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P-V-T Relationships of BF₃ Gas

Description: Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.
Date: July 30, 1960
Creator: Smith, C. R. F.
Partner: UNT Libraries Government Documents Department
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THERMAL CYCLING TESTS ON U-10 w/o Mo FOR THE ORNL FAST BURST REACTOR

Description: One of the uncertainties concerning the use of uranium-10 wt.% molybdenum in the ORNL Fast Burst Reactor is the thermal-cycling behavior of this alloy. Accordingly, an experimental program was undertaken to determine whether transformation or distortion of gamma-phase uranium--10 wt.% molybdenum can occur during simulated fast-burstreactor thermal cycling, and, should transformation occur, to establish the thermal cycling behavior of partially transformed uranium- - 10 wt.% molybdenum. Specimen… more
Date: July 30, 1960
Creator: Minushkin, B.
Partner: UNT Libraries Government Documents Department
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Valve Stem Freeze Seal for High-Temperature Sodium

Description: Abstract: An experimental study of valve stem freeze seals was undertaken as part of the effort to develop components for high temperature service in advanced sodium-cooled reactor systems.
Date: July 30, 1960
Creator: McDonald, J. S.
Partner: UNT Libraries Government Documents Department
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Valve Stem Freeze Seal for High-Temperature Sodium

Description: Valve stem freeze seals for high-temperature service in advanced sodium- cooled reactor systems were studied. An experimental model, suitable for use with a 6-in. size valve, operated satisfactorily under a variety of conditions. The freeze seal region was cooled by natural convection to ambient atmosphere; cooling by both circumferential and longitudinal finned sections was experimentally studied. The operating conditions included sodium bulk temperatures up to 1300 tained F, sodium pressures … more
Date: July 30, 1960
Creator: McDonald, J.S.
Partner: UNT Libraries Government Documents Department
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Pilot Plant Preparation of Thorium Oxide and Thorium-Uranium Oxide During Fiscal Year 1960

Description: Test quantities of thoria (aporoximately 3800 lb of thorium oxide and 3200 lb of mixed thorium-uranium oxide) were prepared during FY-1960 for members of the Reactor Experimental Engineering Division (REED). For preparation of thorium oxide, the calcination temperature was varied from 650 to 1800 deg C. The surface area of the fired oxide ranged from 0.5 to 25 m/sup 2//g and the mean particle size ranged from 1 to 8 microns. For preparation of mixed thorium-- uranium oxide, the calcination temp… more
Date: July 29, 1960
Creator: Winget, R. H., Jr.
Partner: UNT Libraries Government Documents Department
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PREPARATION AND EVALUATION OF ALUMINUM-35 w/o URANIUM ALLOYS CONTAINING UP TO 3 w/o TIN OR ZIRCONIUM

Description: The effects of ternary additions of up to 3 wt.% Sn or Zr to an Al-35 wt.% U extrusion alloy were evaluated on the basis of casting characteristics, UAl/sub 3/ retention, extrusion behavior, mechanical properties, and corrosion resistance. Both additions increased the fluidity of the alloy, and both promoted retention of UAl/sub 3/. The best fluidity was obtained by a 2 wt.% Sn addition, while Zr was the more effective stabilizer of UAl/sub 3/. The retention of UAl/sub 3/ decreased the extrusio… more
Date: July 29, 1960
Creator: Daniel, N.E.; Foster, E.L. Jr. & Dickerson, R.F.
Partner: UNT Libraries Government Documents Department
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Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels

Description: Facilities are to be designed for installation at Hanford for the reprocessing of irradiated, low enrichment fuels from non-production reactors, see Reference 1 and 2. The initial design of the processing facilities is to be based on processing the fuels discharged from the Dresden, Yankee, Piqua, Pathfinder and Shippingport (blanket elements only) reactors. Properties of the fuels and cladding make it impossible to completely process them in existing equipment, although the separation and deco… more
Date: July 29, 1960
Creator: Bierman, S. R.; Graf, W. A.; Kass, M.; Kligfield, G.; McKee, R.W.; Patridge, L. F. et al.
Partner: UNT Libraries Government Documents Department
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Scavenging of Particulate Matter in Connection With Nuclear-Powered Ships. Final Scientific Report

Description: The work carried out over a 2 1/2-yr period on the scavenging of radioactive particles which might be released by the reactor system of a nuclear- powered ship is summarized. Two types of dispersions were considered: aerosols and hydrosols. Radioactive aerosols were scavenged by heterogeneous coagulation with solid and liquid aerosols produced within the radioactive aerosol cloud. Liquid or highly hygroscopic particles, which can be classified as solid particles with liquld films on their surfa… more
Date: July 29, 1960
Creator: Rosinski, J.
Partner: UNT Libraries Government Documents Department
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Static Stress Determinations in Salt, Site Cowboy

