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In the frame of the power plant conceptual studies (PPCS) launched by the European Commission, two main blanket handling concepts have been investigated with respect to engineering feasibility and the impact on the plant availability and on cost: the large module handling concept (LMHC) and the large sector handling concept (LSHC).
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The number of blanket modules has been minimized according to smaller dimensions of the machine and a higher payload capacity of the blanket Remote Handling tool.
It is applicable for the ITER blanket remote handling system.
As a conclusion, major issues for the control system have been solved and the ITER blanket remote handling system becomes further feasible.
This paper presents an overview of the design of the ITER blanket remote handling system (BRHS), an indispensable component for ITER operation because the high irradiation environment will not allow humans to perform in-vessel maintenance activities.
The simulator will be modified further, with addition of other necessary functions, and will finally serve as a prototype of the actual simulator for the blanket remote handling system, which will be procured as part of an in-kind contribution.
Based on the technical design requirements of China Fusion Engineering Test Reactor CFETRR) blanket remote handling (RH) maintenance, this paper focus on the control method of achieving high synchronization accuracy of electro-hydraulic servo system.
Several R&Ds for the ITER blanket remote handling system had been performed from the Engineering Design Activity phase until now and only several technical issues regarding the control system remained such as noise caused by slip ring, control of cable handling system, signal transmission through very long cable and radiation-hard amplifier.
The ITER agreement, which entered into force in the last year, formally decided that Japan will procure the blanket remote handling system and the JAEA, as the Japanese Domestic Agency, is continuing several R&Ds so that the system can be procured smoothly.
An impact hammer test of the full-scale mock-up of the ITER blanket remote handling system (BRHS) was carried out to validate the results of the seismic analysis of the BRHS which were performed using a finite element (FE) model.
This paper presents the conceptual design of the Blanket Remote Handling System (BRHS), which mainly comprises the In-Vessel-Maintenance-System (IVMS), Lifting System and Blanket-Tool-Manipulator System (BTMS).
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