Adjoint computational divertor engineering/optimization techniques are further elaborated in cooperation with KU Leuven and RWTH Aachen. The concept of “pde constrained
geometrical optimization of the tokamak divertor in reactor relevant conditions. The optimization method is implemented in a MATLAB code which solves iteratively the adjoint and forward 2D edge plasma transport equations of the B2 code (“B2_light”). Ultimate goal of this activity is to create a computational divertor design tool applicable (with reasonable computational turnaround times) for DEMO relevant configurations.
Nuclear Fusion Programme – Progress Report 2013 8. DEMO – The Route to A Power Plant
Introduction
Conceptual studies on the development of a DEMO fusion reactor have been started in the frame of the European PPPT programme, with the goal to demonstrate significant fusion electricity production in 2050. On the way to DEMO, the ITER tokamak currently under construction is expected to contribute important results in various fields like the demonstration of robust and well-controlled burning plasma regimes, including pulsed operation at power amplification Q = 10 and steady-state operation at Q = 5, furthermore the test and optimisation of the conventional physics solution for power and Helium exhaust (standard divertor with semi-detached plasma conditions), the validation of test breeding blanket concepts for Tritium production as well as of various technical components and methods, e.g. superconducting magnet technology, remote handling and plasma heating and diagnostic systems.
However, on the way to towards commercial fusion, ITER will leave several important issues either partially or even fully unresolved. Main open issues are first the durability of plasma-facing and structural materials against the challenging heat loads (plasma heating power of DEMO ~ 4 times that of ITER), neutron embrittlement and primary erosion (for both the total fluence in a DEMO device is assumed to be ~ 50 times that of ITER), second the achievement of Tritium self-sufficiency and finally the demonstration of a substantial net electrical output.
Additionally, DEMO will have to improve further significantly as compared to ITER in the fields of stability and control of plasma operation, optimisation of safety issues and reduction of cost. While the well-developed tokamak principle is currently seen as the leading candidate for DEMO, the stellarator concept (W7-X device and HELIAS studies) is pursued in Europe (and outside) as a promising alternative option. After a successful exploitation of W7-X, the stellarator concept is envisioned to become an attractive alternative to the DEMO tokamak due to its intrinsic advantages: steady-state operation, high density operation and current-free plasma configuration without disruptions.
Based on the experience gained in the past decades, the fusion research team at FZJ team is contributing to the development of DEMO within its main areas of expertise in fusion physics and technology.
Within Germany, the three Helmholtz centres IPP (Garching and Greifswald), KIT (Karlsruhe) and FZJ (Jülich) are closely collaborating on conceptual studies towards fusion power production within the German DEMO working group. Since 2010, two meetings of two days duration each were held every year, addressing a variety of topics from both physics and technology.
Additionally, Jülich has been participating in the EFDA Power plant Physics and Technology (PPPT) programme between 2011 and 2013, with contributions to the system studies (SYS) and power exhaust (PEX) tasks.
The main work topics and results are briefly summarized below.
DEMO system studies
Within 2013, the software tool for system studies for tokamak fusion reactors, which originally had been developed in the programming language Pascal, has been converted towards a modern Phyton version with graphical use interface. It allows the calculation of the main physics issues of fusion power, heat exhaust and pulse duration, while avoiding time-consuming technological or costing optimisations. The tool has been successfully benchmarked against more sophisticated system codes (PROCESS, HELIOS) and thus allows performing fast and reliable parameter variation studies. Using this software tool, two different DEMO models, a more conservative DEMO model with large aspect ratio R/a = 5 and a more advanced DEMO model with R/a = 3, each with net electrical output power of Pel = 1 GW, were developed for further discussion within the German DEMO working group.
Plasma diagnostic and control
The reliable operation and control of the plasma in a magnetic fusion reactor requires a robust plasma scenario combined with an integrated diagnostic and control system. Both elements together, scenario and control, have to ensure machine operation in compliance with safety requirements, achieve high plant availability in particular by keeping distance to all known operational limits, and aim for optimized fusion performance while minimizing the aging of components. Initial studies have been performed on the feasibility of DEMO plasma control, including the definition of measurement requirements and identification of candidate diagnostic systems.
