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Metallurgical Laboratory, Chemical Research - Radiation Chemistry, the Effect of Radiation on Water and Aqueous Solutions of Inorganic Substances

Description: Technical report summarizing our knowledge of the chemical effects of ionizing radiation upon water and upon aqueous solutions of inorganic compounds. The types of radiation considered are beta rays, gamma and X rays, and heavy particles, notably neutrons, deuterons, alpha rays and fission recoils.
Date: February 22, 1944
Creator: Allen, A. O.
Partner: UNT Libraries Government Documents Department
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Quantitative Recovery of Tuballoy From Tuballoy Tetrafluoride

Description: Report discussing various procedures for recovering tuballoy from tuballoy tetrafluoride, also called "green salt." Results from trial runs of each procedure are presented.
Date: February 22, 1945
Creator: Gates, J. W., Jr.; Andrews, L. J. & Schaap, Ward B.
Partner: UNT Libraries Government Documents Department
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300 Area, February 12 through February 18

Description: Extrusion was run on one day, February 2, and a total of 271 billets (178 Type G, 12 type BT, and 81 red band) were processed. Two failures occurred among the red band billets; UM 6610 had begun to melt in the furnace and TX 3323 disintegrated on being extruded through the die. Samples of these billets are being checked chemically and metallurgically in an attempt to ascertain the cause for the hot-short characteristics of these billets. A sample cut from a rod which possessed zero strength (fell apart under no stress other than its own weight) at extrusion temperature was found to contain a large amount of microconstituent not ordinarily found in appreciable quantity on uranium sections. The distribution and appearance of the excess phase suggested at least partial liquation at the working temperature and it could, therefore, be responsible for the hot-short tendency.
Date: February 22, 1946
Partner: UNT Libraries Government Documents Department
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Control Chart Method Applied to Errors in Radioactive Counting

Description: Abstract: The Control Chart statistical methods, developed by Showhart for the control of quality of manufactured products, are applied to the control of Geiger-Miller counting instruments. Experiments are reported to show the use to the Control Chart method for detecting disturbances in instrumental behavior and for detecting radioactive effects so weak that they are near the limit of detection of the instruments. As a corollary, the control chart can be used to reduce to its practical limit the time required for tests.
Date: February 22, 1947
Creator: Schlecht, W. G.
Partner: UNT Libraries Government Documents Department
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Shielded room measurements, Final report

Description: The attenuation of electro-statically and electro-magnetically shielded rooms in the ``E,`` ``R,`` ``I,`` and ``T`` Buildings was measured so that corrective measure could be taken if the attenuation was found to be low. If remedial measures could not be taken, the shortcomings of the rooms would be known. Also, the men making the measurements should oversee construction and correct errors at the time. The work was performed by measuring the attenuation at spot frequencies over the range of from 150 kilocycles to 1280 megacycles with suitable equipment mounted in small rubber-tried trucks. The attenuation was determined by ``before and after`` shielding and/or ``door open and door closed`` measurements after installation of copper shielding. In general, attenuation in the frequency range of approximately 10 to 150 mc. was good and was of the order expected. At frequencies in the range of 150 mc. to 1280 mc., the attenuation curve was more erratic; that is, at certain frequencies a severe loss of attenuation was noted, while at others, the attenuation was very good. This was mainly due to poor or faulty seals around doors and pass windows. These poor seals existed in the ``T,`` ``E,`` and ``I`` Buildings because the doors were fitted improperly and somewhat inferior material was used. By experience from these difficulties, both causes were corrected in the ``R`` Building, which resulted in the improvement of the very high frequency (v.h.f.) range in this building. In some specific cases, however, the results were about the same. For the range of frequencies below approximately 10 mc., the attenuation, in almost all cases, gradually decreased as the frequency decreased and reached a minimum at .3 to 1.0 mc. This loss of attenuation was attributed to multiple grounding caused by moisture in the insulating timbers and will gradually decrease as the wood …
Date: February 22, 1949
Creator: Stanton, J.S.
Partner: UNT Libraries Government Documents Department
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Preservation of Laboratory Instruments in Static Storage

Description: It is desirable to place laboratory instruments in static storage so that they may be put into operation with only normal servicing. Such instruments may be subject to many forms of deterioration. There may be deterioration of metal parts due to chemical and electrolytic corrosion and the effects of moisture, excessive dryness, and microorganisms, i.e., mildew on organic parts. To preserve such instruments without disassembly or troublesome surface coatings, requires methods that will remove the major cause of deterioration - that is, excessive humidity, by reducing and maintaining the relative humidity of the air surrounding the item at 30 per cent or less. It is also necessary to eliminate or separate hygroscopic materials from the item since they will cause corrosion, by surface adsorption and condensation, even though a dry atmosphere is maintained. The methods and materials used must not only be efficient and economical but also require a minimun of maintenance, Protection against physical damage and temperature extremes is dependent upon the storage site and is not considered in this report.
Date: February 22, 1950
Creator: Gregg, J. L. & Shackelford, M. A.
Partner: UNT Libraries Government Documents Department
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Increased process water pressure to 105 buildings

