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An Investigation of the Application of the Gas Generator-Free Turbine Cycle to a Nuclear Powered Aircraft

Description: This study has investigated the feasibility of installing a gas generator-free turbine type power plant in the R3Y aircraft, using a circulating fuel reactor as a power source. Two variations of the cycle were considered. The split flow cycle bleeds high temperature, high pressure air from the gas generator directly to the free turbine in the wing. The through flow cycle partially expands the high temperature, high pressure air through the compressor turbine of the gas generator then directs th… more
Date: August 1, 1957
Creator: Alvis, J. H. & Chessman, S. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Manufacture of the ThO$sub 2$-UO$sub 2$ Ceramic Fuel Pellets for Borax-IV

Description: Preliminary investigation indicated that it was possible to prepare thoria-urania solid solutions by sintering in air a mixture of ThO/sub 2/ and U/ sub 3/O.sub 8/. The U/sub 3/O/sub 8/ on heatin g in air was found to disassociate, and when heated with ThO/sub 2/, the resultant body was essentially a ThO/sub 2/-UO/sub 2/ solid solution. The methods used in preparing and granulating the ThO/sub 2/ and U/sub 3/O/sub 8/ for the BORAX-IV loading are discussed in detail. This material was dry presse… more
Date: August 1, 1957
Creator: Handwerk, J. H.; Hoenig, C. L. & Lied, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physics Division Summary Report for April Through June 1957

Description: A laminated scintillator was constructed of Ag activated ZnS in fused B/ sub 2/O/sub 3/. The efficiency of this scintillator was determined and compared with other scintillators. J-values of O for the 41.5 and 44.5 ev and 1 for the 52.6 ev resonances in Pu/sup 239/ were determined. New cross section values are reported for U/sup 235/. Additional attempts to establish fission product mass distribution as a function of neutron energy are reported. A method of analyzing neutron resonances by using… more
Date: August 1, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SUPERHEATING WATER-BOILER. Reactor Design and Feasibility Study

Description: A preliminary design is presented for a boilingwater reactor with integral nuclear superheater, which produces steam at 1200 psia, 950 deg F. The design uses stainless steel, UO/sub 2/, and water for materials and stays generally withln the limits of existing reactor technology. The design output is 129,445 lbs of steam per hour at the stated conditions, which corresponds to 17,500 shaft horsepower in a naval steam plant and to 47.25 Mw of heat. This is thought of as a ship propulsion reactor, … more
Date: August 1, 1957
Creator: Marbury, F.; Alden, J.W.; Bedford, R.E.; Bilenas, J.A.; Coppersmith, W.C.; DeVincentis, J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TRANSIENT LOADING OF THIN-WALLED CYLINDERS. Interim Technical Report

Description: The effect of internal static loading and internal transient loading on the deformation of thin-walled tube specimens was studied for both the elastic and plastic regions. The specimens employed were six inch sections of type 304, seamless, stainless steel tubing having a nominal O.D. and wall thickness of 3/4 inch and 0.020 inch, respectively. The transient forces were obtained from detonations of stoichiometric hydrogen-oxygen mixtures contained in a shocktype detonation tube. Each specimen w… more
Date: August 1, 1957
Creator: Mosier, S.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A CURRENT REVIEW OF BODY FLUID ANALYSIS, PROCEDURES, AND METHOD OF REPORTING--JANUARY 1957

Description: Direct alpha counting to determine fissile material in dilnte solutions of high total solids content is likely to be inaccurate due to the difficulty of preparing thin sources. This report describes a neutron-activation analysis method which eliminates this risk. Results obtained by the neutronactivation analysis for U/sup 238/ in solution are compared with results obtained from other methods. The standard deviation and sensitivity are shown. (auth)
Date: August 1, 1957
Creator: Brown, P.E.; Davis, D.M. & Henley, L.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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GAS COOLED PEBBLE BED REACTOR FOR A LARGE CENTRAL STATION. Reactor Design and Feasibility Study

