Title

Considerations For Modeling Critical Heat Flux Behavior

Comments

Authors: contact us about adding a copy of your work at STARS@ucf.edu

Abbreviated Journal Title

Nucl. Technol.

Keywords

Sociology

Abstract

During normal and accidental operations of a light water nuclear reactor, a wide range of thermal-hydraulic conditions may be encountered for which the critical heat flux (CHF) cannot be predicted by a single correlation. An encompassing model was developed for predicting the steady-state forced convective CHF for water over a wide range of thermal-hydraulic conditions.

A CHF model is postulated using a conceptual CHF map to define possible CHF mechanisms for given thermal-hydraulic conditions. Existing steadystate CHF correlations, for which the primary CHF mechanism modeled can be identified, are then used in conjunction with the conceptual CHF map to construct a predictive CHF model.

The CHF correlations used as the foundation of this model are the Westinghouse-3, the Biasi, and the Modified-Barnett correlations. These correlations allow coverage of a wide range of thermal-hydraulic conditions, provide favorable comparison with experimental data, and are commonly used in the nuclear industry. The parametric ranges covered by the resultant model are

0.3 < P (MPa) <16.0 6.0

where P is pressure; D, the hydraulic diameter; G, the mass flux; and X is quality.

The CHF model compares favorably with available experimental data and was used to construct specific CHF maps.

Journal Title

Nuclear Technology

Volume

68

Issue/Number

262

Publication Date

1-1-1985

Document Type

Article

Language

English

First Page

252

Last Page

366

WOS Identifier

WOS:A1985AAC3500013

ISSN

0029-5450

Share

COinS