Advanced Search
DSpace@MIT

Model of critical heat flux in subcooled flow boiling

Research and Teaching Output of the MIT Community

Show simple item record

dc.contributor.author Fiori, Mario P. en_US
dc.contributor.author Bergles A. E. en_US
dc.contributor.other Massachusetts Institute of Technology. Division of Sponsored Research. en_US
dc.contributor.other Massachusetts Institute of Technology. Dept. of Mechanical Engineering. en_US
dc.contributor.other Massachusetts Institute of Technology. Heat Transfer Laboratory. en_US
dc.date.accessioned 2011-03-04T23:40:32Z
dc.date.available 2011-03-04T23:40:32Z
dc.date.issued 1968 en_US
dc.identifier 14089908 en_US
dc.identifier.uri http://hdl.handle.net/1721.1/61503
dc.description.abstract The physical phenomenon occurring before and at the critical heat flux (CHF) for subcooled flow boiling has been investigated. The first phase of this study established the basic nature of the flow structure at CHF. A photographic study of the flow in a glass annular test section was accomplished by using microflash lighting and a Polaroid camera. The results showed that the flow structure at CHF for high heat flux (1 x 106 - 5 x 106 Btu/hr-ft2), high subcooling (50-110 *F), at low pressures (less than 100 psia) was slug or froth flow depending on the mass velocity. Nucleation was shown to exist in the superheated liquid film. Pin-holes in the burned-out test sections suggested that the CHF condition was extremely localized. Flow regime studies in tubular and annular geometries, using an electrical resistance probe, provided further evidence of the slug or froth nature of the flow, and also showed that dryout of the superheated liquid film was not responsible for CHF. Since this evidence was contradictory to previously formulated models of CHF,a new model was proposed: Near the CHF condition, nucleation is present in the superheated liquid film near the surface. As a large vapor clot passes over the surface, these nucleating bubbles break the film and cause a stable dry spot which results in an increased local temperature. As the vapor finally passes the site, the dry spot is quenched by the liquid slug, and the temperature drops. At CHF, the volumetric heat generation, slug frequency, and void fraction are such that the temperature rise resulting from the dry spot is greater than the temperature drop during quenching. An unstable situation results where the temperature of this point continues to rise when each vapor clot passes the site until the Leidenfrost temperature is reached, at which point quenching is prevented and destruction is inevitable. en_US
dc.description.abstract (cont.) A new method of measuring surface wall temperatures, in conjunction with high speed (Fastax) 16 mm movies, confirmed the microscopic features of the proposed model. At CHF, the wall temperature cyclically increased with the same frequency as the slug-vapor bubble passage. Destruction finally resulted as the temperature increased beyond the Leidenfrost point. An analytical investigation based on an idealized model demonstrated that the cyclical nature of the temperature increase at CHF could be predicted with appropriate flow pattern inputs. A parametric study using the program indicated that heater thickness and heater material should affect the CHF. It was shown that the proposed model appears to be consistent with parametric trends, i.e. mass velocity, pressure, subcooling, diameter, length, and surface tension. The model indicated that the CHF for thicker walled tubes, keeping all other conditions the same, would increase. CHF tests were conducted which confirmed that thicker walled tubes (0.078 vs. 0.012 in. ) had CHF up to 58 percent higher than thin walled tubes. en_US
dc.description.sponsorship Sponsored by the Solid State Sciences Division, Air Force Office of Scientific Research (OAR) Sponsored by Air Force en_US
dc.format.extent 157 p en_US
dc.publisher Cambridge, Mass. : M.I.T. Dept. of Mechanical Engineering, [1968] en_US
dc.relation.ispartofseries Technical report (Massachusetts Institute of Technology, Heat Transfer Laboratory) ; no. 56. en_US
dc.subject Boiling-points. en_US
dc.subject Heat -- Transmission. en_US
dc.subject Tubes -- Fluid dynamics. en_US
dc.title Model of critical heat flux in subcooled flow boiling en_US
dc.type Technical Report en_US


Files in this item

Name Size Format Description
HTL_TR_1968_056.pdf 8.161Mb PDF

This item appears in the following Collection(s)

Show simple item record

MIT-Mirage