Under the APEX program the He-cooled system design task is to evaluate and recommend high power density refractory alloy first wall and blanket designs and to recommend and initiate tests to address critical issues. We completed the preliminary design of a helium-cooled, W–5Re alloy, lithium breeder design and the results are reported in this paper. Many areas of the design were assessed, including material selection, helium impurity control, and mechanical, nuclear and thermal hydraulics design, and waste disposal, tritium and safety design. Systems study results show that at a closed cycle gas turbine (CCGT) gross thermal efficiency of 57.5%, a superconducting coil tokamak reactor, with an aspect ratio of 4, and an output power of 2 GWe, ...
A study of self-cooled lithium blankets was carried out to define the performance of these blankets ...
An investigntion was made of the performance of a gas-cooled reactor, designed to provide a source o...
Results of work performed from January 1, 1977 through March 31, 1977 on the Advanced Gas Cooled Nuc...
Under the APEX program, the goal for the helium-cooled system design task is to evaluate and recomme...
Under the APEX program [11–1], the goal for the He-cooled system design task is to evaluate and reco...
An aggressive low aspect ratio scoping fusion reactor design indicated that a 2 GW(e) reactor can ha...
A He-V-Li blanket design was developed as a candidate for the U.S. fusion demonstration power plant....
Among the concepts considered in the Advanced Power Extraction (APEX) study is the He-cooled refract...
International audienceIn the framework of the European “HORIZON 2020” innovation and research progra...
Existing and potential design problems associated with the helium-cooled blanket assemblies of exper...
Within the framework of EUROfusion R&D activities, CEA-Saclay has carried out an investigation o...
The International Thermonuclear Reactor (ITER) will have a single-null divertor with total power flo...
refractory heatsinks for plasma facing components that can operate at high temperatures as part of a...
The EUROfusion Consortium develops a design of a fusion power demonstrator plant (DEMO) in the frame...
International audiencehe Helium Cooled Lithium Lead (HCLL) blanket is one of the candidate European ...
A study of self-cooled lithium blankets was carried out to define the performance of these blankets ...
An investigntion was made of the performance of a gas-cooled reactor, designed to provide a source o...
Results of work performed from January 1, 1977 through March 31, 1977 on the Advanced Gas Cooled Nuc...
Under the APEX program, the goal for the helium-cooled system design task is to evaluate and recomme...
Under the APEX program [11–1], the goal for the He-cooled system design task is to evaluate and reco...
An aggressive low aspect ratio scoping fusion reactor design indicated that a 2 GW(e) reactor can ha...
A He-V-Li blanket design was developed as a candidate for the U.S. fusion demonstration power plant....
Among the concepts considered in the Advanced Power Extraction (APEX) study is the He-cooled refract...
International audienceIn the framework of the European “HORIZON 2020” innovation and research progra...
Existing and potential design problems associated with the helium-cooled blanket assemblies of exper...
Within the framework of EUROfusion R&D activities, CEA-Saclay has carried out an investigation o...
The International Thermonuclear Reactor (ITER) will have a single-null divertor with total power flo...
refractory heatsinks for plasma facing components that can operate at high temperatures as part of a...
The EUROfusion Consortium develops a design of a fusion power demonstrator plant (DEMO) in the frame...
International audiencehe Helium Cooled Lithium Lead (HCLL) blanket is one of the candidate European ...
A study of self-cooled lithium blankets was carried out to define the performance of these blankets ...
An investigntion was made of the performance of a gas-cooled reactor, designed to provide a source o...
Results of work performed from January 1, 1977 through March 31, 1977 on the Advanced Gas Cooled Nuc...