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Study of the Feasibility of Aqueous Recovery of Spent Fuels. Part 3. Calculated Distribution of Fission Product Nuclides.

Description: Calculation of evaluation of the mass and the activity of each fission product nuclide present in the spent fuel of a 500 Mw reactor operating on a 42 day cycle, at the time of removal from the reactor and as a function of time thereafter.
Date: June 1954
Creator: Nehemias, John V.; Dennis, Ralph C. & Ambo, Eugene
Partner: UNT Libraries Government Documents Department
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Dual Channel Pulse Analyser and Count-Rate Meter for Gamma Spectrometer Monitor

Description: Describes the current prototype model of a linear amplifier, two-channel pulse-height analyser, two-channel count-rate meter, and count-rate difference detector for a gamma-ray spectrometer monitor developed to approach the above design criteria.
Date: June 17, 1954
Creator: Paul, R. S. & Wood, M. R.
Partner: UNT Libraries Government Documents Department
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Structural Evaluation of Underground Waste Storage Tanks

Description: To set forth limiting values of internal vapor pressure and effective liquid specific gravity which will permit the maximum utilization of the existing underground waste storage capacity. It is also intended to describe briefly the elements which could contribute to ultimate failure.
Date: June 23, 1955
Creator: Smith, Edgar F.
Partner: UNT Libraries Government Documents Department
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Thermal Expansion of Rare Earth Metals

Description: High temperature dilatometric investigation of the rare earth metals undertaken as part of a broad program of study of these elements, the ultimate goal being better understanding of metals in general.
Date: June 1956
Creator: Barson, Fred; Legvold, S. & Spedding, F. H.
Partner: UNT Libraries Government Documents Department
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Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity

Description: A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
Date: June 26, 1959
Creator: Jackson, P. M.
Partner: UNT Libraries Government Documents Department
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SM-1 Research and Development Program : Final Report on Fission Product Activity in the SM-1 Primary Coolant, Task XIII

Description: Abstract: Fission product measurements were made on the SM-1 primary coolant. The airborne activity observed during the sampling of the primary system was identified. An analysis was made on the primary coolant for alpha activity and on the secondary water for fission production iodine.
Date: June 30, 1959
Creator: Hasse, Robert A.
Partner: UNT Libraries Government Documents Department
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Mid-Year Summary Report October 1, 1960-March 31, 1961 Army Pwr Support and Development Program

Description: Abstract: A cyclic stress analysis of the SM-1 primary system was carried out. Problems encountered in the fabrication of PM-2A Core II and SM-lA Core II are described, and the results of an examination of damaged SM-lA Core I stationary fuel elements reported. A preliminary study of the radiation damage to SM-1 reactor vessel was made and the possibility of annealing the vessel discussed. Performance analyses are presented for five cores: SM-1 Core, SM-1 Core 1 rearranged and spiked, SM-1 Core… more
Date: June 2, 1961
Creator: Hoover, H. L.
Partner: UNT Libraries Government Documents Department
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Investigation of Local Boiling of SM-1

Description: Abstract; SM-1 Reactor Core I Rearranged and Spiked, and Core II with Special Components were analyzed under various off-design conditions to induce nucleate boiling. The steady state code, STDY-3, written for the thermal analysis of pressurized water cores, was employed for the analysis. The code performs a complete steady state parallel channel thermal analysis for both nominal and hot channels. Thermal characteristics of individual elements were investigated while changing the parameters of… more
Date: June 20, 1961
Creator: Bradley, P. L.
Partner: UNT Libraries Government Documents Department
open access

Extended SM-2 Critical Experiments : CE-2

Description: Abstract: This technical report contains a description and results of a second series of critical experiments performed on the SM-2 core mock-up, as additional to the first series of experiments reported in APAE No. 54. The SM-2 core mock-up contains 36.4 kg U-235 and and estimated 67.9 gm B-10. The equivalent diameter and the active height are about 22 in.; the metal-to-water volume ration is 0.344. Data is presented on activation, reactivity, and stuck rod measurements. All measurements were … more
Date: June 30, 1961
Creator: McCool, W. J.; Robinson, R. A.; Weiss, S. H.; Raby, T. M.; Schrader, E. W. & Walthousen, L. D.
Partner: UNT Libraries Government Documents Department
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