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Dissolution of aluminium oxide as a regulating factor in aqueous aluminum corrosion

Description: The solubility of aluminum corrosion product in contact with metallic aluminum in deionized water has been determined over the range 80 to 350/sup 0/C. Evidence is presented to show that oxide dissolution results in the formation of a porous oxide on aluminum exposed in refreshed dynamic systems. Dynamic corrosion rate data have been analyzed on the basis of parabolic film growth and a linear oxide degradation process acting simultaneously on the system. The degradation process has been shown to be a function of refreshment rate.
Date: August 31, 1959
Creator: Dillon, R.L.
Partner: UNT Libraries Government Documents Department
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Corrosion of Construction Materials in 234-5 Project Solutions

Description: The following report covers the construction materials selected for laboratory corrosion studies and the determination of their corrosion rates in process solutions.
Date: January 31, 1950
Creator: Koenig, W. W.
Partner: UNT Libraries Government Documents Department
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Progress Report on Refining of MgX and Other Uranium-Bearing Materials

Description: From abstract: "Results of two methods of reducing the phosphate and vanadate contents of MgX, a uranium precipitate from the Belgian Congo, are described...Chemical analyses of several samples of pitchblende and MgX are presented."
Date: August 31, 1950
Creator: Ewing, R. A.; Kiehl, S. J., Jr. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
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Topical Report on Refining of MgX and Other Uranium-Bearing Materials

Description: This report discusses a study which explores the effects of feed and acidity on extractive methods. From abstract: "Results from fractional precipitation of MgX from dilute sulfuric acid solutions indicate that, in the presence of sufficienct iron, phosphate is precipitated as ferric phosphate, and not as uranyl phosphate."
Date: December 31, 1950
Creator: Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
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Identification of Slag Constituents from Uranium Metal Production Bombs

Description: Abstract: "X-ray and microscopic examination of slags from uranium metal production bombs which gave good and bad yields in the plant at St. Louis have indicated the significance of uranium oxide formation. Apparently the oxide (UO2) results from reaction of the UF4 with linear material, particularly with moisture in the liner."
Date: January 31, 1952
Creator: Vaughan, D. A.; Cocks, G. G. & Schwartz, C. M.
Partner: UNT Libraries Government Documents Department
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Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 1. Laboratory Investigations

Description: Report discussing laboratory investigations of thorium nitrate purification. Batch equilibrium data, solubility data, viscosity data, density data, and the results seven batch countercurrent extraction tests and two selective stripping tests are included.
Date: July 31, 1952
Creator: Ewing, R. A.; Fishel, J. B.; Kiehl, S. J., Jr.; Sharpe, R. E. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
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Beryllia and Beryllia-Beryllium Bodies for Moderating Cores in Fuel Elements

Description: From introduction: This report presents the results of the two phases of the work: study of the compatibility of beryllia bodies with a coating material, molybdenum; and studies of beryllia-beryllium body fabrication.
Date: July 31, 1952
Creator: Long, R. E.; Duckworth, W. H.; Saller, Henry A.; Stacy, J. T.; Miller, R. A. & Schofield, H. Z.
Partner: UNT Libraries Government Documents Department
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Final Report on Nonaqueous Extractive Methods for Western Uranium Ores

Description: This report discusses tests of several nonaqueous extractive methods meant to leach Western ores of uranium and vanadium. Explanations of different methods are given as well as their extraction results.
Date: January 31, 1955
Creator: Ewing, R. A.; Kiehl, S. J., Jr. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
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Progress Report on the Concentration of Pitchblende

Description: Abstract: "The results of leaching studies on sulphide froth products obtained from the flotation of high-sulphur pitchblende are presented. The distribution of molybdenum in flotation products is also given. The flotation test at Middlesex is evaluated."
Date: December 31, 1950
Creator: Wesner, A. L.; Tangel, O. F. & Richardson, A. C.
Partner: UNT Libraries Government Documents Department
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Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 2. Mixer-Settler Pilot Plant Investigations

Description: From abstract: "This report describes the construction and operation of a mixer-settler pilot plant for the purification of mantle-grade thorium nitrate. The liquid-liquid extraction process utilized 30% tributyl phosphate - 70% 'Solvesso-100' as the organic solvent and nitric acid as the salting agent. Continuous steady-state operation of the equipment was demonstrated, with very good recovery of thorium."
Date: July 31, 1952
Creator: Burkhart, C. A.; Foley, D. D.; Retzke, F. A.; Filbert, Robert B., Jr. & Clegg, John W.
Partner: UNT Libraries Government Documents Department
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Enamels for the Protection of Aluminum Cans for Uranium Slugs

Description: The following report examines the most suitable enamels recommended for protection of aluminum slug cans.
Date: August 31, 1955
Creator: Schultz, John; Tripp, Harlan P.; King, Burnham William, 1907- & Duckworth, Winston H.
Partner: UNT Libraries Government Documents Department
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Strength Properties of Joint Designs for Joining Tubes to Tube Sheets

Description: This report describes the results of a study to determine the mechanical properties of joining stainless steel tubes to stainless steel tube sheets and evaluating the joint types made by various combinations of rolling and welding.
Date: July 31, 1953
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Alaska survey area

Description: Report documenting the suitability of Alaska for plant locations to produce synthetic liquid fuels, based on raw materials such as coal and natural gas.
Date: October 31, 1950
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of New Mexico

Description: Report documenting the suitability of New Mexico for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest
Date: October 31, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Montana

Description: Report documenting the suitability of Montana for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest
Date: October 31, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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Vernatherm functional test, Test Project No. 14