Within 2013, a preliminary list of control functions has been developed for DEMO. Essential quantities to be measured and controlled in a tokamak reactor (and mostly also in a stellarator) are the profiles of particle densities, temperatures and plasma current, furthermore the plasma position and shape, plasma radiation, local wall loads and wall temperatures, plasma instabilities, D/T ratio and fusion power. Except for the fusion power, control schemes for most of the other quantities are already available and continuously under improvement on all current major magnetic fusion experiments. However, already for ITER and even more for a future DEMO fusion reactor, the requirements for the reliability of plasma operation are much more demanding than on any existing device. One specific problem is the stationary power exhaust, where the local power flux densities are near to design limits and must be safely controlled to avoid damage to the target plates. Regarding off-normal transient events in a tokamak reactor, the number of high-power disruptions must be minimized towards almost zero, and the few remaining disruptions have to be reliably mitigated, due to the high risk of significant damage to the first wall.
While present magnetic fusion experiments are amply equipped with diagnostic and actuator systems, their implementation on DEMO will only be possible with reduced performance and/or number of systems, due to several reasons: First, the fraction of openings and voids in the breeding blanket has to be minimized in order to achieve a Tritium breeding rate TBR > 1.
Second, diagnostic front end components will be subject to a harsh environment (radiation, forces, temperatures etc.) and thus may only be installed at some distance behind the first wall or blanket. Third, available actuators on fusion reactors such as magnetic field coils, auxiliary heating, gas inlets, pellet injectors and pumping systems typically can only provide slow, indirect or weak performance in DEMO. In order to achieve reliable machine operation, enhanced long-term stability of both diagnostic systems and actuators, together with redundancy in terms of both number of methods and number of channels, and finally integrated data analysis together with in-situ calibration and consistency checking methods have to be developed and implemented. Following an initial assessment, microwave diagnostics (ECE and reflectometry), IR polarimetry, neutron and gamma diagnostics are regarded as promising on DEMO, while spectroscopic diagnostics may be feasible only with limited performance due to first mirror lifetime issues.
The feasibility of DEMO diagnostic and control is regarded as particularly difficult when going towards high temporal or spatial resolution, specifically in the divertor region or for core plasma profile measurements. Therefore, the controllability of a more sophisticated (high performance) DEMO plasma scenario will strongly depend on the feasibility of the related diagnostic systems, and substantial R&D on DEMO diagnostic and control has to be launched well in time before freezing DEMO design parameters.
Disruptions
Within 2013, the physics properties of disruptions have been analysed and extrapolated towards DEMO conditions. It was found that plasma disruptions on DEMO will release the kinetic plasma energy with a short time of only about 1 – 3 ms (thermal quench), while the inductive energy will be released within a few 10 ms (current quench). While the latter might lead to the generation of a beam of run-away electrons which may eventually hit the first wall and cause local damage (melting), the thermal quench might also approach melting conditions in case of a non-uniform radiation distribution. Therefore it has been concluded that a reliable system for avoidance and mitigation of disruptions has to be developed for DEMO (and to a large extent already for ITER high performance discharges).
Journals refereed 1. Abdullaev S.
On collisional diffusion in a stochastic magnetic field.
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2. Behr W, Faidel D, Fischer K, Pap M, and Offermanns G.
Welding feasibility study of U-shape lips at ITER Port-Plug with new laser beam sources.
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10.1016/j.fusengdes.2013.03.066.
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ICRF specific plasma wall interactions in JET with the ITER-like wall. Journal of nuclear materials, (2013). 438: p. S160 - S165. DOI:
10.1016/j.jnucmat.2013.01.044.
4. Brezinsek S, Jachmich S, Smith R, van Rooij GJ, Ivanova D, Matthews GF, Stamp MF, Meigs AG, Coenen JW, Krieger K, Giroud C, Groth M, Philipps V, and Grünhagen S.
Residual carbon content in the initial ITER-Like Wall experiments at JET.
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5. Brezinsek S, Loarer T, Bucalossi J, Clever M, Coenen JW, Coffey I, Devaux S, Douai D, Freisinger M, Frigione D, Groth M, Huber A, Philipps V, Hobirk J, Jachmich S, Knipe S, Krieger K, Kruezi U, Marsen S, Matthews GF, Meigs AG, Nave F, Nunes I, Esser HG, Neu R, Roth J, Stamp MF, Vartanian S, Samm U, Grünhagen S, Smith R, Felton R, Banks J, Belo P, Boboc A.
Fuel retention studies with the ITER-Like Wall in JET.
Nuclear fusion, (2013). 53(8): p. 083023 -. DOI: 10.1088/0029-5515/53/8/083023.
6. Castaño Bardawil DA, Krasikov Y, Panin A, Neubauer O, and Biel W.
Fast shutter concepts for the new ITER core CXRS upper port plug baseline considering the actuator located inside and outside the port plug.
Proceedings of the 27th Symposium On Fusion Technology, (2013). 88(9-10): p. 2073–2076.
DOI: 10.1016/j.fusengdes.2013.02.012.
7. Clever M, Arnoux G, Balshaw N, Garcia-Sanchez P, Patel K, Sergienko G, Soler D, Stamp MF, Williams J, and Zastrow K-D.
A wide angle view imaging diagnostic with all reflective, in-vessel optics at JET. Proceedings of the 27th Symposium On Fusion Technology, (2013). 88(6-8): p. 1342–1346.
DOI: 10.1016/j.fusengdes.2013.01.038.
8. Coenen JW, Brezinsek S, Neu R, van Rooij GJ, Sertoli M, Stamp MF, JET-EFDA Contributors, Clever M, Coffey I, Dux R, Groth M, Ivanova D, Krieger K, Marsen S, and Meigs A.
Longterm Evolution of the Impurity Composition and Transient Impurity Events with the ITER-like Wall at JET.
24th IAEA Fusion Energy Conference, (2013). 438(Supp 2013): p. 34-41. http://juser.fz-juelich.de/record/141801.
9. Coenen JW, Krieger K, Lipschultz B, Dux R, Kallenbach A, Lunt T, Mueller HW, Potzel S, Neu R, and Terra A.
Evolution of surface melt damage, its influence on plasma performance and prospects of recovery.
Journal of nuclear materials, (2013). 438: p. S27 - S33. DOI: 10.1016/j.jnucmat.2013.01.005.
10. Coenen JW, Sertoli M, Lawson K, Marsen S, Meigs A, Neu R, Puetterich T, van Rooij GJ, Stamp MF, Brezinsek S, Coffey I, Dux R, Giroud C, Groth M, Huber A, Ivanova D, and Krieger K. Long-term evolution of the impurity composition and impurity events with the ITER-like wall at JET.
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11. Dai S, Kirschner A, Matveev D, Borodin D, Björkas C, Sun J, and Wang D.
Modelling of local carbon deposition on a rough test limiter exposed to the edge plasma of TEXTOR.
Plasma physics and controlled fusion, (2013). 55(5): p. 055004 -. DOI: 10.1088/0741-3335/55/5/055004.
12. Ding R, Maddaluno G, Apicella ML, Mazzitelli G, Pericoli Ridolfini V, Kirschner A, Chen JL, Li JG, and Luo G-N.
Modelling of lithium erosion and transport in FTU lithium experiments. Journal of nuclear materials, (2013). 438: p. S690 - S693. DOI:
10.1016/j.jnucmat.2013.01.146.
13. Eren B, Marot L, Meyer E, Ryzhkov IV, Lindig S, Houben A, Wisse M, Skoryk OO, Oberkofler M, Voitsenya VS, and Linsmeier C.
Roughening and reflection performance of molybdenum coatings exposed to a high-flux deuterium plasma.
Nuclear fusion, (2013). 53(11): p. 113013 -. DOI: 10.1088/0029-5515/53/11/113013.
14. Frerichs H, Schmitz O, Reiter D, Cahyna P, Feng Y, and Evans TE.
Numerical sensitivity analysis of divertor heat flux and edge temperature at DIII-D under the influence of resonant magnetic perturbations.
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10.1016/j.jnucmat.2013.01.068.
15. Giroud C, Maddison GP, Joffrin E, Oberkofler M, Lehnen M, Liu Y, Marsen S, McCormick K, Meigs A, Neu R, Sieglin B, van Rooij G, Jachmich S, Arnoux G, Belo P, Brix M, Clever M, Coffey I, Devaux S, Douai D, Eich T, Flanagan J, Grünhagen S, Rimini F, Huber A, Kempenaars M, Kruezi U, Lawson K, Lomas P, Lowry C, Nunes I, Sirinnelli A, Sips ACC, Stamp M, Beurskens MNA, Wiesen S, Balboa I, Brezinsek S, Coelho R, Coenen JW, and Frassinetti L.
Impact of nitrogen seeding on confinement and power load control of a high-triangularity JET ELMy H-mode plasma with a metal wall.
