Analyses of Single-Phase Heat Transfer and Onset of Nucleate Boiling in a Rod Bundle With Mixing Vane Grids
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
B3-2 Core Thermalhydraulics and Subchannel Analysis

Pierre Péturaud (Electricité de France)
Robert Salko (The Pennsylvania State University)
André Bergeron (Commissariat à l'Energie Atomique)
Suresh Yagnik (Electric Power Research Institute)
Maria Avramova (The Pennsylvania State University)


In the framework of axial offset anomaly risk assessment in Pressurized Water Reactor (PWR) cores, an experimental program involving hydraulic and thermal-hydraulic tests on identical 5x5 bundle geometry was completed. It aimed at developing a consistent set of single-phase heat transfer model and associated onset of nucleate boiling (ONB) wall superheat criterion to further predict the existence and location of boiling zones in a PWR core, using a sub-channel Thermal-Hydraulic (T/H) code. This paper is devoted to the code-based analysis of the experimental data obtained on a bundle equipped with alternating simple support grids and mixing vane grids. Dedicated heat transfer models including a grid enhancement function are developed and the use of Frost & Dzakowic ONB wall superheat criterion is recommended along with these models.

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