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Overview of the JET results in support to ITER
The 2014-2016 JET results are reviewed in the light of their significance for optimising the ITER research plan for the active and non-active operation. More than 60 h of plasma operation with ITERExpand
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The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European - Japanese project towards a Li(d,xn) fusion relevant neutron source
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. Expand
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Failure mode and effect analysis on ITER heat transfer systems
The complexity of the ITER (International Thermonuclear Experimental Reactor) plant and the inventories of radioactive materials involved in its operation require a systematic approach to perform detailed safety analyses during the various stages of the project in order to demonstrate compliance with the safety requirements. Expand
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Scaled experiment for Loss of Vacuum Accidents in nuclear fusion devices: Experimental methodology for fluid-dynamics analysis in STARDUST facility
A recognized safety issue for future fusion reactors fueled with deuterium and tritium is the generation of sizeable quantities of dust. Activated dust mobilization during a Loss of Vacuum AccidentsExpand
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Dust Mobilization Experiments in the Context of the Fusion Plants - STARDUST Facility
This paper deals with the dust mobilization in fusion facilities, in which the plasma disruptions induce an erosion of small particles causing external releases if accidents occur. In the TIER safetyExpand
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Validation of a loss of vacuum accident (LOVA) Computational Fluid Dynamics (CFD) model
Abstract Intense thermal loads in fusion devices occur during plasma disruptions, Edge Localized Modes (ELM) and Vertical Displacement Events (VDE). They will result in macroscopic erosion of theExpand
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Validation of the ECART code for the safety analysis of fusion reactors
Abstract Realistic calculation of the radiotoxic substances transport within a fusion facility requires a coupling among thermal–hydraulic, chemistry and aerosol-vapour models. The paper introducesExpand
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Ex-Vessel Break in ITER Divertor Cooling Loop Analysis with the ECART Code
A hypothetical double-ended pipe rupture in the ex-vessel section of the International Thermonuclear Experimental Reactor (ITER) divertor primary heat transfer system during pulse operation has beenExpand
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ITER Safety Analyses with ISAS
Integrated Safety Analysis System of codes (ISAS), which allows users to integrate existing computer codes in a coherent manner. Expand
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ITER Reference Accidents
Abstract Reference accidents are selected to envelope possible accident sequences to confirm the adequacy of ITER's safety design. Analyses of ITER reference accidents were carried out starting fromExpand
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