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Perez F.,ALBA Synchrotron Light Facility | Bravo B.,ALBA Synchrotron Light Facility | Sanchez P.,F4E | Salom A.,Elettra - Sincrotrone Trieste
IPAC 2011 - 2nd International Particle Accelerator Conference | Year: 2011

ALBA is a 3 GeV, 400 mA, 3rd generation Synchrotron Light Source under commissioning in Cerdanyola, Spain. The RF System has to provide 3.6 MV of accelerating voltage and restore up to 540 kW of power to the electron beam. For that six RF plants, working at 500 MHz, are foreseen. The RF plants include several new developments: DAMPY cavity; the normal conducting HOM damped cavity developed by BESSY and based in the EU design; six are installed. CaCo; a cavity combiner to add the power of two 80 kW IOTs to produce the 160 kW needed for each cavity. WATRAX; a waveguide transition to coaxial, specially designed to feed the DAMPY cavities due to the geometrical and cooling constrains. Digital LLRF; fully designed at ALBA using commercial components. This paper shortly describes these systems and reports their performance during the ALBA commissioning. Copyright © 2011 by IPAC'11/EPS-AG.

Garcia R.,Spanish University for Distance Education (UNED) | Garcia M.,Spanish University for Distance Education (UNED) | Pampin R.,F4E | Sanz J.,Spanish University for Distance Education (UNED)
Fusion Engineering and Design | Year: 2016

This paper assesses the quality of the EAF-2007 and 2010 activation cross sections for relevant reactions in the determination of the Shutdown Dose Rate (SDDR) in the Port Cell (PC) and Port Interspace (PI) areas of ITER. For each of relevant ITER materials, dominant radionuclides responsible of SDDR and their production pathways are listed. This information comes from a review of the recent reports/papers about SDDR in ITER and own calculations. A total of 26 relevant pathways are found. The quality of these cross sections pathways is assessed following EAF validation procedure, and for those found as not validated last TENDL library versions have been investigated in order to check possible improvements when compared to EAF. The use of EAF libraries is found as trustworthy and it is recommended for the prediction of SDDR in the ITER PC and PI. However, 3 cross section reactions are considered for further improvement: Co59(n,2n)Co58, Cu63(n,g)Cu64 and Cr50(n,g)Cr51. © 2016 Elsevier B.V.

News Article | March 18, 2016
Site: phys.org

One of the biggest and most complex magnets in history is being manufactured at the ASG facilities, Italy. This gigantic "D" shaped coil will be form part of the system that will confine ITER's super-hot plasma which is expected to reach 150 million ˚C. Basically, an impressive magnetic shield will entrap the hot gas and keep it away from the walls of the vessel of the world's biggest fusion machine. F4E is responsible for the supply of 10 out of the 18 TF coils that ITER will need to operate. Witnessing the first TF coil taking shape is a turning point for the project and the 600 people having contributed to this milestone from at least 26 companies. This is the result of various contracts starting in 2008 when F4E started its collaboration with several suppliers for the production of Europe's TF conductor, which reached a length of 20 km. Iberdrola, ASG and Elytt Energy, have used parts of this conductor to manufacture Europe's first TF coil. Winding, sandblasting and heat treatment have been some of the main steps taken in order to fit the conductor into stainless steel plates, known as radial plates, manufactured by CNIM and SIMIC. Piece by piece the conductor had to be lifted, wrapped, insulated and placed back in the grooves of the plates before it got covered. Then, the structure containing the conductor has been laser welded and wrapped with insulating material, before going through impregnation. To create the inner-core of the TF coil, a pack of seven of these structures had to be stacked, electrically jointed, wrapped, insulated and impregnated. Pipes through which cold liquid helium will circulate inside the magnet to help it reach a superconducting state and instruments to measure its performance have also been added. Each of these packs, known as a winding pack in the ITER jargon, is 14 m high, 9 m wide and 1 m thick. Its weight is approximately 110 tonnes which compares to that of a Boeing 747! For Alessandro Bonito-Oliva, F4E's Manager for Magnets, and his team, this has been an accomplishment of significant importance. "Thanks to our determination to meet the tight planning for magnets and the excellent collaboration between F4E and its suppliers we are heading towards Europe's first TF coil, which also happens to be a first for ITER. Seeing a magnet of such complexity taking shape suggests that we can deliver some of the most technically challenging systems of ITER. Sharing expertise and good communication between F4E, ITER International Organization and Japan's Domestic Agency for ITER have been fundamentally important for the achievement of this milestone and will continue to be as production is still ongoing. So what are the next stages for the inner-core of the first TF coil? The stacking of the first pack has been completed and the electrical insulation material is being applied. When its vacuum-pressure insulation is concluded it will be transferred to SIMIC to conduct a series of tests. Then, it will be inserted in the massive case of the coil and in the end the final casting process will be performed, during which additional epoxy resin will be injected to fill in any remaining gaps. And what about the progress of the other TF components? In March the production of radial plates for which F4E is responsible has accelerated reaching 45 out of a total of 70. Meanwhile, the manufacturing of the components of the second TF coil have been completed paving the way for its assembly.