Description: This document discusses increases in water pressure from the 190 Building process pumps which has been contemplated for a range of pressures up to 550 PSIG. The existing process pumps are dual units, consisting of a steam turbine driven primary pump operated: in series with an electric driven secondary pump. The secondary pumps installed in 100-B, D, F, and H Areas were designed for 400 PSIG working pressure, and were given factory hydrostatic tests of 600 PSIG. The 100-DR pumps were given factory hydrostatic tests of 650 PSIG. The Ingersoll-Rand Company advises that a working pressure of 425 PSIG is as high as they would-recommend for pump casing pressure on the secondary pumps. In consideration of problems incident to increased operating pressures, the immediate limiting factor is the total head pressure permissible on secondary pump casings. Other limiting factors are filter plant capacities, and 183 process water capacities.
Date: February 22, 1951
Creator: Measly, H. F.
Partner: UNT Libraries Government Documents Department
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[Discussion by R. M. Evans at a meeting held with the members of the Military Liaison Committee on February 17, 1954]

Description: Characteristics of the heavy water moderated and cooled reactor when fueled with natural uranium were compared with those of Hanford. The following topics were covered: (1) fundamental safety of the Savannah River Plant reactor and its fundamental efficiency as neutron collector; (2) many critical volumes result in a complex control system and high sensitivity of flux pattern to rod position changes; (3) due to lack of time had to sue slugs initially; (4) had to use D{sub 2}O sparingly; (5) effects of circulating cooling system; and (6) heat transfer considerations. Topics also discussed were Savannah River reactor with enriched loadings and irradiation of thorium in lieu of lithium alloy.
Date: February 22, 1954
Partner: UNT Libraries Government Documents Department
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The Physics of the Fused-Salt Reactor Experiment

Description: In 1954 the Oak Ridge Nationai Laboratory operated, for demonstration purposes, a high-temperature circulatingfuel reactor, employing as fuel enriched uranium fluoride dissolved in molten fluorides of other cations. A BeO moderator was used. At a maximum power of 2.5 Mw, 100 Mw hr were obtained. A negative temperature coefficient resulting largely from fuel expansion yielded exceptional stability of the reactor, and made the reactor a slave of the power demand. Xe/ sup 135/ and some of the other fission fragments are not retained in the fuel; hence, there is no xenon poisoning and relatively little danger of spreading of gaseous fission fragments in case of an accident. The advantages of liquid-fuel reactors (elimination of radiation dnmage and thermal stresses in solid fuel elements, ease of fabrication and fuel reprocessing) are combined with low pressures at very high temperatures. (auth)
Date: February 22, 1957
Creator: Ergen, W.K.
Partner: UNT Libraries Government Documents Department
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Preliminary Investigations for an Advanced Engineering Test Reactor

Description: Study carried out to determine a suitable reactor system or systems for the testing of water, gas, and liquid-metal cooled fuel assemblies.
Date: February 22, 1957
Creator: Elgert, O. J.; Leyse, C. F. & Ott, D. G.
Partner: UNT Libraries Government Documents Department
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100-K Area electrical power system load and voltage study for project CG-775. Revision

Description: The proposed increased water capacity for 100-K plants will increase the electrical load to be supplied. The load study showed that the capacity of the existing 13.8 kV system is adequate to carry the increased loads proposed for Project CG-775, while for the 5 kV system, an expanded power system is proposed. Likewise, the voltage regulation on the kV system bus will be excessive, and voltage regulators should be added.
Date: February 22, 1960
Creator: Thorson, W. R.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for January 1960

Description: Production of Pu nitrate, UO{sub 3}, and unfabricated Pu metal met schedules. Decontamination performance of Purex process continued below standard. The cerium-144 cask is being redesigned. A ``powered ferret``, for driving a scintillation counter through a conduit to monitor ground activity beneath waste storage tanks, is being designed.
Date: February 22, 1960
Partner: UNT Libraries Government Documents Department
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Development of High-Strength Corrosion-Resistant Zirconium Alloys

Description: Approximately 100 ternary and quaternary spongezirconium alloys were screened for structural and cladding applications in a natural-uranium-fueled heavy-watermolerated power reactor. The alloy additions studied included2 to 4 wt.% Sn, 0.5 to 2 wt.% Mo, and 1 to 3 wt.% Nb. The effect of 0.1 wt.% Fe and 0.05 wt.% Ni additions to the experimental alloys was evaluated. All compositions were are melted, rolled at 850 ction prod- C from a helium- atmosphere furnace, vacuum annealed 4 hr at 700 ction prod- C, and furnace cooled. Room- and elevated-temperature hardness measurements were used to estimate the tensile strengths of the alloys, while corrosion resistance was evaluated by 1000-hr exposures to static 300 ction prod- C water. (auth)
Date: February 22, 1960
Creator: De Mastry, J. A.; Shober, F. R. & Dickerson, R. F.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF HIGH-STRENGTH NIOBIUM ALLOYS FOR ELEVATED-TEMPERATURE APPLICATIONS

