Thermal–hydraulic analysis for a sodium-heated steam generator using a multi-shell method |
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| Authors: | Takaaki Sakai Akira Yamaguchi Peter Metz |
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| Affiliation: | a Thermal Hydraulics Research Group, O-arai Engineering Center, Japan Nuclear Cycle Development Institute, 4002 Narita, O-arai, Ibaraki 311-1393, Japan;b System Engineering Group, International Cooperation and Technology Development Center, Japan Nuclear Cycle Development Institute, 1 Shiraki, Tsuruga, Fukui 919-1279, Japan |
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| Abstract: | A multi-shell analysis method has been applied to predict the Thermal–hydraulics in a steam generator of a liquid metal reactor. The method is intended to improve the calculation accuracy for temperature profiles at a wide range of heat exchange rates in a large sized steam generator for the future plant. The calculation accuracy has been examined using experimental 50 MWth steam generator test data that were measured during 1970's–1980's. The calculation results of temperature profiles were compared with experimental data at 20, 30, 50, 75, 90, and 100% of nominal operating condition. Responses for the stepwise flow rate variations were also evaluated. In conclusion, the calculation accuracy for the temperature profile in the steam generator was improved by using the multi-shell analysis method for a wide range of heat exchange rates. |
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