The approach (up to August 1956) to reactor controls analysis, as carried out by the GE-ANPD, is summarized and reviewed. For purposes of illustration, the results of the HTRE No. 3 preliminary controls analysis are outlined. Uncertainties in existing methods lead to probable errors on the order of plus or minus 30% in estimates of reactivity worth. Incorporation of undesirably large safety factors in a given design and resultant losses in performance are costly penalties for these uncertainties. A program of controls analysis methods development, which should reduce the current inherent errors considerably and improve the state of the art, is presented. (auth)
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AF33(038)-21102; AT(11-1)-171 NSA number: NSA-16-007238 OSTI Identifier 4819319 Research organization: General Electric Co. Aircraft Nuclear Propulsion Dept., Cincinnati.
