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Choi, K.-S.; Yim, J.-S.; Kim, I.-K.; Kim, K.-T.
Transactions of the 12. international conference on structural mechanics in reactor technology (SMiRT). Volume C: Fuel, core structures, and fuel element storage. Volume D: Performance and life cycle management of operating reactors1993
Transactions of the 12. international conference on structural mechanics in reactor technology (SMiRT). Volume C: Fuel, core structures, and fuel element storage. Volume D: Performance and life cycle management of operating reactors1993
AbstractAbstract
[en] In PWR the rod cluster control assembly (RCCA) for shutdown is released upon the action of the control drive mechanism and falls down through the guide thimble by its weight. Drop time and impact velocity of the RCCA are two key parameters with respect to reactivity insertion time and the mechanical integrity of fuel assembly. Therefore, the precise control of the drop time and impact velocity is prerequisite to modifying the existing design features of the RCCA and guide thimble or newly designing them. During its falling down into the core, the RCCA is retarded by various forces acting on it such as flow resistance and friction caused by the RCCA movement, buoyancy mechanical friction caused by contacting inner surface of the guide thimble, etc. However, complicated coupling of the various forces makes it difficult to derive an analytical dynamic equation for the drop time and impact velocity. This paper deals with the development of a computer program containing an analytical dynamic equation applicable to the Korean Fuel Assembly (KOFA) loaded in the Korean nuclear power plants. The computer program is benchmarked with an available single control rod drop tests. Since the predicted values are in good agreements with the test results, the computer program developed in this paper can be employed to modify the existing design features of the RCCA and guide thimble and to develop their new design features for advanced nuclear reactors. (author)
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Kussmaul, K.F. (ed.); 487 p; ISBN 0-444-81515-5; ; 1993; p. 179-184; SMiRT 12: 12. international conference on structural mechanics in reactor technology; Stuttgart (Germany); 15-20 Aug 1993; 2 refs, 6 figs, 1 tab
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Conference
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