Recent challenges in subchannel thermal-hydraulics-CFD modeling, subchannel analysis, CHF experiments, and CHF prediction

• Published in: Nuclear engineering and design Vol. 354; p. 110236
• Main Authors: Yang, Bao-Wen, Han, Bin, Liu, Aiguo, Wang, Sipeng
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01.12.2019; Elsevier BV
• Subjects: Assemblies; Boiling; Bundling; Computational fluid dynamics; Computer applications; Cross flow; Experiments; Fluid dynamics; Fluid flow; Heat flux; Hydraulics; Hydrodynamics; Light water reactors; Mathematical models; Nuclear accidents & safety; Nuclear energy; Nuclear engineering; Nuclear fuels; Nuclear power plants; Nuclear reactors; Nuclear safety; Nucleation; Open channels; Pressurized water reactors; Reactors; Safety

•For the first time, the hidden non-conservatisms due to non-typical CHF physical phenomena and non-representative exit quenching effects for both uniformly heated and potentially exit peaking power profile rod bundle CHF tests were identified. These effects not only observed in the typical (straigh...