Search Results

Advanced search parameters have been applied.
open access

Fuel Cycle Program, a Boiling Water Reactor Research and Development Program. Third Quarterly Report, January 1961-March 1961

Description: The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulat… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
open access

Economic Evaluation of Control Rod Materials and Fabrication Processes

Description: Control rod materials, designs, and fabrication processes were compared for their relative economics. Control rod lifetime data were calculated with a simple approximation of nuclear worth depreciation. These data were used in conjunction with the estimated fabrication costs to determine the cost of using several absorber materials in a typical power reactor on a cost-per-year basis. The effect the control system has on core power density and fuel lifetime was included. (auth)
Date: May 1962
Creator: Williamson, H. E. & Megerth, F. H.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen