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Progress Report for Period Covering December 17, 1969 - January 15, 1960

Description: As reported in the previous Progress Report (December 16, 1959) a stock solution of Th 230 was prepared from pitchblende. Pulse height analysis of this solution indicated the presence of only Th 230 (93%), Th 227 (5%), Th 232 (1%), and Th 228 (1%). This solution was used to make up synthetic thorium solution of various concentration. These synthetic solutions were analyzed to establish a chemical yield for the procedure. Neither the precision nor the chemical yield of the procedure were conside… more
Date: January 15, 1960
Creator: Petrow, Henry G.
Partner: UNT Libraries Government Documents Department
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Radioactive Drug Research, Final Summary Report, July 1949 to October 1959

Description: Applications of radioisotopes in the preparation of labeled drugs are reviewed. Among the applications described are the preparation of carbon-14- labeled cardiac glycosides, and the biosyinthesis of carbon-14-labeled digitoxin, morphine, colchicine, atropine, podophyllotoxin, and nicotine. The fate and metabolism of many of these drugs were traced. Radiochemical procedures were developed for the synthesis of pure compounds of pharmacological interest labeled with carbon-14, sulfur-35, and trit… more
Date: January 15, 1960
Creator: Geiling, E. M. K. (Eugene Maximilian Karl), 1891-1971 & Roth, Lloyd J. (Lloyd Joseph), 1911-
Partner: UNT Libraries Government Documents Department
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The SNAP II Power Conversion System. Topical Report No. 3. Dynamic Analysis

Description: SNAP II is the designation for a nuclear auxiliary power unit, designed primarily for utilization in the WS117L satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine, and an alternator. Dynamic analysis of the power conversion system was conducted utilizing a comprehensive analog computer simulation. Feasibility of a parasitic load control for numerous system disturbances was demonstrated. This analysis was performed under a subcontract to to Atomics … more
Date: January 15, 1960
Creator: Deibel, David L.; Mrava, Gene L. & Seldner, Kurt
Partner: UNT Libraries Government Documents Department
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Studies of Reactor Containment : Monthly Technical Progress Report No. 32

Description: The report covers work performed during the period December 1, 1959 through December 31, 1959. The general objectives of the program of "Studies of Reactor Containment" are to accomplish theoretical and experimental investigations of the loads to which external containment structures for nuclear reactors are subjected in the vent of a violent incident at the reactor core, the evaluation of methods of reducing that loading, and the study of the response of and design criteria for external contai… more
Date: January 15, 1960
Creator: Zaker, T. A. (Thomas Allen)
Partner: UNT Libraries Government Documents Department
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Upper Atmosphere Monitoring Program : Progress Report No. 8 for May 1, 1959 through July 31, 1959

Description: The overall scope of the program encompasses both research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication and calibration of balloon-borne sampling equipment to enable the precise determination of stratospheric particle concentration and particle size distribution.
Date: January 15, 1960
Creator: Baumstark, J.; Jones, S.; Stern, S.; Torgeson, L. & Zeller, W.
Partner: UNT Libraries Government Documents Department
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The Irradiated Rupture Prototype (IRP) Design

Description: One of the problems involved in the design of NPR is the method to be used for decontamination, Considerable effort has been made in both laboratories and pilot plants in developing and evaluating decontamination processes under ideal conditions. Promising processes must be tested under prototypical conditions of velocity, water quality, manner of make-up, type and degree of contamination, addition of decontaminating solutions, and so on.
Date: February 15, 1960
Creator: Neibaur, G. E. & Stice, N. D.
Partner: UNT Libraries Government Documents Department
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Progress letter No. 11 for January 1, 1960 through January 31, 1960

Description: A stainless steel autoclave for superheated water corrosion test was installed and "conditioned". Tests were begun to investigate the feasibility of densifying slip cast stainless steel by means of liquid phase sintering. Attempts to prepare tubular fuel elements by vacuum forming were resumed. Although thick-walled vacuum formed casting have been sintered on the aluminum mandrels without cracking, this has not yet been accomplished with the think sections of interest.
Date: February 15, 1960
Creator: Baron, Edeard H.
Partner: UNT Libraries Government Documents Department
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Progress Report for Period Covering January 15, 1960 - February 15, 1960

Description: Thorium Procedure: As was mentioned in the last report, ammonium nitrate was substituted for ferric nitrate as a salting agent. Also, the acidity of the nitrate solution was reduced from 3.0 molar to 0.5 molar. the revised thorium procedure is described in the report. Radium Procedure: Work has ben initiated on the procedure of Petrow, Nietzel and DeSesa (Winchester Procedure) to determine if the procedure is suitable for very low level concentrations of radium.
Date: February 15, 1960
Creator: Petrow, Henry G.
Partner: UNT Libraries Government Documents Department
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Problems of a Small Leak Between the Flow Monitor and Heated Section of a PRTR Process Tube

Description: The result of a leak in a PRTR process tube between the flow monitor and the heated section would be to increase the flow through the monitor, but to decrease the flow through the heated section. The concern for the case of small leaks is whether the increase in flow through the flow monitor is sufficient to cause a high flow tip and a reactor scram for the condition where the flow through the heated section is reduced to the point to cause excessive fuel element temperatures.
Date: March 15, 1960
Creator: Hesson, G. M.
Partner: UNT Libraries Government Documents Department
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Unique Fabrication Processes Applied to Fuel Cladding Materials

