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This study reports on design, modelling and computer code development, relevant to a blanket model and its thermal-hydraulic and tritium mass transport capability and performance. The model includes all the heat and mass transfer processes that occur in the blanket and allows examination of the thermal behaviour with time and under thermal load varying conditions, including the prediction of tritium mass transfer, release, diffusion and recovery behaviour, and corresponding rates in the blanket. The model is used to perform scoping and technology assessment studies for power plant relevent parameters. The model and code also have the capability to analyse accident scenarios of candidate blanket concepts and test neutronic performance of various material configurations.

Additional information

Authors: KARDITSAS P J, AEA Fusion, Culham Laboratory, Abingdon, Oxon. (GB)
Bibliographic Reference: Report: UKAEA FUS 270 EN (1994) 15 pp.
Availability: Available from the Librarian, UKAEA, Culham Laboratory, Abingdon, Oxon. OX14 3DB (GB)
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