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Knaster J.,IFMIF | Ibarra A.,CIEMAT | Abal J.,Polytechnic University of Catalonia | Abou-Sena A.,Karlsruhe Institute of Technology | And 63 more authors.
Nuclear Fusion | Year: 2015

The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the frame of the Broader Approach Agreement between Europe and Japan, accomplished in summer 2013, on schedule, its EDA phase with the release of the engineering design report of the IFMIF plant, which is here described. Many improvements of the design from former phases are implemented, particularly a reduction of beam losses and operational costs thanks to the superconducting accelerator concept, the re-location of the quench tank outside the test cell (TC) with a reduction of tritium inventory and a simplification on its replacement in case of failure, the separation of the irradiation modules from the shielding block gaining irradiation flexibility and enhancement of the remote handling equipment reliability and cost reduction, and the water cooling of the liner and biological shielding of the TC, enhancing the efficiency and economy of the related sub-systems. In addition, the maintenance strategy has been modified to allow a shorter yearly stop of the irradiation operations and a more careful management of the irradiated samples. The design of the IFMIF plant is intimately linked with the EVA phase carried out since the entry into force of IFMIF/EVEDA in June 2007. These last activities and their on-going accomplishment have been thoroughly described elsewhere (Knaster J et al [19]), which, combined with the present paper, allows a clear understanding of the maturity of the European-Japanese international efforts. This released IFMIF Intermediate Engineering Design Report (IIEDR), which could be complemented if required concurrently with the outcome of the on-going EVA, will allow decision making on its construction and/or serve as the basis for the definition of the next step, aligned with the evolving needs of our fusion community. © 2015 IAEA, Vienna.


Heidinger R.,F4E | Knaster J.,IFMIF EVEDA Project Team | Matsumoto H.,IFMIF EVEDA Project Team | Sugimoto M.,Japan Atomic Energy Agency | And 13 more authors.
Fusion Engineering and Design | Year: 2013

The International Fusion Materials Irradiation Facility (IFMIF) Engineering Design and Engineering Validation Activities (EVEDA) are being developed in a joint project in the framework of the Broader Approach (BA) Agreement between EU and Japan. This project has now entered into a crucial phase as the engineering design of IFMIF is now being formulated in a series of 3 subsequent phases for delivering an Interim IFMIF Engineering Design Report (IIEDR) by mid of 2013. Content of these phases is explained, including the plant configuration detailing the 5 IFMIF facilities and their systems. Together with the Engineering Design Activities, prototyping sub-projects are pursued in the Engineering Validation Activities which consist of the design, manufacturing and testing of the following prototypical systems: Linear IFMIF Prototype Accelerator (LIPAc), EVEDA Lithium Test Loop (ELTL), and High Flux Test Module (HFTM) with the prototypical helium cooling loop (HELOKA). Highlights are described from recent experiments in the Engineering Validation Activities. © 2013 Elsevier B.V. All rights reserved.


Calvi M.,CRPP | Bauer P.,ITER Organization | Bessette D.,ITER Organization | Cau F.,CRPP | And 2 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2010

Based on the functional specification by the ITER organization, CRPP developed a design proposal for the ITER magnet feeder busbar system. The magnetic field level estimated for the operation of the busbars allows the use of NbTi superconductor. The minimum superconducting cross sections and copper stabilizers are calculated based on a temperature margin of 2.5 K and a safe hot spot temperature. Based on these cross sections a busbar cable layout has been identified for each magnet feeder type and the optimization of the parameters performed with thermo-hydraulic codes. The temperature margins have been established considering both AC loss and heat exchange between the magnet coil and the busbars through the twin box joint. The rate of growth of the resistive voltage during a busbar quench was calculated to provide the input required for the design of a reliable quench protection system. © 2006 IEEE.


Martovetsky N.N.,Lawrence Livermore National Laboratory | Hatfield D.R.,Oak Ridge National Laboratory | Miller J.R.,Oak Ridge National Laboratory | Bruzzone P.,CRPP | And 2 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2010

The U.S. Domestic Agency (USDA) is one of six suppliers of the TF conductor for ITER. To ensure that U.S.-made conductors are in compliance with ITER requirements, we prepared several lengths of the Cable-in-Conduit Conductors (CICC) and short samples for testing in the SULTAN facility in CRPP, Switzerland. We also fully characterized the strands that were used in these SULTAN samples. Fabrication experience and test results are presented and discussed. © 2006 IEEE.

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