Description: An optimum econonic design for a high temperature, helium cooled, central station reactor power plant of about 400 Mw of electric power was determined. The core consists of a randomly packed bed of unclad graphite spheres, approximately one in. in diameter, impregnated with U/sup 233/ and thorium such that a conversion ratio of near unity is achieved. The high temperature helium permits steam conditions, at the turbine throttle, of 1000 deg F and 1450 psia. (auth)
Date: August 1, 1957
Creator: Schock, A.; Bruley, D.F.; Culver, H.N.; Ianni, P.W.; Kaufman, W.F.; Schmidt, R.A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Radiation on Chemical Reactions. Final Report

Description: Primarily the studies have been devoted to a search for chemical reactions which are promoted by gamma radiation. The underlying purpose behind the studies has been to develop uses for the radiation available from waste fission prcducts. A brief description of all the reactions studied during the program is presented along with appropriate references to the original reports and publications. These give the detailed account of the work done on each reaction and the reader is referred to them for… more
Date: August 1, 1957
Creator: Martin, J. J. & Anderson, L. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EVALUATION OF FCDA FAMILY SHELTER, MARK I, FOR PROTECTION AGAINST NUCLEAR WEAPONS. Preliminary Report

Description: An underground reinforced-concrete family shelter designed for six persons was tested at three anticipated nuclear blast overpressures: 30, 48, and 65 psi. The structures were calculated to sustain a 30-psi long-duration overpressure. Postshot examination of all shelters lndicated there was little or no deflection in the reinforced-concrete members. Although the actual blast load was of short duration, the natural period for the structures was also shortp therefore it is felt that the structure… more
Date: August 1, 1957
Creator: FitzSimons, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preparation of Radiation Sources From Fission Products by the Clay Process

Description: This study was made to determine the feasibility of producing usable radiation sources by the montmorillonite clay process. The clay process was developed at Brookhaven National Laboratory primarily to solve the problem of ultimately disposing of waste fission products. After reviewing the process in detail, it is shown that radiation sources may be prepared with specific activity as high as 4.5 curies of Ce/sup 137/ per gram of clay. Sources of this strength would be entirely suitable for such… more
Date: August 1, 1957
Creator: Schoolmeester, J. E. & Martin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AN 80 MEGAWATT AQUEOUS HOMOGENEOUS BURNER REACTOR. Reactor Design and Feasibility Problem

Description: An 80 Mw aqueous homogeneous burner reactor suitable for producing 20 Mw of electricity at a remote location is described. The reactor fuel consists of a light water uranyl sulfate solution which acts as its own moderator and coolant. The uranium is highly enriched (93% U/sup 235/). The primary considerstions for the design were simplicity and reliability of the components, automatic demand control and safe for any load change, full xenon override not required, possibility of construction withi… more
Date: August 1, 1957
Creator: Chapman, R.H.; Collins, H.L.; Dollard, W.J.; Fieno, D.; Hernandez- Fragoso, J.; Miller, J.W. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An Investigation of the Chattanooga Black Shale of Tennessee as a Source of Uranium Progress Report: July 1, 1956-June 30, 1957

Description: From introduction: The primary aim of this study is to present as complete a geologic picture as possible, of the Chattanooga shale in its outcrop area of the Eastern Highland Rim and the Northern Highland Rim of Tennessee and adjacent Kentucky. Special emphasis has been placed upon the stratigraphic relationships and their implications upon the age and manner of origin of the sediments and upon the origin, source, and distribution of uranium in the shale.
Date: August 1, 1957
Creator: Klepser, Harry J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PROCESS DEVELOPMENT QUARTERLY REPORT. PART II. PILOT PLANT WORK

Description: ABS>The stoicbiometric HNO/sub 3/ concentrations required to digest feed materials to 200g U/I, 3N excess acid are tabulated. Stoichiometrically the minimum HNO/sub 3/ concentration required to dissolve feed materials to flowsheet conditions flowsheet tests is presented. The sensitivity of the Weldon Spring TBP-extraction system to process flow rates is discussed. A series of pilot plant experiments are deserined for removing TBP from raffinate. Steam distillstion of the raffinate slurries prov… more
Date: August 1, 1957
Creator: Elliott, B. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During July, 1957

Description: A report about equipment which is assembled and tested to determine the feasibility of measuring the thermal conductivity and electrical resistivity of irradiated uranium rods clad with Zircaloy 2 with NaK as the heat-transfer medium.
Date: August 1, 1957
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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