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Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report

Description: An analytical trajectory and aerothermodynamic analysis of a satellite containing a Task 2 thermoelectric generator was completed. A 300-statute mile circular polar orbit was used for this analysis and the launch was assumed to be from Vandenberg Air Force Base. Results of this study show that upon natural decay from a successful mission, the radio-cerium fuel will burn up in space at high altitude, thus only a very minor amount of radio cerium will be released to the stratosphere. A complete a… more
Date: December 27, 1960
Creator: Oehrli, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aeroradioactivity Survey and Areal Geology of the Savannah River Plant Area, South Carolina and Georgia (ARMS-I)

Description: Report regarding an airborne radioactivity survey that took place in the 10,000 square mile area near Augusta, Georgia. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
Date: December 1960
Creator: Schmidt, Robert G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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After Shutdown Heating in the HFIR

Description: After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanen… more
Date: December 29, 1960
Creator: McLain, H. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ames Laboratory Annual Summary Research Report in Metallurgy: 1960

Description: Annual summary documenting research related to metallurgy at Ames Laboratory. Discussions are given of developments in the following areas: the preparation and purification of metals; phase equlibria and thermodynamic properties of alloys; physical and mechanical properties of metals and alloys; solid state studies; separation processes; and investigations dealing with diffusion, oxidation, and reduction, halide reactions, preparations, vapor pressure measurements, and transport reactions. (B.… more
Date: December 1960
Creator: Ames Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents

Description: The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date: December 16, 1960
Creator: Pierce, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis--Graphite Core Structure

Description: A study was made to determine the structural and functional adequacy of the EGCR graphite core design. Maximum stress and distortion of the core and the probable operating time before graphite cracking were determined. The major cause of stress is non-uniform fast-neutron flux, which causes non-uniform shrinkage of graphite components. The critical stress was found to be tensile. The criterion for determining the time of cracking of graphite columns appears to be the point at which the creep st… more
Date: December 14, 1960
Creator: Newton, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of E-N loadings

Description: Three E-N loaded tubes were dissolved, sampled and analyzed, starting November 9, 1960. The results of these analyses and an explanation of the methods used are the subject of this report. Each tube loading received an identification code in each facility in which it was processed. All of these codes are listed for future reference. Each batch of slugs was dissolved in a preflushed dissolver. When complete solution was indicated by a leveling off of the specific gravity, two 1 ml samples were t… more
Date: December 28, 1960
Creator: Zimmer, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium

Description: Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of … more
Date: December 27, 1960
Creator: Gaitanis, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Anion Exchange of Neptunium in Nitrate Solutions

Description: Technical report. From Abstract : "The absorption and elution of the anionic nitrate complex of neptunium (IV) were studied with several anion exchange resins and under a wide variety of conditions." From Introduction : "The objective of this study was to provide a technical basis for selecting process conditions for the recovery of Np."
Date: December 1960
Creator: Burney, Glenn A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM SUMMARY REPORT ON MATERIALS FOR THE GCRE-II

Description: Investigatiors were made of various materials for development of metal- canned and semi-homogeneous GCRE-II fuel element concepts. The materials were studied for application to development of fuels, grapanite, silicon-silicon carbide coatings, metal claddings, carburization barrier coatings, and graphite joining. A survey of the literature showad that uranium carbide fuels are superior to other types for the applications described and that refractory metal or metal carbide fuel coatings appear … more
Date: December 30, 1960
Creator: Carpenter, R. & Del Grosso, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE ASSEMBLY, SODIUM BONDING AND INSPECTION OF EBR-II BLANKET RODS

Description: The Experimental Power Breeder Reactor (EBR-II) is a heterogeneous, unmoderated, Na-cooled reactor developed to provide engineering and operational information on fullscale central-station power plants. The enriched U-fissium alloy fuel is blanketed with depleted unalloyed U in type 304 stainless steel tubes. Details of fabrication and loading of these rods are given. (J.R.D.)
Date: December 1, 1960
Creator: Salley, R. L. & Bean, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[Basketball game in progress, 3]

Description: Photograph of a men's basketball game. North Texas State University freshmen going up against Southern Methodist University freshmen. The photo is a full-length picture of a basketball court that features a basketball goal on each end. Stands of crowds are behind the far basketball goal and to the right of the photo. A basketball play is developing near the goal. A referee looks on from the out-of-bounds line. Another referee watches from half-court. A scoreboard hangs from in the back wall of … more
Date: December 1960
Item Type: Refine your search to only Photograph
Partner: UNT Libraries Special Collections
open access

BIOLOGICAL AND MEDICAL RESEARCH DIVISION SEMIANNUAL REPORT, JULY THROUGH DECEMBER, 1959

Description: Progress is reported on the following studies: the possible relationship between environmental Ra/sup 226/ and incidence of bone tumors in human populations; the incidence of tumors in mice exposed to chronic gamma irradiation; the effects of chronic gamma irradiation on histology of testes cells; the effects of periodic exposure to gamma radiation on the mortality of guinea pigs; determinations of the density of various mouse tissues; the synthesis of dimethyl formarmide (DMF) and uranyl nitra… more
Date: December 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Bounce III

Description: BOUNCE III is a program which was written for the IBM-704 as part of a study of the parameters of the neutron distribution in a large thermal column. The program calculates the eigenvalues and corresponding eigenvectors of the matrix resulting from a diffusion-theory, multigroup description of the thermal neutron spectrum.
Date: December 15, 1960
Creator: Kerr, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Boundary Layer Between a Plasma and a Magnetic Field - I

Description: "The problem of a steady boundary layer or sheath between a plasma and a magnetic field is considered. A self-consistent transition layer is found which joins a uniform magnetic field at plus infinity with a collisionless field-free plasma region with arbitrary velocity distribution at minus infinity, i.e., a magnetic field profile is found such that the exact particle orbits in this field produce a current which gives rise to this field. An interesting feature of the solution is that, with any… more
Date: December 28, 1960
Creator: Grad, Harold, 1923-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Burnout Heat Fluxes for Low-Pressure Water in Natural Circulation

Description: Twenty-nine experimental determinations of burn-out heat flux were made with water flowing by natural circulaion through electrically heated vertical tubes with and without internal twisted tapes and through rectangular cross sections of three aspect ratios. Heated lengths varied from 10 to 33 in., system pressure at the testsection flow exit from 14.7 to 26.3 psia, inlet subcooling from 36 to 170 deg F, and burn-out heat flux from 13,000 to 218,500 Btu/hr/sq ft. Tests were made with both unres… more
Date: December 20, 1960
Creator: Gambill, W. R. & Bundy, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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