Nuclear fusion, (2013). 53(11): p. 113025 -. DOI: 10.1088/0029-5515/53/11/113025.
16. Groth M, Brezinsek S, Eich T, Flanagan J, Giroud C, Huber A, Jachmich S, Kruezi U, Lehnen M, Lowry C, Maggi CF, Marsen S, Belo P, Meigs AG, Sergienko G, Sieglin B, Silva C, Sirinelli A, Stamp MF, van Rooij GJ, Corrigan G, Harting D, Wiesen S, Beurskens MNA, Brix M, Clever M, and Coenen JW.
Target particle and heat loads in low-triangularity L-mode plasmas in JET with carbon and beryllium/tungsten walls.
Journal of nuclear materials, (2013). 438: p. S175 - S179. DOI:
10.1016/j.jnucmat.2013.01.072.
17. Groth M, Brezinsek S, Guillemaut C, Giroud C, Harting D, Huber A, Jachmich S, Kruezi U, Lawson KD, Lehnen M, Lowry C, Maggi CF, Belo P, Marsen S, Meigs AG, Pitts RA, Sergienko G, Sieglin B, Silva C, Sirinelli A, Stamp MF, van Rooij GJ, Wiesen S, Beurskens MNA, Brix M, Clever M, Coenen JW, Corrigan C, Eich T, and Flanagan J.
Impact of carbon and tungsten as divertor materials on the scrape-off layer conditions in JET.
Nuclear fusion, (2013). 53(9): p. 093016 -. DOI: 10.1088/0029-5515/53/9/093016.
18. Guillemaut C, Pitts RA, Flanagan J, Groth M, Jachmich S, Kruezi U, Marsen S, Strachan J, Wiesen S, Kukushkin AS, Bucalossi J, Corrigan G, Harting D, Huber A, Wischmeier M, Arnoux
G, Brezinsek S, and Devaux S.
EDGE2D-EIRENE modelling of divertor detachment in JET high triangularity L-mode plasmas in carbon and Be/W environment.
Journal of nuclear materials, (2013). 438: p. S638 - S642. DOI:
10.1016/j.jnucmat.2013.01.134.
19. Guszejnov D, Bencze A, Zoletnik S, and Krämer-Flecken A.
Determination of structure tilting in magnetized plasmas—Time delay estimation in two dimensions.
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20. Hakola A, Airila MI, Krieger K, Kurki-Suonio T, Likonen J, Lindholm V, Makkonen T, Mayer M, Miettunen J, Müller HW, Neu R, Petersson P, Björkas C, Rohde V, Rubel M, Widdowson A, Borodin D, Brezinsek S, Coad JP, Groth M, Järvinen A, Kirschner A, and Koivuranta S.
Global migration of impurities in tokamaks.
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21. Huber A, Brezinsek S, Clever M, Coenen JW, Beurskens MNA, Eich T, Jachmich S, Lehnen M, Lerche E, Marsen S, Matthews GF, McCormick K, Groth M, Meigs AG, Mertens P, Philipps V, Rapp J, Samm U, Stamp M, Wischmeier M, Wiesen S, Calabro G, de Vries PC, Riccardo V, van Rooij G, Sergienko G, Arnoux G, Boboc A, and Bilkova P.
Impact of the ITER-like wall on divertor detachment and on the density limit in the JET tokamak.
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10.1016/j.jnucmat.2013.01.022.
22. Huber A, Brezinsek S, Egner S, Farthing J, Hartl M, Horton L, Kampf D, Klammer J, Lambertz HT, Matthews GF, Morlock C, Murari A, Mertens P, Reindl M, Riccardo V, Samm U, Sanders S, Stamp M, Williams J, Zastrow KD, Zauner C, Schweer B, Sergienko G, Terra A, Arnoux G, Balshaw N, Clever M, and Edlingdon T.
A new radiation-hard endoscope for divertor spectroscopy on JET. Fusion engineering and design, (2013). 88(6-8): p. 1361 - 1365. DOI:
10.1016/j.fusengdes.2013.02.053.
23. Huber A, Burdakov A, Sergienko G, Shoshin A, Samm U, Unterberg B, Zlobinski M, Wirtz M, Coenen JW, Linke J, Mertens P, Philipps V, Pintsuk G, and Schweer B.
Investigation of the Impact on Tungsten of Transient Heat Loads Induced by Laser Irradiation, Electron Beams and Plasma Guns.
