Mechanistic CHF modeling for natural circulation applications in SMR

Jeffrey Luitjens, Qiao Wu, Scott Greenwood, Michael Corradini

Research output: Contribution to journalArticlepeer-review

13 Scopus citations

Abstract

A mechanistic critical heat flux correlation has been developed for a wide range of operating conditions which include low mass fluxes of 540–890 kg/m2-s, high pressures of 12–13 MPa, and critical heat fluxes of 835–1100 kW/m2. Eleven experimental data points have been collected over these conditions to inform the development of the model using bundle geometry. Errors of within 15% have been obtained with the proposed model for predicting the critical heat flux value, location, and critical pin power for a non-uniform heat flux applied to a 2 × 2 bundle configuration.

Original languageEnglish
Pages (from-to)604-611
Number of pages8
JournalNuclear Engineering and Design
Volume310
DOIs
StatePublished - Dec 15 2016
Externally publishedYes

Funding

This material is based upon work supported by the Department of Energy Nuclear Energy University Programs grant in collaboration with the University of Wisconsin-Madison .

FundersFunder number
DOE Office of Nuclear Energy
University of Wisconsin-Madison

    Keywords

    • Boiling crisis
    • CHF
    • Critical heat flux
    • Japan-US seminar
    • Two-phase

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