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Murdoch, D.*; Beloglazov, S.*; Boucquey, P.*; Chung, H.*; Glugla, M.*; 林 巧; Perevezentsev, A.*; Sessions, K.*; Taylor, C.*
Fusion Science and Technology, 54(1), p.3 - 8, 2008/07
被引用回数：21 パーセンタイル：78.82(Nuclear Science & Technology)One of the key activities on ITER during 2007 is a Design Review covering selected high priority areas of the project in which a significant number of features of the design with the potential to compromise the achievement of some objectives of ITER have been identified. These issues are being addressed by a number of focused working groups to develop solutions, which will improve the ITER design in terms of operating margins, reliability and availability, compliance with the French licensing framework and other respects. One of the working groups, WG-7, has been set up to investigate tritium related issues. The principal design features which are being addressed by WG-7 and the proposed resolutions of these issues are described in this paper, such as atmosphere and vent detritiation systems.
Glugla, M.*; Beloglazov, S.*; Carlson, B.*; Cho, S.*; Cristescu, I.*; Cristecu, I.*; Chung, H.*; Girard, J.-P.*; 林 巧; Mardoch, D.*; et al.
no journal, ,
For the operation of ITER with equimolar DT mixtures a rather complex chemical plant -the ITER tritium plant - is needed. Fuel cycle systems are designed to process considerable and unprecedented DT flow rates with high flexivility and reliability. Multiple confinement of tritium will be achieved through passive physical barriers and active detritiation systems. High decomtamination factor for effluent and release streams and low tritium inventories in all systems are required to minimize chronic and accidental emissions, respectively. The paper will provide an update of all aspects of the ITER tritium plant design, will report on construction supporting R&D and will identify issues remaining for the immediate future.
