Analyses of spatial CHF/REWET behaviour of fuel rod bundle in pump-trip simulation experiment with three-dimensional multi-fluid porous media approach
Abstract
The investigation of three-dimensional transient propagations of dry-out fronts within a nuclear fuel rod bundle is performed, based on experimental and numerical simulations. The spreading of critical heat flux (CHF) fronts across a bundle, caused by gradual decrease of coolant mass flow rate without power increase is predicted, and the locus of dry patches is shown. Obtained results show that a simultaneous occurrence of CHF and rewet multi-fronts in simulated reactor coolant flow transient are less pronounced than in power transients. Due to a possible building of a vapour zone, the CHF front spatial propagation has to be carefully analysed in transient conditions.
Source:
American Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED, 2002, 257, 2 A, 447-457Publisher:
- American Society of Mechanical Engineers (ASME)
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Institution/Community
Mašinski fakultetTY - CONF AU - Stošić, Zoran V. AU - Stevanović, Vladimir AU - Iguchi, T. PY - 2002 UR - https://machinery.mas.bg.ac.rs/handle/123456789/264 AB - The investigation of three-dimensional transient propagations of dry-out fronts within a nuclear fuel rod bundle is performed, based on experimental and numerical simulations. The spreading of critical heat flux (CHF) fronts across a bundle, caused by gradual decrease of coolant mass flow rate without power increase is predicted, and the locus of dry patches is shown. Obtained results show that a simultaneous occurrence of CHF and rewet multi-fronts in simulated reactor coolant flow transient are less pronounced than in power transients. Due to a possible building of a vapour zone, the CHF front spatial propagation has to be carefully analysed in transient conditions. PB - American Society of Mechanical Engineers (ASME) C3 - American Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED T1 - Analyses of spatial CHF/REWET behaviour of fuel rod bundle in pump-trip simulation experiment with three-dimensional multi-fluid porous media approach EP - 457 IS - 2 A SP - 447 VL - 257 DO - 10.1115/FEDSM2002-31228 ER -
@conference{ author = "Stošić, Zoran V. and Stevanović, Vladimir and Iguchi, T.", year = "2002", abstract = "The investigation of three-dimensional transient propagations of dry-out fronts within a nuclear fuel rod bundle is performed, based on experimental and numerical simulations. The spreading of critical heat flux (CHF) fronts across a bundle, caused by gradual decrease of coolant mass flow rate without power increase is predicted, and the locus of dry patches is shown. Obtained results show that a simultaneous occurrence of CHF and rewet multi-fronts in simulated reactor coolant flow transient are less pronounced than in power transients. Due to a possible building of a vapour zone, the CHF front spatial propagation has to be carefully analysed in transient conditions.", publisher = "American Society of Mechanical Engineers (ASME)", journal = "American Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED", title = "Analyses of spatial CHF/REWET behaviour of fuel rod bundle in pump-trip simulation experiment with three-dimensional multi-fluid porous media approach", pages = "457-447", number = "2 A", volume = "257", doi = "10.1115/FEDSM2002-31228" }
Stošić, Z. V., Stevanović, V.,& Iguchi, T.. (2002). Analyses of spatial CHF/REWET behaviour of fuel rod bundle in pump-trip simulation experiment with three-dimensional multi-fluid porous media approach. in American Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED American Society of Mechanical Engineers (ASME)., 257(2 A), 447-457. https://doi.org/10.1115/FEDSM2002-31228
Stošić ZV, Stevanović V, Iguchi T. Analyses of spatial CHF/REWET behaviour of fuel rod bundle in pump-trip simulation experiment with three-dimensional multi-fluid porous media approach. in American Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED. 2002;257(2 A):447-457. doi:10.1115/FEDSM2002-31228 .
Stošić, Zoran V., Stevanović, Vladimir, Iguchi, T., "Analyses of spatial CHF/REWET behaviour of fuel rod bundle in pump-trip simulation experiment with three-dimensional multi-fluid porous media approach" in American Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED, 257, no. 2 A (2002):447-457, https://doi.org/10.1115/FEDSM2002-31228 . .