Reactor core thermohydraulic transients with thermohydrodynamic coupling |
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| Authors: | Katsuhiro Sakai |
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| Affiliation: | Osaka University, Department of Nuclear Engineering, Faculty of Engineering, 2-1 Yamadaoka, Sulta City, Osaka, Japan;Mitsubishi Atomic Power Industries, Inc., Advanced Reactors Engineering Dept., 2-4-1 Shibakoen Minatoku, Tokyo, Japan |
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| Abstract: | A study of the reactor core thermohydraulics in an LMFBR has been performed for the strongly coupled thermo-hydrodynamic transients. A numerical method to solve the coupled energy-momentum equations among multichannels in a core is presented and the computer code ORIFS-TRANSIENT has been developed.The results of sample calculations for a flow coastdown transient to natural circulation following a reactor scram in a typical loop-type LMFBR are as follows: (1) the inter-subassembly coolant flow redistribution due to buoyancy forces is significant under the low flow condition, such as natural circulation; (2) the maximum coolant temperature was decreased by about 80°C (corresponding to about 22% in terms of hot channel factor) due to the flow redistribution; (3) due to thermohydrodynamic coupling between upper plenum and other regions, the maximum coolant temperature was decreased by about 9°C; (4) due to inter-subassembly heat redistribution, the maximum coolant temperature was increased by about 7°C. |
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