This paper describes the design status of the ITER tritium plant. The key processing requirements and basis for process selection are summarized. Status of the remaining R&D efforts and selection of the process for impurity detritiation are also given. Evaluation studies for preliminary tritium plant...
Tritium processing technologies of the two Europea Utili,M.,Calderoni,... - 《Fusion Science & Technology An International Journal of the American Nuclear Society》 被引量: 0发表: 2015年 Status on the Development of the Fabrication Technology and the Mock-up Qualification Tests for the ITER Blan...
Its function is, among other things, to maintain the tritium cover modules at the correct position when they are attached to the Vacuum Vessel and to distribute / collect the fluids (helium and LiPb in the case of the HCLL Conclusions Main achievements in manufacturing activities for TBM and...
It then moves on to the enhancements required for protection of the Beryllium coated tiles of the ITER Like Wall (ILW) and the high power deuterium-tritium campaigns, followed by several interesting experiments with particular CODAS challenges. Finally, the post operations CODAS legacy is considered...
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This paper describes the design status of the ITER tritium plant. The key processing requirements and basis for process selection are summarized. Status of the remaining R&D efforts and selection of the process for impurity detritiation are also given. Evaluation studies for preliminary tritium plant...
Several institutes of the Forschungszentrum Karlsruhe are currently contributing to tritium-related research for fusion reactors. The overall objective of this work is the provision of sound technologies and proven components for the torus exhaust gas processing system of ITER and investigations into key ...
The evolution of process systems since the beginning of the engineering design activities (EDA) is emphasized. The ITER tritium plant provides high purity mixtures of tritium and deuterium to the fuelling systems for pellet injection, neutral beams, and gas puffing, and processes the plasma exhaust...
Together with a significant advancement in understanding, they have warranted a revisitation of the previous estimates of tritium inventory in ITER, with beryllium as the plasma facing material for the first-wall components, and tungsten in the divertor with some carbon-fibre-composites clad areas, ...
The compliancy with the ITER interface requirements, in terms of space availability, service fluids, limits on tritium release, constraints on maintenance, is driving the design of the TBS tritium processing systems. Other requirements come from the characteristics of the relevant test blanket module ...