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Title: A formal approach for the prediction of the critical heat flux in subcooled water

Abstract

The critical heat flux (CHF) in subcooled water at high mass fluxes are not yet satisfactory correlated. For this scope a formal approach is here followed, which is based on an extension of the parameters and the correlation used for the dryout prediction for medium high quality mixtures. The obtained correlation, in spite of its simplicity and its explicit form, yields satisfactory predictions, also when applied to more conventional CHF data at low-medium mass fluxes and high pressures. Further improvements are possible, if a more complete data bank will be available. The main and general open item is the definition of a criterion, depending only on independent parameters, such as mass flux, pressure, inlet subcooling and geometry, to predict whether the heat transfer crisis will result as a DNB or a dryout phenomenon.

Authors:
 [1]
  1. Polytechnic of Milan (Italy)
Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; American Nuclear Society, La Grange Park, IL (United States); American Inst. of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers, New York, NY (United States); Canadian Nuclear Society, Toronto, ON (Canada); European Nuclear Society (ENS), Bern (Switzerland); Atomic Energy Society of Japan, Tokyo (Japan); Japan Society of Multiphase Flow, Kyoto (Japan)
OSTI Identifier:
111415
Report Number(s):
NUREG/CP-0142-Vol.4; CONF-950904-Vol.4
ON: TI95017080; TRN: 95:021603
Resource Type:
Conference
Resource Relation:
Conference: 7. international topical meeting on nuclear reactor thermal-hydraulics (Nureth-7), Saratoga Springs, NY (United States), 10-15 Sep 1995; Other Information: PBD: Sep 1995; Related Information: Is Part Of Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Sessions 17-24; Block, R.C.; Feiner, F. [American Nuclear Society, La Grange Park, IL (United States)]; PB: 825 p.
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; REACTOR COOLING SYSTEMS; CRITICAL HEAT FLUX; PWR TYPE REACTORS; THERMONUCLEAR REACTOR COOLING SYSTEMS; THERMONUCLEAR REACTORS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; DRYOUT; MATHEMATICAL MODELS; VERIFICATION

Citation Formats

Lombardi, C. A formal approach for the prediction of the critical heat flux in subcooled water. United States: N. p., 1995. Web.
Lombardi, C. A formal approach for the prediction of the critical heat flux in subcooled water. United States.
Lombardi, C. Fri . "A formal approach for the prediction of the critical heat flux in subcooled water". United States. https://www.osti.gov/servlets/purl/111415.
@article{osti_111415,
title = {A formal approach for the prediction of the critical heat flux in subcooled water},
author = {Lombardi, C.},
abstractNote = {The critical heat flux (CHF) in subcooled water at high mass fluxes are not yet satisfactory correlated. For this scope a formal approach is here followed, which is based on an extension of the parameters and the correlation used for the dryout prediction for medium high quality mixtures. The obtained correlation, in spite of its simplicity and its explicit form, yields satisfactory predictions, also when applied to more conventional CHF data at low-medium mass fluxes and high pressures. Further improvements are possible, if a more complete data bank will be available. The main and general open item is the definition of a criterion, depending only on independent parameters, such as mass flux, pressure, inlet subcooling and geometry, to predict whether the heat transfer crisis will result as a DNB or a dryout phenomenon.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Sep 01 00:00:00 EDT 1995},
month = {Fri Sep 01 00:00:00 EDT 1995}
}

Conference:
Other availability
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