Browsing Heat Transfer Laboratory Technical Reports by Title

Now showing items 79-80 of 80

    • 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 ...