Hirai T.,ITER Organization | Escourbiac F.,ITER Organization | Carpentier-Chouchana S.,Sogeti Inc. | Durocher A.,ITER Organization | And 13 more authors.
Physica Scripta | Year: 2014

The full tungsten divertor qualification program was defined for the R&D activity in domestic agencies. The qualification program consists of two steps: (i) technology development and validation and (ii) a full-scale demonstration. Small-scale mock-ups were manufactured in Japanese and European industries and delivered to the ITER divertor test facility in Russia for high heat flux testing. In parallel activity to the qualification program, both domestic agencies demonstrated that W monoblock technologies withstanding up to 20 MW m-2 were available. © 2014 The Royal Swedish Academy of Sciences.

Knaster J.,IFMIF EVEDA Project Team | Arbeiter F.,Karlsruhe Institute of Technology | Cara P.,F4E | Favuzza P.,ENEA | And 10 more authors.
Nuclear Fusion | Year: 2013

The Engineering Validation and Engineering Design Activities (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF), an international collaboration under the Broader Approach Agreement between Japan Government and EURATOM, aims at allowing a rapid construction phase of IFMIF in due time with an understanding of the cost involved. The three main facilities of IFMIF (1) the Accelerator Facility, (2) the Target Facility and (3) the Test Facility are the subject of validation activities that include the construction of either full scale prototypes or smartly devised scaled down facilities that will allow a straightforward extrapolation to IFMIF needs. By July 2013, the engineering design activities of IFMIF matured with the delivery of an Intermediate IFMIF Engineering Design Report (IIEDR) supported by experimental results. The installation of a Linac of 1.125 MW (125 mA and 9 MeV) of deuterons started in March 2013 in Rokkasho (Japan). The world's largest liquid Li test loop is running in Oarai (Japan) with an ambitious experimental programme for the years ahead. A full scale high flux test module that will house ∼1000 small specimens developed jointly in Europe and Japan for the Fusion programme has been constructed by KIT (Karlsruhe) together with its He gas cooling loop. A full scale medium flux test module to carry out on-line creep measurement has been validated by CRPP (Villigen). © 2013 IAEA, Vienna.

Savoldi Richard L.,Polytechnic University of Turin | Bonifetto R.,Polytechnic University of Turin | Zanino R.,Polytechnic University of Turin | Corpino S.,Polytechnic University of Turin | And 4 more authors.
Fusion Engineering and Design | Year: 2013

The 3D steady-state Computational Fluid Dynamics (CFD) analysis of the ITER vacuum vessel (VV) regular sector #5 is presented, starting from the CATIA models and using a suite of tools from the commercial software ANSYS FLUENT ®. The peculiarity of the problem is linked to the wide range of spatial scales involved in the analysis, from the millimeter-size gaps between in-wall shielding (IWS) plates to the more than 10 m height of the VV itself. After performing several simplifications in the geometrical details, a computational mesh with ∼50 million cells is generated and used to compute the steady-state pressure and flow fields from a Reynolds-Averaged Navier-Stokes model with SST k-ω turbulence closure. The coolant mass flow rate turns out to be distributed 10% through the inboard and the remaining 90% through the outboard. The toroidal and poloidal ribs present in the VV structure constitute significant barriers for the flow, giving rise to large recirculation regions. The pressure drop is mainly localized in the inlet and outlet piping. © 2013 Elsevier B.V. © 2013 Published by Elsevier B.V.

