (2007)

HIRAI, T, BONDARCHUK, E, BOROVKOV, AI, KOPPITZ, T, LINKE, J, MERTENS, P, ...

Tungsten and beryllium armour development for the JET ITER-like wall project (2007)

MAIER, H, HIRAI, T, RUBEL, M, NEU, R, MERTENS, P, GREUNER, H, ...

New scenarios of ICRF wall conditioning in TEXTOR and ASDEX upgrade (2007)

LYSSOLVAN, A, KOCH, R, VAN EESTER, D, VAN WASSENHOVE, G, VERVIER, M, WEYNANTS, R, ...

ICRF plasmas for fusion reactor applications (2007)

LYSSOIVAN, A, VERVIER, M, NEUBAUER, O, HARTMANN, D, GAUTHIER, E, SHVETS, O, ...

Experience with bulk tungsten test-limiters under high heat loads: melting and melt layer propagation. (2007)

Sergienko, G., Bazylev, B., Hirai, T., Huber, A., Kreter, A., Mertens, Ph., ...

Physica Scripta, T128(2007) S.81-86

Experience with bulk tungsten test-limiters under high heat loads: melting and melt layer propagation. (2007)

Sergienko, G., Bazylev, B., Hirai, T., Huber, A., Kreter, A., Mertens, Ph., ...

11th Internat.Workshop on Plasma-Facing Materials and Components for Fusion Applications, Greifswald, October 10-12, 2006

Erosion of a tungsten limiter under high heat flux in TEXTOR . (2007)

Sergienko, G., Bazylev, B., Huber, A., Kreter, A., Litnovsky, A., Rubel, M., ...

Journal of Nuclear Materials, 363-365(2007) S.96-100

Properties of co-deposited layers on graphite high heat flux components at the TEXTOR tokamak (2007)

Fortuna, E., Rubel, M. J., Philipps, V., Kurzydlowski, K. J., Mertens, Ph., Miskiewicz, M., ...

R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project (2007)

Hirai, T., Maier, H., Rubel, M., Mertens, Ph., Neu, R., Gauthier, E., ...

Tritium retention in next step devices and the requirements for mitigation and removal techniques. Invited paper (2006)

Counsell, G., Coad, P., Grisola, C., Hopf, C., Jacob, W., Kirschner, A., ...

Material Erosion and Redeposition during the JET MkIIGB-SRP Divertor Campaign (2006)

Kirschner, A., Philipps, V., Balden, M., Bonnin, X., Brezinsek, S., Coad, J., ...

Plasma-surface interaction, scrape-off layer and divertor physics: Implications for ITER (2006)

Lipschultz, B., Asakura, N., Bonnin, X., Coster, D., Counsell, G., Doerner, R., ...

Gas Balance and Fuel Retention in Fusion Devices (2006)

Loarer, T., Brosset, C., Bucalossi, J., Coad, P., Esser, G., Hogan, J., ...

Tungsten and Beryllium Armour Development for the JET ITER-like Wall Project (2006)

Maier, H., Hirai, T., Rubel, M., Neu, R., Mertens, P., Greuner, H., ...

Investigation of carbon transport by 13CH4 injection through graphite and tungsten test limiters in TEXTOR (2006)

Kreter, A., Borodin, D., Brezinsek, S., Droste, S., Hirai, T., Kirschner, A., ...

Tritium retention in next step devices and the requirements for mitigation and removal techniques. Invited paper (2006)

Counsell, G., Coad, P., Grisola, C., Hopf, C., Jacob, W., Kirschner, A., ...

Investigations on Tungsten Coatings on Graphite and CFC. Invited paper (2006)

Neu, R., Maier, H., Gauthier, E., Greuner, H., Hirai, T., Hopf, C., ...

Overview of the ITER-like Wall Project. Invited paper (2006)

Matthews, G., Edwards, P., Hirai, T., Kear, M., Lioure, A., Lomas, P., ...

