An updated approach to the prediction of dryout and void fraction for RBWR bundles

X. Zhao, K. Shirvan, Y. Wu, M. S. Kazimi

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

1 Scopus citations

Abstract

Unlike a traditional square lattice BWR fuel bundle, the Resource-Renewable Boiling Water Reactor (RBWR) fuel bundle is a tight hexagonal lattice. The different geometry, combined with different operating conditions, demands a re-examination of the standard BWR thermal hydraulic models. For dryout, the previously recommended MIT correlation, which is based on the CISE-4 formulation, had large scatter when compared to experimental data in its validation database. In a new study, narrowing the range of hydraulic diameter and operating conditions and including critical heat flux (CHF) data for tubes and annuli were investigated. A new MIT correlation was derived but yielded very similar low MCPR (minimum critical power ratio) values as previously predicted for the RBWR designs. Another methodology, the 2006 CHF look-up table of Groeneveld was also used to predict dryout in RBWR type geometry. It was found that the effects of boiling length and axial power shape require further detailed investigation via higher fidelity simulations. For void fraction, experimental data and a three field model for annular flow regime revealed that the common drift flux approaches over-estimate the void fraction at smaller hydraulic diameters. The void fraction dependence on diameter below 10 mm requires further experimentation and high fidelity mechanistic simulations.

Original languageEnglish
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages365-378
Number of pages14
ISBN (Electronic)9781510811843
StatePublished - 2015
Externally publishedYes
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: Aug 30 2015Sep 4 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume1

Conference

Conference16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Country/TerritoryUnited States
CityChicago
Period08/30/1509/4/15

Keywords

  • Dryout
  • Rbwr
  • Tight lattice bundle
  • Void fraction

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