Description: An investigation was made to determine the stress field in the salt dome and the stress concentrations on the surface of the small (12-ft diameter) sphere. For the most part, the apparatus and techniques used in the investigation are new and have not been described in other reports. Therefore the theory, concepts, apparatus, and some of the lists made to determine the reproducibility of the apparatus are described briefly. (W.L.H.)
Date: July 29, 1960
Creator: Merrill, Robert H.
Partner: UNT Libraries Government Documents Department
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Supplement D, Production Test IP-314-A, measurement of fuel element temperature changes as the result of film deposition

Description: The thermocouple train is modified by the substitution of one eighteen-inch enriched and four twenty-four inch natural uranium tubular elements for the two thirty-six inch enriched tubular elements used on the original thermocouple train. The operating limits for the loading have been changed because of the change in charge power. This supplement also authorizes the addition of fuel elements upstream of the thermocouple train if the thermocouple element and heater elements do not provide enough… more
Date: July 29, 1960
Creator: Kratzer, W. K. & Peacock, D. W.
Partner: UNT Libraries Government Documents Department
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Chemical Techinology Division, Unit Operations Section Monthly Progress Report, April 1960

Description: Experiments showed that 30% tributyl phosphate will not extract acid- deficient species of uranyl nitrate. Flooding throughputs for the Mark I stacked- clone contactor ranged from 600 cc/min organic at zero aqueous to 60 cc/min organic at 1950 cc aqueous. A large electronic vibrator of 5000-lb thrust was found somewhat inferior to pneumatic vibration for compacting oxide fuels into stainless-steel tubes. Tests were started on the use of fixed-bed CuO oxidizers for removing hydrogen contaminatio… more
Date: July 28, 1960
Creator: Whatley, M E; Haas, P A; Horton, R W; Ryon, A D; Suddath, J C & Watson, C D
Partner: UNT Libraries Government Documents Department
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Inventory radioactive liquid waste to ground 200 Areas, 1945--1959

Description: Since startup in January 1945 through December 1959, 4 {times} 10{sup 9} gallons of radioactive liquid wastes have been discharged to cribs and trenches at HAPO by the Chemical Processing Department facilities in the 200 Areas. These wastes contained approximately 2.5 {times} 10{sup 6} curies of beta emitters. The Scavenged Waste Recovery Program was completed in 1957 and Redox Plant process changes were made during the latter part of 1958. These changes resulted in significant reduction in the… more
Date: July 28, 1960
Creator: Brown, G. D. & McConiga, M. W.
Partner: UNT Libraries Government Documents Department
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FLUORINE DISPOSAL USING CHARCOAL

Description: Wood, coke, and coconut-shell charcoals were evaluated for fluorine entrapment. The coconut-shell charcoal produced the smallest amount of solid and liquid reaction products. Efficient removal of fluorine was accomplished by the coconut-shell charcoal in a 5-in.-diameter reactor with a feed containing 25% fluorine at flow rates from 100 to 400 scfh and reactor-wall temperatures of 1200 to 1800 deg F. (C.J.G.)
Date: July 26, 1960
Creator: Houston, N. W.
Partner: UNT Libraries Government Documents Department
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Reactor Physics Calculations for the Msre

Description: A compilation is presented of results obtained to date from a number of reactor physics calculations for the molten salt reactor experiment (MSRE). Included are one-dimensional multigroup and two-dimensional twogroup calculations of critical mass, flux, and power density distributions; gamma heating in the core can, reactor vessel, and core support grid; drain tank criticality; and an estimate of the beta , gamma , and delayed neutron dose rates due to fission products in the fuel contained in … more
Date: July 26, 1960
Creator: Nestor, Jr, C. W.
Partner: UNT Libraries Government Documents Department
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Transistorized Pulse Counting Equipment

Description: This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.
Date: July 26, 1960
Creator: Henry, John J.
Partner: UNT Libraries Government Documents Department
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MINERAL AND SEDIMENT AFFINITY FOR RADIONUCLIDES

Description: In determining radionuclide sorption by clay minerals, shortcomings in the filtration technique for solid separation and in the contact times selected for testing were noted. Filters were found to have a high affinity for cesium and strontium when these elements were present in tracerlevel concentrations. Sorption equilibrium was not established in 24 hr, and the contact time was extended to 7 days. The affinity of the clay minerals illite, kaolinite, montmorillonite, and vermiculite for select… more
Date: July 25, 1960
Creator: Sorathesn, A; Bruscia, G; Tamura, T & Struxness, E G
Partner: UNT Libraries Government Documents Department
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Plowshare Program : Peaceful Uses for Nuclear Explosives

Description: The concept of thermonuclear explosives as a potentially cheap and almost inexhaustible energy source for mankind's non military needs has for several years been under active consideration at the Lawrence Radiation Laboratory. Many of the proposed peaceful applications involve underground nuclear explosions, and several experiments at the AEC Nevada Test Site have provided valuable insight into the phenomenology of such explosions. Among the possible uses currently under consideration are excav… more
Date: July 25, 1960
Creator: Lombard, David B.
Partner: UNT Libraries Government Documents Department
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