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As the construction of a fusion demonstration reactor, DEMO, for demonstrating competitive electrical power generation will be the next important program milestone after ITER, the timely availability of a sound materials database has become an indispensable element in international fusion road maps.
Recent divertor designs for future fusion demonstration reactors include dispersion strengthened tungsten as structural material.
Plasma facing components of tokamak reactors such as ITER or the Korean fusion demonstration reactor (K-DEMO) can be subjected to damage by plasma instabilities.
A major design philosophy for the initiated conceptual design study for a steady-state Korean fusion demonstration reactor (K-DEMO) is engineering feasibility.
The concept of Chinese Fusion Engineering Testing Reactor (CFETR) was proposed to fill the gap between International Thermonuclear Experimental Reactor ITERR) and fusion demonstration plant.
The establishment of technology bases required for the development of a fusion demonstration reactor (DEMO) has been discussed by a joint effort throughout the Japanese fusion community.
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In the frame of the EUROfusion Consortium programme, the Water Cooled Lithium Lead (WCLL) option has been chosen as a candidate for the breeding blanket (BB) of the European fusion power demonstration plant (DEMO) conceptual design.
In the frame of the newly established EUROfusion WPBB Project for the period 2014 2018, four breeding blanket options are being investigated to be used in the fusion power demonstration plant DEMO.
In Europe (EU), in the frame of the EUROfusion consortium activities, four Breeding Blanket (BB) concepts are being developed with the aim of fulfilling the performances required by a near-term fusion power demonstration plant (DEMO) in terms of tritium self-sufficiency and electricity production.
The high average power laser program is developing an inertial fusion energy demonstration power reactor with a solid first wall chamber.
The status and key issues of reduced activation ferritic/martensitic (RAFM) steels R&D are reviewed as the primary candidate structural material for fusion energy demonstration reactor blankets.
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