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  • This paper presents a CFD simulation of selected “Large Water Loop” critical heat flux experiments. Calculations were performed by NEPTUNE_CFD code. The Large Water Loop (LWL) is non-active pressurised-water equipment with technological and thermal parameters corresponding to those of PWR. Thirteen CHF tests were calculated with NEPTUNE. In all calculated tests, a sudden rise of the wall temperature was observed. Simulations of cases with a higher mass flux were successful. Simulation of cases with a low mass flux indicates that the modelling approach might not be suitable for lower mass fluxes. The results show that NEPTUNE has some potential for predicting boiling flow up to CHF in the reactor fuel assembly. Proceedings of XCFD4NRS, Experiments and CFD Code Applications to Nuclear Reactor Safety OECD/NEA & IAEA, Grenoble, France, 10 - 12 September 2008.
  • This paper presents a CFD simulation of selected “Large Water Loop” critical heat flux experiments. Calculations were performed by NEPTUNE_CFD code. The Large Water Loop (LWL) is non-active pressurised-water equipment with technological and thermal parameters corresponding to those of PWR. Thirteen CHF tests were calculated with NEPTUNE. In all calculated tests, a sudden rise of the wall temperature was observed. Simulations of cases with a higher mass flux were successful. Simulation of cases with a low mass flux indicates that the modelling approach might not be suitable for lower mass fluxes. The results show that NEPTUNE has some potential for predicting boiling flow up to CHF in the reactor fuel assembly. Proceedings of XCFD4NRS, Experiments and CFD Code Applications to Nuclear Reactor Safety OECD/NEA & IAEA, Grenoble, France, 10 - 12 September 2008. (en)
Title
  • Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code
  • Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code (en)
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  • Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code
  • Simulation of Critical Heat Flux Experiments in NEPTUNE_CFD Code (en)
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  • RIV/46356088:_____/08:#0001219!RIV13-MPO-46356088
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  • RIV/46356088:_____/08:#0001219
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  • computational fluid dynamics; subcooled boiling; critical heat flux; wall-heat-flux; splitting; interfacial area transport (en)
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  • [F59675E262DE]
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  • Macek, Jiří
  • Vyskočil, Ladislav
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