Zanino R.,Polytechnic University of Turin | Richard L.S.,Polytechnic University of Turin | Subba F.,F4E | Corpino S.,Polytechnic University of Turin | And 3 more authors.
Fusion Engineering and Design | Year: 2013

The 3D Computational Fluid Dynamic (CFD) steady state analysis of the regular sector #5 of the ITER vacuum vessel (VV) is presented in these two companion papers using the commercial software ANSYS-FLUENT®. The pure hydraulic analysis, concentrating on flow field and pressure drop, is presented in Part I. This Part II focuses on the thermal-hydraulic analysis of the effects of the nuclear heat load. Being the VV classified as safety important component, an accurate thermal-hydraulic analysis is mandatory to assess the capability of the water coolant to adequately remove the nuclear heat load on the VV. Based on the recent re-evaluation of the nuclear heat load, the steady state conjugate heat transfer problem is solved in both the solid and fluid domains. Hot spots turn out to be located on the surface of the inter-modular keys and blanket support housings, with the computed peak temperature in the sector reaching ∼290 C. The computed temperature of the wetted surfaces is well below the coolant saturation temperature and the temperature increase of the water coolant at the outlet of the sector is of only a few C. In the high nuclear heat load regions the computed heat transfer coefficient typically stays above the 500 W/m2 K target. © 2013 Elsevier B.V. © 2013 Published by Elsevier B.V.

News Article | March 2, 2017
Site: www.eurekalert.org

Tecnalia has a large network of accredited laboratories and qualified staff with extensive experience in the field of testing and characterization of materials and parts. This capacity and knowledge allows Tecnalia to offer a wide range of services (testing, assessment, diagnosis, consulting...) in the different areas related to material and parts properties (mechanical, chemical, etc.). Our laboratories are accredited according to national and international quality standards and feature multiple authorisations. In the execution of this contract, Tecnalia will work with other laboratories for some specific tests, and we should highlight the collaboration with SCI, S.A. which will be responsible for conducting non-destructive tests (NDT). ITER is a first-of-a-kind global collaboration. It will be the world's largest experimental fusion facility and is designed to demonstrate the scientific and technological feasibility of fusion power. It is expected to produce a significant amount of fusion power (500 MW) for about seven minutes. Fusion is the process which powers the sun and the stars. When light atomic nuclei fuse together form heavier ones, a large amount of energy is released. Fusion research is aimed at developing a safe, limitless and environmentally responsible energy source. Europe will contribute almost half of the costs of its construction, while the other six parties to this joint international venture (China, Japan, India, the Republic of Korea, the Russian Federation and the USA), will contribute equally to the rest. The components that make up ITER are being manufactured by each of the participating parties and contributed in kind through so-called Domestic Agencies including Fusion for Energy (F4E) as the European Agency. The site of the ITER project is in Cadarache, in the South of France. In many cases the engineering and technologies required to manufacture these components are very advanced. On the other hand, the performance of materials is crucial for the operation of fusion reactors, so their quality needs to be assured with high certitude. Material characterizations and non-destructive testing are needed in order to support the construction and development of components and materials for ITER and other fusion related facilities under the responsibility of F4E. The contract concerns the materials at room and elevated temperatures, which are present in particular in the vacuum vessel and in-vessel components operating normally between RT and 200 ºC, but higher peak temperatures are also expected during the operation of ITER.

Girard S.,CNRS Hubert Curien Laboratory | Kuhnhenn J.,Fraunhofer Institute For Naturwissenschaftlich Technische Trendanalysen | Gusarov A.,Belgian Nuclear Research Center | Brichard B.,F4E | And 4 more authors.
IEEE Transactions on Nuclear Science | Year: 2013

In this review paper, we present radiation effects on silica-based optical fibers. We first describe the mechanisms inducing microscopic and macroscopic changes under irradiation: radiation-induced attenuation, radiation-induced emission and compaction. We then discuss the influence of various parameters related to the optical fiber, to the harsh environments and to the fiber-based applications on the amplitudes and kinetics of these changes. Then, we focus on advances obtained over the last years. We summarize the main results regarding the fiber vulnerability and hardening to radiative constraints associated with several facilities such as Megajoule class lasers, ITER, LHC, nuclear power plants or with space applications. Based on the experience gained during these projects, we suggest some of the challenges that will have to be overcome in the near future to allow a deeper integration of fibers and fiber-based sensors in radiative environments. © 1963-2012 IEEE.

Spears W.R.,F4E
IEEE Transactions on Plasma Science | Year: 2014

The construction of the JT-60SA tokamak is one of the three projects of the Broader Approach activities being undertaken jointly by Japan and Europe. The construction of the new load assembly and the refurbishment of some reutilized equipment from JT-60U is now well underway, and is on track to produce its first plasma in March 2019. As a satellite tokamak of ITER, and being superconducting, JT-60SA has the objective of supporting ITER in its operation as well as complementing ITER in the definition of the design basis of DEMO, particularly to identify the best ways to extend plasma pulse lengths toward steady state. © 2014 IEEE.

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