Description: A study to improve the elevated-temperature strength of niobium by solloving has resulted not only- in greatly improved strengths at 1200 and 1470 deg F but also in the development of improved fabrication techniques for these alloys. The most important step in the fabric:ition procedure of niobium and niobium-base allows is the initial breakdown of the cast structure. The cast structure of 1.84 wt. 4 chromium, 3.21 wt.% chromium. 4.33 wt. ' zirconium, and 20.5 wt.% titanium-4.28 wt. = chromium allovs and unalloyed niobium was broken known by- forging ingots (protected from oxidation by molybdenum ciins) at 2550 deg F and rolling at 800 deg F. After the initiai breakdown of the cast structure, the alloy-s were coid roiied to a total of 95 per cent reduction with no difficulty .A second fabrication technique was employed for a second set of alloys. Unalloyed niobium and 1.29 wt. % chromium, 2.74 wt. 3 zirconium, 4.5 wt.% molybdenum, and 10 wt. % titanium-3 wt.% chromium alloys were forged and rolled at 1000 deg F to break down the cast structure and then cold rolled to 0.030-in. sheet. the sheet obtained by this technique showed moderate edge cracking. Tensite tests on the coid-worked materiais at 1200 and 1470 deg F indicate that chromium and zirconium.ire both potent strengtheners of niobium: the 1.84 wt.% chromium alloy- hiid a 0.2 per cent offset yield strength of 107,000 psi at 1200 deg F and 69,000 psi at 1470 deg F, and the 4.33 wt. % zirconium alloy had a 0.2 per cent offset yield strength of 69,000 psi at 1470 deg F. Limited welding studies indicate that strong and reasonably ductlle welds can be produced both by arc and spot welding. (auth)
Date: February 22, 1960
Creator: De Mastry, J. A.; Shober, F. R. & Dickerson, R. F.
Partner: UNT Libraries Government Documents Department
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Expansion task force: Old reactors speed of control for no overbore cases

Description: The Criteria for Speed of Control must be met for all cases being considered in the Expansion Studies. These Criteria are dependent upon the ratio Volume of water/volume of uranium in the process channel, the reactor power level, and the rate at which the vertical rods are released and inserted into the reactor. For those cases wherein the graphite channel is overbored by 0.200 inch., the criteria can generally be met for the power levels under consideration since the ratio of Vw/Vu is maintained adequately small by the use of large diameter fuel elements. If the graphite is not overbored, high pressure drop across the fuel element section must be maintained in order to maintain small values of Vw/Vu, which results in a substantial increase in the front header pressure. A method is developed in this document which ties together and defines the hydraulic and physics characteristics of the fuel-process channel geometry necessary to satisfy the Speed of Control Criteria over a range of feasible operating conditions. This study assumes no graphite overboring and employs throughout a smooth bore zircaloy process tube having an inside diameter of 1.650 inches. The fuel elements are self-supported., and the inner hole size was selected to provide an optimum flow split for corrosion considerations.
Date: February 22, 1960
Creator: Gilbert, W. D.; Carlson, P. A. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Radial Temperature Profile of Sodium Pool Boiling Heater Assembly

Description: The radial temperature around a sodium reactor heater assembly submerged in water is calculated using a model of the heater cross section found by conformal mapping. Thermocouple readings were also analyzed. When the heat flux is 5 x 10/sup 5/ Btu/hr-ft/sup 2/, a radial temperature drop of about 680 deg C across the center of the thermocouple well is calculated and found to be within 6% of the experimental value. Since most of this drop is across the 0.001-in. helium gap between the heater and its sleeve, it is concluded that the thermocouple will have to be bonded to the sleeve for dependable reading of true sleeve temperature. Drawings of the heater assembly and thermocouple are given. (D. L. C.)
Date: February 22, 1960
Creator: Cappel, H. H.
Partner: UNT Libraries Government Documents Department
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PUREX PULSE COLUMN STUDIES-1960

Description: A series of pilot plant runs was conducted to define new cartridges for increasing the capacity in the Purex 1 Bx, 2A, lC and 2E columns and eliminate plastic cartridge failures in the HA column scrub section, the HS column and the 2A column. The most favorable designs are presented and data from the various runs are included. (J.R.D.)
Date: February 22, 1961
Creator: Jansen, G. & Richardson, G.L.
Partner: UNT Libraries Government Documents Department
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Insulated control drum bow tests

Description: No Description Available.
Date: February 22, 1966
Creator: Kallin, I. N.
Partner: UNT Libraries Government Documents Department
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