Abstract
In an HTGR core consisting of graphite blocks, leakage flows of the coolant gas through gaps between blocks have unfavorable effects on the core thermal hydraulics such as the increase of the block thermal stresses and fuel temperature. A seal mechanism consisting of plate-type graphite seal elements has been devised in the design of High Temperature Engineering Test Reactor to prevent the leakage flows through gaps between core support blocks.Experiments using air and He gas were conducted to study leakage flow characteristics of this seal mechanism under various conditions of the core support block relative displacements. The pressure loss coefficients were determined from the experiments and the design criteria were found to be satisfied by the present seal mechanism. It is also found that leakage flow characteristics of a plate-type seal mechanism were very sensitive to the wedge-shaped type block displacements.
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More From: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
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