Fusion science and technology, (2013). 63: p. 197-200. http://juser.fz-juelich.de/record/134982.
24. Huber A, Burdakow A, Sergienko G, Shoshin A, Samm U, Unterberg B, Zlobinski M, Wirtz M, Coenen JW, Linke J, Mertens P, Philipps V, Pintsuk G, and Schweer B.
Investigation of the Impact on Tungsten of Transient Heat Loads induced by Laser Irradiation, Electron Beams and Plasma Guns.
Fusion science and technology, (2013). 63(1T): p. 197-200. http://juser.fz-juelich.de/record/134837.
25. Järvinen A, Groth M, Havlickova E, Jachmich S, Lehnen M, Lönnroth J, Tskhakaya D, JET EFDA Contributors, Moulton D, Strachan J, Wiesen S, Belo P, Beurskens MNA, Corrigan G, Eich T, and Giroud C.
Simulations of tungsten transport in the edge of JET ELMy H-mode plasmas. Journal of nuclear materials, (2013). 438: p. S1005 - S1009. DOI:
10.1016/j.jnucmat.2013.01.219.
26. Kawamura G, Tomita Y, and Kirschner A.
Kinetic effects of inclined magnetic field on physical sputtering by impurity ions. Journal of nuclear materials, (2013). 438: p. S909 - S912. DOI:
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27. Kirschner A, Wienhold P, Philipps V, Pospieszczyk A, Samm U, Schweer B, Borodin D, Björkas C, Van Hoey O, Matveev D, Brezinsek S, Kreter A, Laengner M, and Ohya K.
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28. Klepper CC, Jacquet P, Mayoral M-L, Rimini F, Sergienko G, Van Eester D, Bobkov V, Colas L, Biewer TM, Borodin D, Czarnecka A, Giroud C, Lerche E, and Martin V.
RF sheath-enhanced beryllium sources at JET’s ICRH antennas. Journal of nuclear materials, (2013). 438: p. S594 - S598. DOI:
10.1016/j.jnucmat.2013.01.124.
29. Kondratyev D, Borodin D, Kirschner A, Brezinsek S, Coenen JW, Laengner M, Stoschus H, Vainshtein L, Pospieszczyk A, and Samm U.
Simulation of spectroscopic patterns obtained in W/C test-limiter sputtering experiment at TEXTOR.
Journal of nuclear materials, (2013). 438: p. S351 - S355. DOI:
10.1016/j.jnucmat.2013.01.066.
30. Köppen M, Oberkofler M, Riesch J, Schmid K, Vollmer A, and Linsmeier C.
Quantitative depth-resolved photoelectron spectroscopy analysis of the interaction of energetic oxygen ions with the beryllium–tungsten alloy Be2W.
Journal of nuclear materials, (2013). 438: p. S766 - S770. DOI:
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31. Kotov V, Reiter D, and Wiesen S.
Self-consistent modeling of X-point MARFE and divertor detachment. Journal of nuclear materials, (2013). 438: p. S449 - S452. DOI:
10.1016/j.jnucmat.2013.01.091.
32. Kreter A, Wienhold P, Esser HG, Litnovsky A, Philipps V, Sugiyama K, and Team T.
Long-term carbon transport and fuel retention in gaps of the main toroidal limiter in TEXTOR.
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33. Krimmer A, Kassek G, Allelein HJ, Krasikov Y, and Neubauer O.
Design and testing of secondary mirrors for the core CXRS diagnostic system in ITER.
Fusion engineering and design, (2013). 88(9-10): p. 2021 - 2024. DOI:
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34. Kukushkin AS, Pacher HD, Pacher GW, Kotov V, Pitts RA, and Reiter D.
Consequences of a reduction of the upstream power SOL width in ITER. Journal of nuclear materials, (2013). 438: p. S203 - S207. DOI:
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35. Lang PT, Loarte A, Gribov Y, Horton LD, Lowry C, Martin Y, Neubauer O, Oyama N, Schaffer MJ, Stork D, Suttrop W, Thomas P, Saibene G, Tran M, Wilson HR, Kavin A, Schmitz O, Baylor LR, Becoulet M, Cavinato M, Clement-Lorenzo S, Daly E, Evans TE, and Fenstermacher ME.
ELM control strategies and tools: status and potential for ITER.
Nuclear fusion, (2013). 53(4): p. 043004 DOI: 10.1088/0029-5515/53/4/043004.
