The critical experiments showed that the original specification of 1.0 wt% for the boron concentration could be reduced to 0.25 wt% without reducing the one-rod-out shutdown margin below 2 1/2% reactivity as measured by rod drop experiments. Good agreement was obtained between calculated and measured eigenvalues for the small, clean cores which were analyzed. In cores with no control rods and containing all fuel, 0.0, 0.25, or 1.1 wt% boronstainless steel, and with all 0.25 wt% boron-stainless steel and fuel elements surrounded by aluminum-water displacers, the calculated eigenvalues were 0.7 to 1.0% greater than the measured values. In a core with 0.25 wt% boronstainless steel and with the center control rod fully inserted, the calculated ...
This paper documents the results of a scoping study of boron dilution and mixing phenomena during sm...
An extensive development, fabrication, and design analysis program was completed on 2 wt% boron stai...
A series of criticality experiments with undermoderated (1.6 water-to-fuel volume ratio) 2.35 wt% an...
A series of critical experiments were completed from 1962–1965 at Oak Ridge National Laboratory’s (O...
The studies were primarily directed toward selection of the optimum loading for Core lA and a predic...
A series of critical experiments were completed in 1962-1965 at Oak Ridge National Laboratory’s Crit...
A series of critical experiments were completed in 1962-1965 at Oak Ridge National Laboratory’s Crit...
The SM-2 core lifetime was calculated and stuck rod criteria formulated. The control system could sh...
Three hypothetical disrupted core models were analyzed for the President's Commission on the Acciden...
Elimination of soluble boron from reactor design eliminates boron-induced reactivity accidents and l...
Research and development on metallurglcal aspects of pressurized-water systems is summarized. A surv...
Critical experiments were performed with two assemblies simulating a cold clean, and an end-of-cycle...
A survey of literature on irradiation experience with boron stainless steel was conducted to determi...
Light water critical experiments have been performed in order to measure microscopic parameters and ...
A series of critical experiments were performed with 4.31 wt % /sup 235/U enriched UO/sub 2/ fuel ro...
This paper documents the results of a scoping study of boron dilution and mixing phenomena during sm...
An extensive development, fabrication, and design analysis program was completed on 2 wt% boron stai...
A series of criticality experiments with undermoderated (1.6 water-to-fuel volume ratio) 2.35 wt% an...
A series of critical experiments were completed from 1962–1965 at Oak Ridge National Laboratory’s (O...
The studies were primarily directed toward selection of the optimum loading for Core lA and a predic...
A series of critical experiments were completed in 1962-1965 at Oak Ridge National Laboratory’s Crit...
A series of critical experiments were completed in 1962-1965 at Oak Ridge National Laboratory’s Crit...
The SM-2 core lifetime was calculated and stuck rod criteria formulated. The control system could sh...
Three hypothetical disrupted core models were analyzed for the President's Commission on the Acciden...
Elimination of soluble boron from reactor design eliminates boron-induced reactivity accidents and l...
Research and development on metallurglcal aspects of pressurized-water systems is summarized. A surv...
Critical experiments were performed with two assemblies simulating a cold clean, and an end-of-cycle...
A survey of literature on irradiation experience with boron stainless steel was conducted to determi...
Light water critical experiments have been performed in order to measure microscopic parameters and ...
A series of critical experiments were performed with 4.31 wt % /sup 235/U enriched UO/sub 2/ fuel ro...
This paper documents the results of a scoping study of boron dilution and mixing phenomena during sm...
An extensive development, fabrication, and design analysis program was completed on 2 wt% boron stai...
A series of criticality experiments with undermoderated (1.6 water-to-fuel volume ratio) 2.35 wt% an...