Material erosion and redeposition during the JET MkIIGB-SRP divertor campaign (2006)

Kirschner, A., Philipps, V., Balden, M., Bonnin, X., Brezinsek, S., Coad, J.P., ...

Applicability of ß-ray-induced X-ray spectrometry to in situ measurements of tritium retention in plasma-facing materials in ITER. (2006)

Matsuyama, M., Torikai, Y., Bekris, N., Glugla, M., Erbe, A., Naegele, W., ...

7th Internat.Symp.on Fusion Nuclear Technology (ISFNT-7), Tokyo, J, May 22-27, 2005

Applicability of ß-ray-induced X-ray spectrometry to in situ measurements of tritium retention in plasma-facing materials in ITER. (2006)

Matsuyama, M., Torikai, Y., Bekris, N., Glugla, M., Erbe, A., Naegele, W., ...

Fusion Engineering and Design, 81(2006) S.163-68

Flux dependence of carbon erosion and implication for ITER (2005)

Roth, J., Kirschner, A., Bohmeyer, W., Brezinsek, S., Cambe, A., Casarotto, E., ...

Development of ICRF wall conditioning technique on divertor-type tokamaks ASDEX Upgrade and JET (2005)

Lyssoivan, A., Hartmann, D. A., Koch, R., Bobkov, V., Blackman, T., ...

Diagnostics for studying deposition and erosion processes in JET (2005)

Coad, J. P., Likonen, J., Mayer, M., Neill, G., Philipps, V., ...

Modelling of tritium retention and target lifetime of the ITER divertor (2005)

Kirschner, A., Droste, S., Borodin, D., Philipps, V., Federici, G., Roth, J.

Report on the 11th European Fusion Physics Workshop (2005)

Campbell, D. J., Becoulet, A., Counsell, G., Federici, G., Imbeaux, F., Kirschner, A., ...

Overview of gas balance in plasma fusion devices (2005)

Loarer, T., Philipps, V., Brosset, C., Bucalossi, J., Geraud, A., Grosman, A., ...

Overview of recent work on carbon erosion, migration and long-term fuel retention in the EU-fusion programme and conclusions for ITER (2005)

Philipps, V., Roth, J., Loarte, A.

Studies of ICRF Discharge Conditioning (ICRF-DC) on ASDEX Upgrade, JET and TEXTOR (2005)

Lyssoivan, A., Koch, R., Van Eester, D., Van Wassenhove, G., Vervier, M., Weynants, R., ...

Tokamak operation with high-Z plasma facing components. Invited paper (2005)

Kallenbach, A., Neu, R., Dux, R., Fuchs, J. C., Giannone, L., ...

The effect of field reversal on the JET MkIIGB-SRP divertor performance in L-mode density limit discharges (2005)

Huber, A., Rapp, J., Andrew, P., Coad, P., Corrigan, G., Erents, K., ...

The effect of field reversal on the JET MkIIGB-SRP divertor performance has been investigated in L-mode density limit discharges. These experiments show that the direction of the magnetic field has a...

Toroidal plasma rotation induced by the Dynamic Ergodic Divertor in the TEXTOR tokamak (2005)

FINKEN, KH, ABDULLAEV, SS, DE BOCK, MFM, VON HELLERMANN, M, JAKUBOWSKI, M, JASPERS, R, ...

Development of ICRF wall conditioning technique on divertor-type tokamaks ASDEX Upgrade and JET (2005)

LYSSOIVAN, A, HARTMANN, DA, Noterdaeme, Jean-Marie, KOCH, R, BOBKOV, V, BLACKMAN, T, ...

Studies of ICRF Discharge Conditioning (ICRF-DC) on ASDEX Upgrade, JET and TEXTOR (2005)

LYSSOIVAN, A, KOCH, R, VAN EESTER, D, VAN WASSENHOEVE, G, VERVIER, G, WEYNANTS, R, ...