Description: The fabrication processes applied to nuclear fuels are subject to severe limitations because of the conditions imposed by the reactor environment. The combined problems of neutrons fluxes, high heat fluxes, corrosion by the coolant , and embrittlement by hydriding or similar reactions may be minimized through establishing rigorous materials and fabrication specifications for fuel and cladding.
Date: March 15, 1960
Creator: Bush, S. H.
Partner: UNT Libraries Government Documents Department
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VARI Solution of Simultaneous, First-Order, Ordinary, Differential Equations

Description: VARI solves on the IBM-650 a system of simultaneous, first-order, ordinary, differential equations. The program was written so that a large number of calculations could be done in a reasonable length of time. The program permits the consideration of the production of the isotope by absorption and/or decay of one or more of any of the other isotopes in the chain.
Date: March 15, 1960
Creator: Kerr, B. A.
Partner: UNT Libraries Government Documents Department
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Zero Power Experiments for the SM-1 Core II : Task XV

Description: Abstract: An element by element reactivity check for SM-1 Core II fuel elements and control rod absorber sections was performed and the burnable nuclear poison loading in the SM-1 Core II stationary fuel elements was established. An approach to criticality of the SM-1 Core II was performed by the inverse multiplication method and the critical rod bank position obtained as a function of fuel loading up to the full SM-1 Core II loading. Maximum and minimum core reactivity measurements were obtai… more
Date: March 15, 1960
Creator: Robinson, R. A.; Weiss, S. H.; McCool, W. J. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
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Magnetic Recorder for Nuclear Pulse Application : Covering the Period from February 6, 1960 to April 5, 1960

Description: Abstract: "The accuracies which can be achieved in analog recording systems are for the most part tape limited. While reasonable variations in tape speed do not directly affect the accuracy, such variations result in improper tape tensioning, which in turn results in poor head-to-tape contact. The quality of the tape transport mechanism should be such that the error introduced by improper head- to tape contact is less than tape errors. Some additional equipment is necessary in setting up a tape… more
Date: April 15, 1960
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department
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Niobium Phase Diagrams

Description: The following report is the final technical report on a series of reports under contract AT(11-1)-515, titled "Niobium Phase Diagrams", covering the period from April 15, 1957 to April 16, 1960.
Date: May 15, 1960
Creator: Elliott, Rodney P. & Komjathy, Steven
Partner: UNT Libraries Government Documents Department
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The p-n Cross Sections onf Ti47, V51, Cr52, Co59, and Cu63 from 4 to 6.5 Mov

Description: Absolute (p,n) cross sections have been measured for Ti47, V51, Cr52, Co59, and Cu63 at energies between 4 and 6.5 Mov. These data plus earlier measurements of the cross section for inelastic proton scattering have been used to estimate total proton absorption cross sections for V51 and Co59. An optical model calculation using parameters giving a good fit to elastic scattering measurements predicts an absorption cross section in good agreement with the measurements for Co59. For V51, some sets … more
Date: June 15, 1960
Creator: Taketanit, H. & Alford, W. P. (William Parker), 1927-
Partner: UNT Libraries Government Documents Department
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Sampling and Analytical Data on Al-Pu Alloy for PRTR Start-Up Tests

Description: In answer to the question, "How well do we know the composition of the fuel material for the PRTR start-up tests?", the analytical data on the PRTR fuel elements and other fuel elements which were fabricated by similar processes was gathered and analyzed. The results of this analysis are presented.
Date: June 15, 1960
Creator: Bloomster, C. H.
Partner: UNT Libraries Government Documents Department
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Thorium Oxide Infiltration of Graphite Spheres

Description: Work on the preparation of graphite spheres containing thorium oxide for use as breeder elements in the Pebble Bed Reactor-Steam Power Plant is described. Graphite spheres of varying density were infiltrated with thorium nitrate solutions, followed by denitration to thorium oxide.
Date: June 15, 1960
Creator: Parker, W. E. & Rusinko, F.
Partner: UNT Libraries Government Documents Department
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Water Chemistry for KER Loop 1- June 29, 1959 to December 31, 1959

Description: One of the primary reasons for operating the high pressure KER loops is to obtain information concerning water quality control characteristics for recirculating water cooled reactors. The KER-1 loop is predominantly carbon steel and approximates the water quality conditions specified for the New Production Reactor (NPR).
Date: June 15, 1960
Creator: Demmitt, T. F. & Wood, E. R.
Partner: UNT Libraries Government Documents Department
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Project Cowboy : Physical Properties of Salt Samples

Description: The purpose of Project Cowboy was to investigate the seismic signals generated by chemical explosions in underground cavities, with particular emphasis on the possibility of decoupling of these signals from the surrounding media. The project site was the Carey Salt Company salt mine, located approximately five miles west of Winnfield, Louisiana. The tests were run during fiscal year 1960. This report presents the results of tests performed on specimens from the samples of salt taken in the area. more
Date: July 15, 1960
Creator: Guido, Raymond S. & Warner, Stanley E.
Partner: UNT Libraries Government Documents Department
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Reactor Grade Zircaloy-2 Ingot

Description: Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-2, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Reactor-Grade Zircaloy-4 Ingot

Description: Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-4, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Sheet and Strip Material

Description: Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Tubing for Fuel Sheathing

Description: Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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Zircaloy-2 Wire Material

Description: Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Partner: UNT Libraries Government Documents Department
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