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Blast Loading and Response of Underground Concrete-Arch Protective Structures

Description: Four reinforced-concrete arch structures, with the top of arch crown 4 ft below ground surface, were exposed at high overpressure ranges from Priscilla Burst in order to obtain data on their resistance to blast, radiation, and missile hazards. The four structures received actual air overpressures of 56, 124, and 199 psi and suffered only minor damage, all remaining structurally serviceable. The entranceway used for the structures sealed out the air pressure. It was not designed to attenuate radiation and thus did not provide adequate radiation protection for personnel. There were no missile and apparently no dust hazards in any of the structures. Results of the test indicate that an underground reinforced-concrete arch is an excellent structural shape for resisting the effects of a kiloton-range air burst. (C.H.)
Date: June 1, 1959
Creator: Flathau, W.J.; Breckenridge, R.A. & Wiehle, C.K.
Partner: UNT Libraries Government Documents Department
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LITERATURE SEARCH ON LEAD-BISMUTH ALLOYS

Description: BS>The use of a lead-bismuth alloy as a coolant in the removal of heat from power-generating nuclear reactors was considered with the possibility that its ternary alloy with uranium or plutonium might be of use in a reactor of the circulating-liquid-fuel type. Information collected from the literature covering phase-equilibrium studies, physicalproperty data, and reactivity of this alloy toward other substances is presented. (auth)
Date: February 14, 1950
Creator: Lee, M.E.
Partner: UNT Libraries Government Documents Department
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CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES

Description: A report is presented to provide a tool for evaluating the relative economic incentives for changing reactor core parameters. The cost relations are shown in terms of differential cost in lieu of total cost. A total cost for each reactor described is included so that power costs for a specified set of parameters can be obtained. A description is also included concerning 5 reactor types considered along with a discussion of the effects on power costs of varying the significant core parameters. A listing of basic references is given. (J.R.D.)
Date: January 1, 1959
Creator: Atomic Energy Commission, Washington, D.C. & Jackson and Moreland, Inc., Boston
Partner: UNT Libraries Government Documents Department

Happy Mother

Description: The bronze sculpture consists of a woman with a ponytail holding three children as they play.
Access: Restricted to UNT Community Members. Login required if off-campus.
Date: 1958
Creator: Gross, Chaim
Partner: UNT College of Visual Arts + Design
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Concerto Grosso for Oboe, Clarinet, Piano, and String Quartet

Description: The first movement of the present work is a French overture patterned in form after the overtures of Jean Baptiste Lully. The second movement (Lento) is a simple ABA song-form and presents a rather rhapsodic development of its theme. The third movement consists of a set of six continuous variations on the polyphonic chanson Revecy venu du printans by Claude le Jeune (1528-1600). The last movement is a rondo (ABACADA).
Date: August 1956
Creator: Taliaferro, Lloyd Carr
Partner: UNT Libraries
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SRE CONTROL ROD SHIELDING REQUIREMENTS

Description: Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended power run of 90 days duration. (M.C.G.)
Date: October 22, 1957
Creator: Whittum, H.O.
Partner: UNT Libraries Government Documents Department
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Creep Rupture in the Presence of a Fast Neutron Flux

Description: Possible mechanisms for creep rupture during irradiation are examined. Evidence that the rupture occurs by grain boundary sliding alone, or by vacancy condensation, is compared. It is observed that vacancy condensation is the more probable mechanism, and that this mechanism predicts a reduction in creep rupture life for metals exposed to a fast neutron flux (neglecting effects of radiation annealing). (T.F.H.)
Date: January 14, 1959
Creator: Gregory, D. P.
Partner: UNT Libraries Government Documents Department
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Production of Pebble-Type Fuel Elements

Description: A capillary-drop method of producing spherical shapes of brittle materials less than 0.l00 inch in diameter was developed. It appears to be a feasible means for producing large numbers of pebble-tyne fuel element cores. Coating of pebble-type fuel element cores by the coating-pan technique, though not adequately developed, showed promise. (auth)
Date: June 1, 1955
Creator: Brassfield, H.C.
Partner: UNT Libraries Government Documents Department

[Basilica di Santa Maria della Salute]

Description: Photograph of the Basilica di Santa Maria della Salute in Venice, Italy. The basilica is visible in the middle ground surrounded by canals on both sides. A cluster of buildings is visible in the right foreground. Buildings on the other side of the Grand Canal are visible in the background.
Date: 1953
Creator: Gough, Ray
Partner: UNT College of Visual Arts + Design
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Demodectic Mange in Cattle.

Description: Describes demodectic mange, its causes, how it is recognized on cattle, and what can be done to control the disease.
Date: August 1958
Creator: United States. Agricultural Research Service. Animal Disease and Parasite Research Division.
Partner: UNT Libraries Government Documents Department
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GCRE-I HAZARD SUMMARY REPORT

Description: The GCRE-I hazard summary report is supplemented in the following areas: geometry and operation of the steam cooling system, the reactor coolant by-pass, and by-pass valving; the means by which by-passed circuits are prevented from remaining unintentionally disabled; design details, and details of procedure for core flooding operations. (A.C.)
Date: March 1, 1959
Partner: UNT Libraries Government Documents Department
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REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE

Description: It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 3000 psi and temperatures to 300 deg F. At temperatures of 100 to 400 deg F and pressures to 5000 psi continuous deformation of the cavity resulted. Initial movement of the salt was observed at all pressures. This was evidenced by vertical deformation and cavity size reduction. It was noted that a point of structural equilibrium was reached at lower temperatures when the pressure did not exceed 5000 psi. A literature study reveals that the most common type of cavity utilized in liquefied petroleum gas storage is either cylindrical or ellipsoidal. A few are pear or inverted cone shaped. There was no indication of leakage for cavities when pressure tested for as long as 72 hr. This indicates that the salt mass is not permeable under conditions of prevailing underground temperature and pressure. Salt specimens tested under atmospheric Pressure and temperature exhibited permeabilities of 0.1 to 0.2 millidarcys. The cost of completing underground storage cavities in salt masses is expected to be approximately 05 per barrel of storage space. (auth)
Date: January 15, 1959
Creator: Brown, K. E.; Jessen, F. W. & Gloyna, E. F.
Partner: UNT Libraries Government Documents Department
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MATERIALS PROBLEMS IN THE ROVER PROGRAM

Description: Problems in fuel element development for the Rover program are discussed. Properties of refractory materials which remain solid above 2500 deg C are described. Tensile and compressive creep properties of graphite were deterndined. The compatibility of fuel element materials with the hydrogenous working fluid was also considered. The effect of composition on the properties of graphite is discussed. (M.C.G.)
Date: January 1, 1959
Creator: MacMillan, D.P.
Partner: UNT Libraries Government Documents Department
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