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Title: Critical heat flux (CHF) phenomenon on a downward facing curved surface

Abstract

This report describes a theoretical and experimental study of the boundary layer boiling and critical heat flux phenomena on a downward facing curved heating surface, including both hemispherical and toroidal surfaces. A subscale boundary layer boiling (SBLB) test facility was developed to measure the spatial variation of the critical heat flux and observe the underlying mechanisms. Transient quenching and steady-state boiling experiments were performed in the SBLB facility under both saturated and subcooled conditions to obtain a complete database on the critical heat flux. To complement the experimental effort, an advanced hydrodynamic CHF model was developed from the conservation laws along with sound physical arguments. The model provides a clear physical explanation for the spatial variation of the CHF observed in the SBLB experiments and for the weak dependence of the CHF data on the physical size of the vessel. Based upon the CHF model, a scaling law was established for estimating the local critical heat flux on the outer surface of a heated hemispherical vessel that is fully submerged in water. The scaling law, which compares favorably with all the available local CHF data obtained for various vessel sizes, can be used to predict the local CHF limits onmore » large commercial-size vessels. This technical information represents one of the essential elements that is needed in assessing the efficacy of external cooling of core melt by cavity flooding as a severe accident management strategy. 83 figs., 3 tabs.« less

Authors:
; ;  [1]
  1. Pennsylvania State Univ., University Park, PA (United States). Dept. of Mechanical Engineering
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; Pennsylvania State Univ., University Park, PA (United States). Dept. of Mechanical Engineering
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
491560
Report Number(s):
NUREG/CR-6507; PSU/ME-97-7321
ON: TI97006632; TRN: 97:012481
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Jun 1997
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; CRITICAL HEAT FLUX; REACTOR ACCIDENTS; POOL BOILING; TEST FACILITIES; PRESSURE VESSELS; CORIUM; WATER COOLED REACTORS; COOLING; EXPERIMENTAL DATA; THEORETICAL DATA; SCALING LAWS; AFTER-HEAT REMOVAL

Citation Formats

Cheung, F.B., Haddad, K.H., and Liu, Y.C. Critical heat flux (CHF) phenomenon on a downward facing curved surface. United States: N. p., 1997. Web. doi:10.2172/491560.
Cheung, F.B., Haddad, K.H., & Liu, Y.C. Critical heat flux (CHF) phenomenon on a downward facing curved surface. United States. doi:10.2172/491560.
Cheung, F.B., Haddad, K.H., and Liu, Y.C. Sun . "Critical heat flux (CHF) phenomenon on a downward facing curved surface". United States. doi:10.2172/491560. https://www.osti.gov/servlets/purl/491560.
@article{osti_491560,
title = {Critical heat flux (CHF) phenomenon on a downward facing curved surface},
author = {Cheung, F.B. and Haddad, K.H. and Liu, Y.C.},
abstractNote = {This report describes a theoretical and experimental study of the boundary layer boiling and critical heat flux phenomena on a downward facing curved heating surface, including both hemispherical and toroidal surfaces. A subscale boundary layer boiling (SBLB) test facility was developed to measure the spatial variation of the critical heat flux and observe the underlying mechanisms. Transient quenching and steady-state boiling experiments were performed in the SBLB facility under both saturated and subcooled conditions to obtain a complete database on the critical heat flux. To complement the experimental effort, an advanced hydrodynamic CHF model was developed from the conservation laws along with sound physical arguments. The model provides a clear physical explanation for the spatial variation of the CHF observed in the SBLB experiments and for the weak dependence of the CHF data on the physical size of the vessel. Based upon the CHF model, a scaling law was established for estimating the local critical heat flux on the outer surface of a heated hemispherical vessel that is fully submerged in water. The scaling law, which compares favorably with all the available local CHF data obtained for various vessel sizes, can be used to predict the local CHF limits on large commercial-size vessels. This technical information represents one of the essential elements that is needed in assessing the efficacy of external cooling of core melt by cavity flooding as a severe accident management strategy. 83 figs., 3 tabs.},
doi = {10.2172/491560},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jun 01 00:00:00 EDT 1997},
month = {Sun Jun 01 00:00:00 EDT 1997}
}

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