Mechanistic CHF modeling for natural circulation applications in SMR

Jeffrey Luitjens; Qiao Wu; Scott Greenwood; Michael Corradini

doi:10.1016/j.nucengdes.2016.10.040

Mechanistic CHF modeling for natural circulation applications in SMR

Jeffrey Luitjens
, Qiao Wu
, Scott Greenwood
, Michael Corradini

Research output: Contribution to journal › Article › peer-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 language	English
Pages (from-to)	604-611
Number of pages	8
Journal	Nuclear Engineering and Design
Volume	310
DOIs	https://doi.org/10.1016/j.nucengdes.2016.10.040
State	Published - Dec 15 2016
Externally published	Yes

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 .

Keywords

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

Access to Document

10.1016/j.nucengdes.2016.10.040

Cite this

@article{17ed2fb66caa4704834e67b82f7b8627,

title = "Mechanistic CHF modeling for natural circulation applications in SMR",

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.",

keywords = "Boiling crisis, CHF, Critical heat flux, Japan-US seminar, Two-phase",

author = "Jeffrey Luitjens and Qiao Wu and Scott Greenwood and Michael Corradini",

note = "Publisher Copyright: {\textcopyright} 2016",

year = "2016",

month = dec,

day = "15",

doi = "10.1016/j.nucengdes.2016.10.040",

language = "English",

volume = "310",

pages = "604--611",

journal = "Nuclear Engineering and Design",

issn = "0029-5493",

publisher = "Elsevier",

}

TY - JOUR

T1 - Mechanistic CHF modeling for natural circulation applications in SMR

AU - Luitjens, Jeffrey

AU - Wu, Qiao

AU - Greenwood, Scott

AU - Corradini, Michael

PY - 2016/12/15

Y1 - 2016/12/15

N2 - 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.

AB - 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.

KW - Boiling crisis

KW - CHF

KW - Critical heat flux

KW - Japan-US seminar

KW - Two-phase

UR - https://www.scopus.com/pages/publications/85002940311

U2 - 10.1016/j.nucengdes.2016.10.040

DO - 10.1016/j.nucengdes.2016.10.040

M3 - Article

AN - SCOPUS:85002940311

SN - 0029-5493

VL - 310

SP - 604

EP - 611

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

ER -

Mechanistic CHF modeling for natural circulation applications in SMR

Abstract

Funding

Keywords

Access to Document

Other files and links

Fingerprint

Cite this