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Wiegers S.A.J.,Radboud University Nijmegen | Den Ouden A.,Radboud University Nijmegen | Rook J.,Radboud University Nijmegen | Perenboom J.A.A.J.,Radboud University Nijmegen | And 3 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2010

A 45 T Hybrid Magnet System is being developed at the Nijmegen High Field Magnet Laboratory as part of the Nijmegen Center for Advanced Spectroscopy. The 45 T Hybrid Magnet System will be used in combination with far-infra-red light produced by a Free Electron Laser under construction directly adjacent to the High Field Magnet Laboratory. The superconducting outsert magnet will consist of three CICC coils wound on a single coil form, using Nb3Sn strands. A test program for strand and cable qualification is underway. The CICC will carry 13 kA and the coils will produce 12 T on axis field in a 600 mm warm bore. The nominal operating temperature will be 4.5 K maintained with forced-flow supercritical helium. The insert magnet will produce 33 T at 40 kA in a 32 mm bore consuming 20 MW, and will consist of four coils. The insert magnet will be galvanically and mechanically isolated from the outsert magnet. Complete system availability for users is expected in 2014. In this paper we will report on the conceptual design of the 45 T Hybrid Magnet System. © 2006 IEEE. Source

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. Source

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. Source

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. Source

Pruneri G.,IFMIF EVEDA | Ibarra A.,CIEMAT | Heidinger R.,F4E | Knaster J.,IFMIF EVEDA Project Team | Sugimoto M.,Japan Atomic Energy Agency
Fusion Engineering and Design | Year: 2016

In 2013, the IFMIF, the International Fusion Material Irradiation Facility, presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase, framed by the Broader Approach Agreement between Japan and EURATOM, accomplished in 2013 its mandate to provide the engineering design of the plant on schedule [1]. The IFMIF aims to qualify and characterize materials that are capable of withstanding the intense neutron flux originated in D-T reactions of future fusion reactors due to a neutron flux with a broad peak at 14 MeV, which is able to provide >20 dpa/fpy on small specimens in this EVEDA phase. The successful operation of such a challenging plant demands a careful assessment of the Conventional Facilities (CF), which have adequate redundancies to allow for the target plant availability [2]. The present paper addresses the design proposed in the IFMIF Intermediate Engineering Design Report regarding the CF, particularly the IFMIF's Nuclear and Industrial HVAC design. A preliminary feasibility study, including the initial configuration, calculations and reliability/availability analysis, were performed. The nuclear HVAC design was developed progressively; first, by establishing a conceptual design, starting from the system functional description, followed by the identification of the corresponding interfacing systems and their technical requirements. Once the technical requirements were identified, safety zones were identified based on the radiation classification, frequency dose and parameter of Derivate Air Contamination (DAC). The zone color was determined to match the room's radiation classification. The system design was further developed by defining and creating a Block Diagram with basic and additional information, eventually resulting in a Process Flow Diagram concurrent with the equipment layout definition. Subsequently, we studied and developed the various Piping & instrumentation diagrams (P&ID's), air duct layout and equipment list for different air handling units, air ducting as well as a layout plan of the equipment piping, which was eventually integrated into the 3D model of the building and coordinated with others subsystems of the IFMIF. © 2015 Elsevier B.V. All rights reserved. Source

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