36. Linsmeier C, Fu C-C, Décamps B, Ferrero C, Greuner H, Hébert C, Höschen T, Hofmann M, Hugenschmidt C, Jourdan T, Köppen M, Płociński T, Kaprolat A, Riesch J, Scheel M, Schillinger B, Vollmer A, Weitkamp T, Yao W, You J-H, Zivelonghi A, Nielsen SF, Mergia K, Schäublin R, Lindau R, Bolt H, Buffière J-Y, and Caturla MJ.
Advanced materials characterization and modeling using synchrotron, neutron, TEM, and novel micro-mechanical techniques—A European effort to accelerate fusion materials development.
Journal of nuclear materials, (2013). 442(1-3): p. S834 - S845. DOI:
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37. Litnovsky A, Matveeva M, Reichle R, De Temmerman G, Richter S, Breuer U, Buzi L, Möller S, Philipps V, Samm U, Wienhold P, Herrmann A, Rohde V, Mayer M, Sugiyama K, Krieger K, Voitsenya V, Vayakis G, and Costley AE.
First studies of ITER-diagnostic mirrors in a tokamak with an all-metal interior:
results of the first mirror test in ASDEX Upgrade.
Nuclear fusion, (2013). 53(7): p. 073033 DOI: 10.1088/0029-5515/53/7/073033.
38. Litnovsky A, Rudakov DL, Biel W, Brezinsek S, Coenen JW, Kreter A, Kantor M, Lambertz HT, Philipps V, Pospieszczyk A, Samm U, Sergienko G, Bozhenkov S, Schmitz O, Stoschus H, Krasheninnikov SI, Smirnov RD, Ratynskaia S, Bergsåker H, Bykov I, Ashikawa N, De Temmerman G, and Xu Y.
Dust investigations in TEXTOR: Impact of dust on plasma–wall interactions and on plasma performance.
Journal of nuclear materials, (2013). 438: p. S126 - S132. DOI:
10.1016/j.jnucmat.2013.01.020.
39. Meigs AG, Brezinsek S, Clever M, Huber A, Marsen S, Nicholas C, Stamp M, and Zastrow K-D.
Deuterium Balmer/Stark spectroscopy and impurity profiles: First results from mirror-link divertor spectroscopy system on the JET ITER-like wall.
Journal of nuclear materials, (2013). 438: p. S607 - S611. DOI:
10.1016/j.jnucmat.2013.01.127.
40. Mekkaoui A.
Derivation of Stochastic differential Equations for Scrape-off Layer Plasma fluctuations from experimentally measured statistics.
Physics of plasmas, (2013). 20(1): p. 010701. DOI: 10.1063/1.4789453.
41. Mekkaoui A.
Derivation of Stochastic differential Equations for Scrape-off Layer Plasma fluctuations from experimentally measured statistics.
Physics of plasmas, (2013). 20: p. 010701. http://juser.fz-juelich.de/record/155382.
42. Mertens P, Coenen JW, Thompson V, Samm U, Devaux S, Jachmich S, Balboa I, Matthews GF, Riccardo V, Sieglin B, Tanchuk V, and Terra A.
Power handling of the bulk tungsten divertor row at JET: First measurements and comparison to the GTM thermal model.
Fusion engineering and design, (2013). 88(9-10): p. 1778 - 1781. DOI:
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Journal of nuclear materials, (2013). 438: p. S401 - S405. DOI:
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44. Nemov A, Panin A, Borovkov A, Khovayko M, Zhuravskaya E, Krasikov Y, Biel W, and Neubauer O.
Dynamic structural analysis of a fast shutter with a pneumatic actuator. Fusion engineering and design, (2013). 88(9-10): p. 2133 - 2137. DOI:
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45. Neu R, Arnoux G, de Vries PC, Dux R, Frassinetti L, Giroud C, Groth M, Hobirk J, Joffrin E,
Lang P, Lehnen M, Lerche E, Beurskens M, Loarer T, Lomas P, Maddison G, Maggi C, Matthews G, Marsen S, Mayoral M-L, Meigs A, Mertens P, Nunes I, Bobkov V, Philipps V,
Lang P, Lehnen M, Lerche E, Beurskens M, Loarer T, Lomas P, Maddison G, Maggi C, Matthews G, Marsen S, Mayoral M-L, Meigs A, Mertens P, Nunes I, Bobkov V, Philipps V,