Development of natural circulation analysis methods for a sodium cooled fast reactor |
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Authors: | Kazuhiro Oyama Junji Endo Norihiro Doda Ayako Ono Takahiro Murakami Osamu Watanabe |
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Affiliation: | 1. Mitsubishi FBR Systems (MFBR), Inc., 2-34-17 Jingumae, Shibuya-ku, Tokyo 150-0001, Japan;2. Japan Atomic Energy Agency (JAEA), O-arai Engineering Center, 4002 Narita, O-arai, Ibaraki 311-1393, Japan;3. Central Research Institute of Electric Power Industry (CRIEPI), 1646 Abiko, Abiko-shi, Ibaraki 270-1194, Japan |
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Abstract: | A natural circulation evaluation methodology has been developed to insure safety of a sodium cooled fast reactor (SFR) of 1500 MWe adopting a natural circulation decay heat removal system (NC-DHRS). The methodology consists of a one-dimensional safety analysis which can be applied to safety evaluation for SFR licensing taking into account the temperature flattening effect due to buoyancy force in the core, and a three-dimensional fluid flow analysis which can evaluate thermal-hydraulics for local convection and thermal stratification in the primary system and DHRSs. The one-dimensional safety analysis method and the three-dimensional fluid flow analysis method have been validated using the test results of a water test apparatus and a sodium test loop for some typical transient events selected from the design basis events of the SFR. Finally, it has been confirmed that a good agreement between the test results and analysis results has been obtained, and reliability of each method has been demonstrated. |
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Keywords: | fast reactor passive decay heat removal natural circulation CFD thermal hydraulics |
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