Tritium distribution in JET Mark IIA type divertor tiles analysed by BIXS. (2005)

Torikai, Y., Matsuyama, M., Bekris, N., Glugla, M., Coad, P., Naegele, W., ...

16th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices (PSI 2004), Portland, Maine, May 24-28, 2004

Tritium distribution in JET Mark IIA type divertor tiles analysed by BIXS. (2005)

Torikai, Y., Matsuyama, M., Bekris, N., Glugla, M., Coad, P., Naegele, W., ...

Journal of Nuclear Materials, 337-339(2005) S.575-79

Flux dependence of carbon chemical erosion by deuterium ions (2004)

Roth, J., Preuss, R., Bohmeyer, W., Brezinsek, S., Cambe, A., Casarotto, E., ...

The dynamic ergodic divertor in the TEXTOR tokamak: plasma response to dynamic helical magnetic field perturbations (2004)

FINKEN, KH, ABDULLAEV, SS, BIEL, W, DE BOCK, MFM, BUSCH, C, FARSHI, E, ...

OVERVIEW OF EROSION MECHANISMS, IMPURITY TRANSPORT, AND DEPOSITION IN TEXTOR AND RELATED MODELING (2004)

A. Kirschner, V. Philipps, Forschungszentrum Jülich Gmbh

This paper gives an overview of the research activities at TEXTOR on impurity production, impurity transport through the plasma, and then deposition. First, laboratory experiments on chemical erosion...

B4C-limiter experiments at TEXTOR (2003)

Pospieszczyk, A., Schweer, B., Philipps, V., Huber, A., Sergienko, G., Samm, U., ...

In the TEXTOR tokamak the five top and five bottom poloidal carbon limiter blocks have been replaced by inertially cooled copper blocks coated with a 170 μm VPS-B4C layer. Similar limiter blocks...

Comparing scrape-off layer and divertor physics in JET pure He and D discharges (2003)

Pitts, R. A., Andrew, P., Andrew, Y., Becoulet, C., Coffey, I., Coster, D., ...

Though helium plasmas are one option for the low activation phase of ITER, little effort has thus far been devoted to studying them in a large, diverted tokamak. A recent campaign on JET has...

JET carbon screening experiments using methane gas puffing and its relation to intrinsic carbon impurities (2003)

Strachan, J. D., Fundamenski, W., Charlet, M., Corrigan, G., Erents, K., Gafert, J., ...

JET carbon screening experiments were performed using methane gas injection. L-Mode experiments scanned parameters influencing the JET scrape-off-layer (SOL) and/or intrinsic impurity level. Scaling...

Short and long range transport of materials eroded from wall components in fusion devices (2003)

Wienhold, P., Philipps, V., Kirschner, A., Huber, A., Von Seggern, J., Esser, H. G., ...

Carbon sources and the sinks have been quantified in TEXTOR and are discussed in terms of short and long range transport. The major source (22 g/h) is the graphite belt limiter, but part (10 g/h) of...

Tomographic reconstruction of 2D line radiation distribution in the JET MkIIGB divertor (2003)

Huber, A., Coad, P., Coster, D., Ingesson, L. C., Itami, K., Jachmich, S., ...

A 2D-tomographic reconstruction of D- and C III-emission distribution in L-mode, density limit discharge has been performed and compared with results from other diagnostics (KL2, KS3). The observed...

Reduction of divertor heat load in JET ELMy H-modes using impurity seeding techniques (2003)

Rapp, J., Monier-Garbet, P., Andrew, P., Dumortier, P., Eich, T., Fundamenski, W., ...

One of the most severe problems for fusion reactors is the power load on the divertor target plates. In order to reduce the power load in the divertor radiation cooling by seeding of impurities is...

Studies of ELM Heat Load, SOL Flow and Carbon Erosion from Existing Tokamak Experiments, and their Predictions to ITER (2003)

Asakura, N., Loarte, A., Porter, G., Philipps, V., Lipschultz, B., Kallenbach, A., ...

Three important physics issues for the ITER divertor design and operation are summarized based on the experimental and numerical work from multi-machine database (JET, JT-60U, ASDEX Upgrade, DIII-D,...

Density limits in helium plasmas at JET (2003)

Rapp, J., Huber, A., Ingesson, L. C., Jachmich, S., Matthews, G. F., Philipps, V., ...

Recently at JET a pure helium campaign has been performed. The exploration of the density limit in L-mode limiter as well as L-mode and H-mode diverted plasmas was one of the main objectives. In...

Comparison of carbon and main ion radiation profiles in matched helium and deuterium plasmas in JET (2003)

Fenstermacher, M. E., Lawson, K. D., Porter, G. D., Erents, S. K., Ingesson, C., Matthews, G. F., ...

This paper examines the radiation profiles and corresponding ionization source profiles of carbon and main plasma ions in matched helium and deuterium. L-mode plasmas in JET. The radiation...

First wall material issues and related activities at JET. (2003)

Scaffidi-Argentina, F., Ciattaglia, S., Coad, P., Penzhorn, R.D., Philipps, V.

10th Internat.Conf.on Fusion Reactor Materials (ICFRM-10), Baden-Baden, October 14-19, 2001

Non-destructive tritium measurements of Mk IIA divertor tile by BIXS. (2003)

Matsuyama, M., Bekris, N., Glugla, M., Noda, N., Philipps, V., Watanabe, K.

Proc. of the 15th Internat.Conf.on Plasma Surface Interactions in Controlled Fusion Devices (PSI-15), Gifu, J, May 27-31, 2002

Interpretation of recent power width measurements in JET MkIIGB ELMy H-modes (2002)

Fundamenski, W., Sipilä, S., Matthews, G. F., Riccardo, V., Andrew, P., Eich, T., ...

ELM mitigation by nitrogen seeding in the JET gas box divertor (2002)

Rapp, J., Eich, T., Von Hellermann, M., Herrmann, A., Ingesson, L. C., Jachmich, S., ...

One of the most severe problems for fusion reactors is the power load on the divertor target plates. Technically only power loads of less than 10 MW m(-2) are acceptable. However, strong edge...

Overview of fuel retention in composite and tungsten limiters (2002)

Rubel, M., Philipps, V., Pospieszczyk, A., Tanabe, T., Kötterl, S.

A number of materials, in a form of limiters, have been tested at the TEXTOR tokamak as candidates for plasma facing components in future devices. The results for fuel distribution and content in...

Progress of the European R&D on plasma-wall interactions, neutron effects and tritium removal in ITER plasma facing materials. (2002)

Wu, C.H., Alessandrini, C., Bonal, J.P., Davis, J.W., Haasz, A.A., Jacob, W., ...

21st Symp.on Fusion Technology (SOFT), Madrid, E, September 11-15, 2000

Novel Method to Study SOL-Response to ELMs by Divertor Target Probes in JET (2001)

Jachmich, S., Laux, M., Becoulet, M., Eich, T., Loarte, A., Matthews, G.F., ...

Radiation Distribution and Neutral-Particle Loss in High-Density Plasmas in the JET MKI-IGB Divertor (2001)

Ingesson, C., Fuchs, J.C., Barnsley, R., Coster, D.P., Fundamenski, W., Huber, A., ...

Plasma-Material Interactions in Current Tokamaks and their Implications for Next-Step Fusion Reactors (2001)

Federici, G., Skinner, C.H., Brooks, J.N., Coad, J.P., Grisolia, C., Haasz, A., ...

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors (2001)

Federici, G., Skinner, C. H., Brooks, J. N., Coad, J. P., Grisolia, C., Haasz, A. A., ...

Recent results from Helium plasma operation in JET (2001)