QUARTERLY SUMMARY RESEARCH REPORT IN METALLURGY FOR OCTOBER, NOVEMBER, DECEMBER 1954 (open access)

QUARTERLY SUMMARY RESEARCH REPORT IN METALLURGY FOR OCTOBER, NOVEMBER, DECEMBER 1954

None
Date: July 14, 1955
Creator: unknown
System: The UNT Digital Library
Homogenous Reactor Project Quarterly Progress Report For Period Ending April 30, 1955 (open access)

Homogenous Reactor Project Quarterly Progress Report For Period Ending April 30, 1955

Part I. Experimental Reactors: The effect of prompt-neutron lifetime upon reactor safety was investigated for the HRT. It was found that for a given pressure rise the allowable rate of reactivity addition was relatively insensitive to the average prompt-neutron lifetime, although the rate de creased somewhat with decreasing lifetime for the higher pressure rises. With only source neutrons present and the reactor initially subcritical, the allowable rate was practically independent of the initial value of k£. For a core-pressure rise of 400 psi, the corresponding rate of reactivity addition was about 0.8% per second; for a pressure rise of 4000 psi, the rate was 2.5 to 3.0% per second. Part II. Thorium Breeder Reactor: An economic study of one-region thorium breeder reactors was completed. Where possible, the process characteristics and cost factors were the same as those used previously in studies of two-region-type reactors. The mini mum-cost reactor is about 12 ft in diameter, operating with 260 g of thorium per liter on a chemical processing cycle of about 450 days. The ratio of U232 to U233 produced is approximately 2 x 10~4 VIM in the minimum-cost one-region system, compared with 4 x 10 5 in the two-region system. The …
Date: July 14, 1955
Creator: McDuffie, H. F. & Kelly, D. C.
System: The UNT Digital Library
A critical mass study of Hood No. 5 and the filter boat cleaning and testing hood in the 234-5 Building (open access)

A critical mass study of Hood No. 5 and the filter boat cleaning and testing hood in the 234-5 Building

Calculations are presented for the estimated minimum critical mass of Pu that would be allowed in Hood No. 5 and the filter boat cleaning and testing hood of the Plutonium Finishing Plant. Hood No. 5 contains the overflow tank and two vacuum traps. Limits are given for several pile exposure rates. These limits do not allow the approach of personnel into Hood No. 5 when these vessels are full.
Date: July 14, 1955
Creator: Ketzlach, N.
System: The UNT Digital Library
Determination of Plutonium and Uranium in Scrup Dissolver Solutions (open access)

Determination of Plutonium and Uranium in Scrup Dissolver Solutions

Methods for the determination of plutonium and uranium in highly radioactive scrup dissolver solutions have been developed. Plutonium was separated from the dissolver solutions by solvent-extraction and ion-exchange techniques and determined by potentiometric titration. Uranium was separated by ion exchange and determined by potentiometric titration. Solutions that were similar to the actual dissolver solutions and that contained known amounts of plutonium and uranium were analyzed by these methods. Evaluation of the data secured for the determination of plutonium and uranium by the methods given herein indicated that, within the limits of the precision of the methods, there was no bias. The precision of the data obtained for the determination of plutonium, expressed as the relative standard deviation, was better than 2% for plutonium in the concentration range of 0.27 to 0.64 mg/ml. The precision for uranium was estimated to be about 0.2% for uranium concentrations of 425 mg/ml. These methods and the data obtained by then are discussed in this report; the procedures are appended.
Date: July 14, 1955
Creator: Foster, R. W.; Cooper, J. H. & Raaen, H. P.
System: The UNT Digital Library