Description: The Vernatherm unit is a temperature sensitive capsule which translates temperature change to mechanical movement of a brass plunger. A change in phase of a hydrocarbon contained in a cylinder caused by temperature change, causes movement of the brass plunger. The units are available for various temperature ranges. The adaptation considered was to monitor the outlet water temperature from individual process tubes in the ``G`` pile. The purpose of the test was to determine the magnitude of error, if any, that is induced in a standard Vernatherm unit of known calibration when subjected to gamma irradiation. The accuracy of the units prior to irradiation was within 1.25 F. An examination of the calibration curves shows that a hysteresis effect in the hydrocarbon of the unit causes the curve of descending temperature to be displaced from the ascending temperature curve. The effects of irradiation were to decrease the accuracy to within 3.75 F. After a total exposure of 17,416 {times} 10{sup 4}R at 1.1 MEV. Since the exposure of 11,441 {times} 10{sup 4}R is equivalent to approximately 2,000 months exposure in the pile at 250 MW they can conclude that the effect of radiation is not detrimental since the increase in accuracy is only within 0.75 F.
Date: October 31, 1951
Creator: Smith, J. L.
Partner: UNT Libraries Government Documents Department
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Development of the Hanford Slave Manipulator for Use in the Multicurie Cells at Hanford

Description: Introduction: "During the early planning of the multicurie cells at Hanford it was decided that a slave type manipulator would be necessary to perform the experiments for which the cells were being designed. The design required steel roofs for installation through a port hole in the face. Technical Services Equipment Development began developing the proposed manipulator in January 1951 by making a study of those existing at that tune. None met the requirements which had been established; therefore, the design of a special manipulator was started immediately."
Date: October 31, 1952
Creator: Field, Richard E. & Gifford, John F.
Partner: UNT Libraries Government Documents Department
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Reduction of rear face Zn{sup 65} activity

Description: This report discusses two methods which have been considered to reduce the rear face activity. The first involves the use of a solids purge to scour out the activity, and the second employs the use of a chromic acid purge to put the activity into solution. Solids purging is found to be ineffective in reducing rear face activity levels. A chromic acid purge conducted at 60 C for 1/2 hour can be expected to reduce the Zn{sup 65} activity level about five fold without injuring the reactor or causing any harmful aftereffects.
Date: January 31, 1955
Creator: de Halas, D. R. & Gay, R. H.
Partner: UNT Libraries Government Documents Department
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Tube Power Limits -- Past, Present and Future

Description: During the history of operation of the Hanford reactors, several methods have been utilized to establish an outlet water temperature or ``Panellit`` limit based on the stability of water flowing through the process tubes. These methods have been known as ``Excess Header Pressure Limits,`` ``Trip Before Boiling Limits,`` and the most recent, ``Trip Before Instability Limits.`` Each new concept vas accepted only after considerable experimental data had proved the new method to be safe and operationally feasible. It is anticipated that in the future other tube outlet water temperature limits will be developed based on new technology. The purpose of this document is to present, in simple terms, an understandable explanation of previous operating limits, to discuss the status of the present Instability Limits, and to outline the direction of future work in raising the outlet water temperature limits.
Date: May 31, 1955
Creator: Carbon, M. W. & Gilbert, W. D.
Partner: UNT Libraries Government Documents Department
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Design study GEO-14, Segregation of Redox and TBP UO{sub 3} production, revised March 29, 1951

Description: Authorization has been received in the form of Modification No. 5 to Directive HW-158, dated March 23, 1951 to provide the necessary equipment and piping in the currently planned UO{sub 3} plant to permit the segregation of UO{sub 3} arising from the processing of stored metal waste (TBP) from that arising from ``current`` pile operation (Redox). In anticipation of this, the S Division, Manufacturing Divisions, requested that a study be made of the feasibility and cost of providing facilities for such segregation. This report is the result of that study. It concludes that by providing additional liquid storage and handling equipment, the desired segregation can be accomplished at a cost estimated to be approximately $128,000. $106,500 would be for Construction and $21,500 for Engineering. The schedule for this work will be reflected in the forthcoming modification to the C-361 Project Proposal. The general method of operation is alternately to store and process solution from TBP and Redox. The solution from TEP will be of a composition equivalent to the formula UNH and will require five days each week to process in the decomposition pots. The solution from Redox is received as 60% UNH and is batch concentrated in the storage tank to between 80 and 100% UNH, depending on stability. This solution will be processed in the decomposition pots in two days.
Date: March 31, 1951
Creator: Ludlow, J. O.
Partner: UNT Libraries Government Documents Department
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Fuel element performance

Description: For some time, it has been considered that cycling natural uranium fuel elements through the {alpha}-{beta} transformation point (approx. 662 C) is a contributing factor in split type ruptures. This hypothesis is based upon the fact that the transition temperature, a one percent increase in volume occurs. It is reasoned that as the uranium hardens under irradiation, it becomes progressively less able to adjust to the severe stresses imposed by the volume change as the material cycles through the {alpha}-{beta} transformation point. Failure finally occurs by a splitting of the core. The IPD is now interested in evaluating some of the effects of reactor operation upon fuel performance. It appears that the life of solid fuel elements may be prolonged if sudden changes in reactor operation can be minimized. It is the purpose of this report to bring to the attention of FPD management the new ideas being developed in the IPD on split type failures and to point out the effect such thinking may have on future fuel element development activities. Based on a discussion with personnel in PID, there is reasonable hope that the performance of solid fuel elements will not be limited by the {alpha}-{beta} transformation, and that the solid geometry can be used to advantage in all HAPO production reactors.
Date: December 31, 1957
Creator: Hagie, L. T.
Partner: UNT Libraries Government Documents Department
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