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Eggenstein-Leopoldshafen, Germany

Spaeh P.,Karlsruhe Institute of Technology | Spaeh P.,Institute for Materials Research I | Aiello G.,Karlsruhe Institute of Technology | Aiello G.,Institute for Materials Research I | And 16 more authors.
Fusion Engineering and Design | Year: 2011

Four ITER EC H&CD (Electron Cyclotron Heating and Current Drive) Upper Launchers will be installed in the ITER Tokamak to counteract plasma instabilities by injection of up to 20 MW of millimeter-wave power at 170 GHz. Each Launcher features a structural system which is equipped with eight beam lines in a Front-Steering arrangement. The Launcher development has reached the status of a preliminary design, since the corresponding review meeting was held in November 2009 at the ITER site in Cadarache. All design work is performed by several EU associations being contracted by Fusion for Energy (F4E). The structural design of the Upper Launcher consists of three sub-components: First of all the Blanket Shield Module (BSM), which fills the gap between the regular blankets. The BSM dissipates about 80% of the nuclear heating and envelopes the front mirrors of the mm-wave system. Further the Launcher Mainframe, which provides a rigid structure for precise and secure integration of the mm-wave system to guarantee reliable operation under all potential scenarios. Finally the internals, such as dedicated support structures for the mm-wave system, shielding elements and components for gas and coolant supply. The most challenging design aspects are proper dissipation of nuclear heating in zones of high heat flux, the mechanical integrity during plasma disruptions, the integration of sufficient shielding material and the precise alignment of the mm-wave system under tight space conditions. Furthermore the definition of efficient manufacturing routes with respect to tolerance compliance requires substantial investigation and, though the Launcher is designed for ITER lifetime, potential repair by adequate remote handling procedures must be considered. This paper presents the recent status of the preliminary structural design and outlines future design approaches with the main focus on manufacturing methods, remote handling capability of the sub-components and optimum integration of the internals to bring the EC Launcher towards the final design. © 2011 Published by Elsevier B.V. Source

Maione I.A.,Institute for Neutron Physics and Reactor Technology | Marracci M.,University of Pisa | Tellini B.,University of Pisa
Fusion Engineering and Design | Year: 2013

This work is mainly focused on the study of remanent magnetization of in-vessel components for DEMO fusion reactor and its effect on remote handling procedures. In particular a DEMO reactor configuration based on multi module segment (MMS) design in vertical maintenance is investigated. The system has been analyzed considering the reference magnetic properties of EUROFER97 and of similar Fe-9Cr steel characterized by the authors. The numerical analysis of the EM forces acting on the blanket segment is performed using the commercial ANSYS© code for which a procedure to consider a demagnetization curve with non-zero coercive field for non-permanent magnets has been developed. © 2013 Elsevier B.V. Source

Lazaro A.,European Commission | Schikorr M.,Institute for Neutron Physics and Reactor Technology | Mikityuk K.,Paul Scherrer Institute | Ammirabile L.,European Commission | And 12 more authors.
Nuclear Engineering and Design | Year: 2014

The new reactor concepts proposed in the Generation IV International Forum require the development and validation of computational tools able to assess their safety performance. In the first part of this paper the models of the ESFR design developed by several organisations in the framework of the CP-ESFR project were presented and their reliability validated via a benchmarking exercise. This second part of the paper includes the application of those tools for the analysis of design basis accident (DBC) scenarios of the reference design. Further, this paper also introduces the main features of the core optimisation process carried out within the project with the objective to enhance the core safety performance through the reduction of the positive coolant density reactivity effect. The influence of this optimised core design on the reactor safety performance during the previously analysed transients is also discussed. The conclusion provides an overview of the work performed by the partners involved in the project towards the development and enhancement of computational tools specifically tailored to the evaluation of the safety performance of the Generation IV innovative nuclear reactor designs. © 2014 The Authors. Published by Elsevier B.V. Source

Weinhorst B.,Institute for Neutron Physics and Reactor Technology | Fischer U.,Institute for Neutron Physics and Reactor Technology | Lu L.,Institute for Neutron Physics and Reactor Technology | Strauss D.,Applied Materials | And 3 more authors.
Fusion Engineering and Design | Year: 2015

The electron cyclotron-heating upper launcher (ECHUL) will be installed in four upper ports of the ITER tokamak thermonuclear fusion reactor. Each ECHUL is able to deposit 8 MW power into the plasma for plasma mode stabilization via microwave beam lines. An essential part of these beam lines are the diamond windows. They are located in the upper port cell behind the bioshield to reduce the radiation levels to a minimum. The paper describes the first detailed neutronic modelling of the ECHUL port cell with ECHUL equipment. The bioshield plug is modelled including passageways for the microwave beam lines, piping and cables looms as well as rails and openings for ventilation. The port cell is equipped with the beam lines including the diamond windows, the beam lines mounting box, conduit boxes and rails. The neutrons are transported into the port cell starting from a surface source in front of the bioshield. Neutronic results are obtained for radiation levels in the port cell at different positions, mainly focusing on the diamond windows position. It is shown that the radiation level is below the limit for maintenance in the port cell. The radiation level at the diamond window is very low and should not influence its performance. © 2015 Elsevier B.V. Source

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