Browsing Heat Transfer Laboratory Technical Reports by Title

Now showing items 75-80 of 80

    • The transition from the annular to the slug flow regime in two-phase flow 

      Haberstroh, Robert D.; Griffith, P. (Cambridge, Mass. : M.I.T. Division of Sponsored Research, [1964], 1964)
      Experiments were conducted to determine the transition from annular to semiannular flow regimes for two-phase, gas-liquid upflow in vertical tubes. The influencesof liquid flow rate, tube diameter, liquid viscosity, surface ...

    • The transition from two phase bubble flow to slug flow 

      Radovcich, Nick A.; Moissis, Raphael. (Cambridge, Mass. : M.I.T. Division of Sponsored Research, [1962], 1962)
      The process of transition from bubble to slug flow in a vertical pipe has been studied analytically and experimentally. An equation is presented which gives the agglomeration time as a function of void fraction, channel ...

    • Two phase flow in capillary tubes 

      Suo, Mikio; Griffith, P. (Cambridge, Mass. : M.I.T. Heat Transfer Laboratory, [1963], 1963)
      The flow of two phases, gas and liquid, has been studied in horizontal tubes of capillary diameter. The flow has been primarily studied in the regime where the gas flows as long bubbles separated from the wall of the tube ...

    • Two phase pressure drop in inclined and vertical pipes 

      Griffith, P.; Lau, Chun Woon.; Hon, Pou Cheong.; Pearson, John Franklin. (Cambridge : Heat Transfer Laboratory, [1973], 1973)
      A method of calculating the pressure drop in inclined and vertical oil-gas wells is proposed. The data used to establish the method is from a variety of sources but is largely from air and water flowing in systems close ...

    • Unsteady momentum fluxes in two-phase flow and the vibration of nuclear reactor components 

      Yih, Tien Sieh; Griffith, P. (Cambridge, Mass. : M.I.T. Dept. of Mechanical Engineering, [1968], 1968)
      The steady and unsteady components of the momentum flux in a twophase flow have been measured at the exit of a vertical pipe. Measured momentum flux data has been machine processed by standard random vibration techniques ...

    • Void volumes in subcooled boiling systems 

      Griffith, P.; Clark, John A.; Rohsenow, Warren M. (Cambridge, Mass. : M.I.T. Division of Industrial Cooperation, [1958], 1958)
      Introduction: Knowledge of the pressure drop in a channel and the resulting flow redistribution is essential in predicting the performance of a nuclear reactor. The pressure drop in a channel which is experiencing boiling ...