Partially heated U-tube configurations are characteristic idealizations for the so called building condensers of future nuclear reactors with passive safety systems. In this paper three simple cases of natural circulation problems are analyzed and analytical solutions are generated. This solutions are recommended for validation of pipe network computer codes. As an example the procedure is demonstrated for the IVA computer code. The usefulness of the obtained solutions is demonstrated discussing the inherent safety behavior of the building condenser of the Framatome ANP SWR 1000 power plant being under development.
- Nuclear Engineering Division
Simple Analytical U-Tube Benchmarks Appropriate for Testing of Pipe-Network Computer Codes
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Kolev, NI. "Simple Analytical U-Tube Benchmarks Appropriate for Testing of Pipe-Network Computer Codes." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 1087-1100. ASME. https://doi.org/10.1115/ICONE10-22711
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