Validation of the thermal-hydraulic system code ATHLET based on selected pressure drop and void fraction BFBT tests
| Autor: | Victor Hugo Sánchez Espinoza, Valentino Di Marcello, Javier Jimenez Escalante |
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| Rok vydání: | 2015 |
| Předmět: |
Pressure drop
Nuclear and High Energy Physics Engineering business.industry Mechanical Engineering Nuclear engineering Mechanical engineering Computational fluid dynamics Turbine law.invention Thermal hydraulics Experimental uncertainty analysis Nuclear Energy and Engineering law Boiling Nuclear power plant General Materials Science Transient (oscillation) Safety Risk Reliability and Quality business Waste Management and Disposal |
| Zdroj: | Nuclear Engineering and Design. 288:183-194 |
| ISSN: | 0029-5493 |
| Popis: | Validation and qualification of thermal-hydraulic system codes based on separate effect tests are essential for the reliability of numerical tools when applied to nuclear power plant analyses. To this purpose, the Institute for Neutron Physics and Reactor Technology (INR) at the Karlsruhe Institute of Technology (KIT) is involved in various validation and qualification activities of different CFD, sub-channel and system codes. In this paper, the capabilities of the thermal-hydraulic code ATHLET are assessed based on the experimental results provided within the NUPEC BFBT benchmark related to key Boiling Water Reactors (BWR) phenomena. Void fraction and pressure drops measurements in the BFBT bundle performed under steady-state and transient conditions which are representative for e.g. turbine trip and recirculation pump trip events, are compared with the numerical results of ATHLET. The comparison of code predictions with the BFBT data has shown good agreement given the experimental uncertainty and the results are consistent with the trends obtained with similar thermal-hydraulic codes. |
| Databáze: | OpenAIRE |
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