Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione

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012 progress report 2010 Table 1.I – Summary of FTU operations in 2010 Jan. Feb. March April May June July Total Total pulses (p) 11 0 0 22 0 283 33 349 Successful pulses (sp) 9 0 0 19 0 262 30 320 I(sp) 0.82 0.86 0.93 0.91 0.92 Potential experimental days 3.5 0.0 3.5 0.0 10.0 6.0 23.0 Real experimental days 0.5 0.0 1.0 0.0 10.0 1.0 12.5 I(ed) 0.14 0.29 1.00 0.17 0.54 Experimental minutes 134 0 287 0 4476 500 5397 Delay minutes 119 0 345 0 1735 155 2354 I(et) 0.53 0.45 0.72 0.76 0.70 A(sp/d) 18.00 19.00 26.20 30.00 25.60 A(p/d) 22.00 22.00 28.30 33.00 27.92 Delay per system (minutes) Jan. Feb. MarchApril May June July Total % Machine 94 0 0 12 0 339 42 487 20.7 Power supplies 10 0 0 83 0 599 33 725 30.8 Radiofrequency 0 0 0 0 0 0 0 0 0.0 Control system 0 0 0 0 0 108 0 108 4.6 DAS 0 0 0 0 0 44 0 44 1.9 Feedback 0 0 0 0 0 84 0 84 3.6 Network 0 0 0 0 0 0 0 0 0.0 Diagnostic systems 0 0 0 39 0 115 30 184 7.8 Analysis 12 0 0 0 0 283 50 345 14.7 Others 3 0 0 211 0 163 0 377 16.0 TOTAL 119 0 0 345 0 1735 155 2354 100 An upgrade of the present FTU feedback control system was started, also envisaging a possible reutilization in the proposed FAST experiment. A pre–existent framework called multithreaded application real–time executor (MARTe), already successfully used in other European tokamak devices, was adopted. MARTe has been integrated in the current control structure and pulse programming interface, thus providing a common environment with other MARTe systems already running in FTU, such as the real time version of the plasma equilibrium reconstruction RT–ODIN and the satellite station that minimizes the LH reflected power. 50 40 30 20 10 0 Figure 1.2 – 2010 ITM–TF users grouped by country F D I UK FINCH PL P S EU A CZ GR NL B DK RO CY E H IRLRUSLO US NaN ITM Task Force Gateway. The Gateway operations have continued to provide the full scale support to Integrated Tokamak Modelling–Task Force (ITM–TF) users, thus allowing them to develop ITM software and data access facilities. It has been carried out by means of the Gateway trouble ticket system and direct support by email. A number of 223 ITM–TF users have got an account onto the Gateway in 2010 as depicted in figure 1.2. The development & testing activity of the ITM–TF users is reported as CPUs
magnetic confinement (cont’d.) progress report 2010 013 % CPU usage 100 EFDA-ITM batch cluster yearly usage 0 Jan 01 Mar 01 May 01 Jul 01 Sept 01 Nov 01 Total CPU load % Current: 2% Average: 9% Maximal: 100% Figure 1.3 – CPUs yearly usage of the Gateway batch cluster yearly usage of the Gateway batch cluster in 2010 and shown in figure 1.3. The upgrade activity has been carried out involving the base software (operating system, parallel filesystem, distributed filesystem) and scientific tools as well. The Storage Data Area used in 2010 is as follow: 4.3 TB for users and software repositories stored under the distributed filesystem, 14 TB for simulation data stored under the parallel filesystem. The RAM resources of Front–End nodes have been updated to 32 GB for each one, to take into account the heavy CPU usage due to the interactive sessions during Code Camp meeting. Several EU Code Camp 2010 meetings were supported by using hardware/software resources of the Gateway. The Inter–operability between ITM Gateway and High Performance Computing For Fusion (HPC–FF) has been implemented fully. It allows both HPC facilities to be used in a common operating environment for sharing codes, data exchange and user access, as well as joint tools and libraries to facilitate the creation of community fusion codes. 1.2 FTU Experimental Activity Lower hybrid Lower hybrid current drive experiments in plasma regimes of interest for ITER. The need for non–ohmic steady–state current drive is a fundamental weakness of the tokamak as a magnetic fusion reactor. Low frequency microwaves, in the range of a few GHz, have been successfully used to drive current in tokamak core plasmas at relatively low densities [1.1–1.3], but extrapolation of these results to the higher densities of ITER and subsequent reactor grade plasmas has proved to be problematic, because the coupled LH power stubbornly localizes in the plasma edge region [1.4,1.5]. A thermonuclear plant needs to maximise the bootstrap current for saving current driven by external power sources. For this reason ITER will need to operate with almost flat radial profiles such that high pressure gradient occur in the external region of the plasma column with high densities even at the edge (at normalized minor radius r/r LCMS ∼0.9: n e_0.9 ≥0.7×10 20 m –3 , and in the centre: n e0 ≥0.8×10 20 m –3 , where r LCMS is the plasma minor radius at the last closed magnetic field surface (LCMS)). The operation with relatively high plasma density in the region of the periphery is thus an important constraint to be considered for designing a tool for driving actively non–inductive current in the plasma, which is essential for obtaining the necessary requirements of stability and confinement. Theoretical and experimental works have been extensively carried out on FTU, which have evidenced the role of parametric instabilities (PI) in inhibiting penetration of the lower hybrid wave to the plasma core when operating at relatively high plasma densities [1.4,1.5]. These works have produced the guidelines used in the FTU experiments, based on theoretical predictions that the PI–produced spectral broadening would diminish under operations with higher electron temperatures at the periphery (T e_outer ) of the plasma column [1.3]. As a result of operating in such a regime, the spectral broadening measured by radio–frequency (rf) probe has been indeed observed to diminish. It has also been observed that the LH power penetration into a high density core took place as expected. The following options, available on the FTU device, have been exploited for producing different plasma edge temperatures in high–density plasmas, and different plasma targets for LH power coupling: i) Toroidal or poloidal limiter operations. With toroidal limiter operations, a stronger plasma–wall interaction occurs due to the larger plasma–wall contact area. In these conditions lower recycling of particles from the vessel walls and
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