1982•OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)Requires access
Heat enhancement techniques for thermal-hydraulic and thermomechanical testing of fusion blankets in a low power fusion device
L.G. Miller, T. Bohn, G.A. Deis, L.S. Masson, D.E. Wessol
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Abstract
Development of blanket designs for fusion reactors requires module testing at reactor-relevant power densities, which cannot be obtained on near-term devices without augmented heating. Concepts are investigated which will substantially increase fusion blanket bulk heating over that produced by incident flux from a fusion or fission reactor, thus permitting meaningful near-term blanket testing on lower-power fusion devices. Electrical heating is considered and limitations determined for its use. A heat enhancement technique for bulk heating blanket materials is also proposed which uses the high energy released by fission of /sup 235/U. Calculations indicate that doping the blanket module with low percentages (2 to 3 vol %) of /sup 235/UO/sub 2/ will provide heat enhancement exceeding a factor of five. Calculated results of heating profiles for Li/sub 2/O and LiAlO/sub 2/ blankets are presented.