Three-dimensional characteristics of post-CHF behaviour within a rod bundle for loss-of-flow simulation: Experimental and three-fluid porous media numerical analyses
Апстракт
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 sudden decrease of coolant mass flow rate followed by delayed gradual decrease of power generation is predicted, and the locus of dry patches is shown. Simultaneous occurrence of CHF and rewet multi-fronts in here-analysed flow transient has not been detected so obvious as in power transient, previously analysed. Due to a possible building of a vapour zone, the CHF front spatial propagation has to be carefully analysed in transient conditions.
Извор:
International Conference on Nuclear Engineering, Proceedings, ICONE, 2002, 3, 247-262Колекције
Институција/група
Mašinski fakultetTY - CONF AU - Stošić, Zoran V. AU - Stevanović, Vladimir AU - Iguchi, T. PY - 2002 UR - https://machinery.mas.bg.ac.rs/handle/123456789/254 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 sudden decrease of coolant mass flow rate followed by delayed gradual decrease of power generation is predicted, and the locus of dry patches is shown. Simultaneous occurrence of CHF and rewet multi-fronts in here-analysed flow transient has not been detected so obvious as in power transient, previously analysed. Due to a possible building of a vapour zone, the CHF front spatial propagation has to be carefully analysed in transient conditions. C3 - International Conference on Nuclear Engineering, Proceedings, ICONE T1 - Three-dimensional characteristics of post-CHF behaviour within a rod bundle for loss-of-flow simulation: Experimental and three-fluid porous media numerical analyses EP - 262 SP - 247 VL - 3 DO - 10.1115/ICONE10-22203 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 sudden decrease of coolant mass flow rate followed by delayed gradual decrease of power generation is predicted, and the locus of dry patches is shown. Simultaneous occurrence of CHF and rewet multi-fronts in here-analysed flow transient has not been detected so obvious as in power transient, previously analysed. Due to a possible building of a vapour zone, the CHF front spatial propagation has to be carefully analysed in transient conditions.", journal = "International Conference on Nuclear Engineering, Proceedings, ICONE", title = "Three-dimensional characteristics of post-CHF behaviour within a rod bundle for loss-of-flow simulation: Experimental and three-fluid porous media numerical analyses", pages = "262-247", volume = "3", doi = "10.1115/ICONE10-22203" }
Stošić, Z. V., Stevanović, V.,& Iguchi, T.. (2002). Three-dimensional characteristics of post-CHF behaviour within a rod bundle for loss-of-flow simulation: Experimental and three-fluid porous media numerical analyses. in International Conference on Nuclear Engineering, Proceedings, ICONE, 3, 247-262. https://doi.org/10.1115/ICONE10-22203
Stošić ZV, Stevanović V, Iguchi T. Three-dimensional characteristics of post-CHF behaviour within a rod bundle for loss-of-flow simulation: Experimental and three-fluid porous media numerical analyses. in International Conference on Nuclear Engineering, Proceedings, ICONE. 2002;3:247-262. doi:10.1115/ICONE10-22203 .
Stošić, Zoran V., Stevanović, Vladimir, Iguchi, T., "Three-dimensional characteristics of post-CHF behaviour within a rod bundle for loss-of-flow simulation: Experimental and three-fluid porous media numerical analyses" in International Conference on Nuclear Engineering, Proceedings, ICONE, 3 (2002):247-262, https://doi.org/10.1115/ICONE10-22203 . .