| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 4925287 | Nuclear Engineering and Design | 2017 | 13 Pages |
Abstract
A scaled test facility was setup to simulate the thermal hydraulic characteristics of the PMCS and to analyze the performance behavior of the PMCS. Prolonged SBO transient experiment was performed in the test facility and analyzed using system code RELAP5/Mod 3.2. Besides, CFD simulations were also carried out for analyzing the temperature distribution inside calandria vessel of the test facility. Experimental results show efficient removal of the heat from the moderator and isolation condensers. The simulation results show that RELAP5 is able to predict the natural circulation phenomena very well and three dimensional temperature fields inside the vessel can be predicted by CFD. Temperature field as predicted by CFD is found to be in good agreement with the experiment.
Keywords
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Authors
Mukesh Kumar, A.K. Nayak, J.B. Joshi,