The paper presents validation of the CORETRAN-01 code thermal–hydraulic module VIPRE02 against experimental data, obtained at experimental facilities at EREC E108 (Russia) and RIT (Sweden). The validation was carried out in order to assess the VIPRE02 code predictions for CHF occurrence and post–CHF heat transfer in 7.0 m long tubes. The lengths of the test sections in the experiments correspond to the heated length of the RBMK reactor fuel assembly. The CHF and post-CHF (transition and film boiling) correlations, included in the standard version of VIPRE02 code package were tested. The validation results as well as VIPRE model and code modification description are the subject of this paper.
- Nuclear Engineering Division
VIPRE02 Code Assesment for CHF and Post-CHF Heat Transfer Modes in Long Tubes
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Jasiulevicius, A, & Sehgal, BR. "VIPRE02 Code Assesment for CHF and Post-CHF Heat Transfer Modes in Long Tubes." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 4. Arlington, Virginia, USA. April 14–18, 2002. pp. 717-726. ASME. https://doi.org/10.1115/ICONE10-22082
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