Calculations are made to determine the safe steady-state power operating limits of the Spert III reactor from the viewpoint of fuel plate burnout. A computer program is developed for the IBM 704 to aid in these calculations. The Bettis design departure from nucleate boiling (MB) equation is used in conjunction with the LeTourneau and Grimble method of "hot channel" analysis in the development of the calculations. For cases where MB occurs in the bulk boiling region, a modified Martinelli-Kelson two-phase flow correlation and some ex¬perimental single-phase pressure drop data are employed.nMB for a typical operating condition of 550°F inlet temperature and 2500 psig is computed to check the code.
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