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20,000 KW Nuclear Power Plant Study for United States Atomic Energy Commission

Description: Introduction: In September of 156, Gilbert Associates, Inc., entered into a contract with the United States of America, acting through the United States Atomic Energy Commission, for the study and preliminary design of a nuclear power plant being considered for integration into a central station power system at an overseas site.
Date: July 7, 1957
Creator: Gilbert Associates, Inc.
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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 within the immediate future, and economic operation not the cortrolling factor. Reasonably complete studies are presented for the reactor physics, safety, stability, chemistry, hent transfer, and operation of the system. (auth)
Date: August 1, 1957
Creator: Chapman, R.H.; Collins, H.L.; Dollard, W.J.; Fieno, D.; Hernandez- Fragoso, J.; Miller, J.W. et al.
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100-B Area flow analysis

Description: Results of experimental programs indicate that it might be desirable in the future to modify the existing reactors by replacing the aluminum process tubes with tubes made of a zirconium alloy. The zirconium tubes would be more corrosion resistant than the aluminum ones and would also be stronger at higher temperatures. These new tubes would have the same outer diameter as the present tubes (for ease of handling and in order to provide adequate graphite cooling) but would have a thinner wall (since zirconium alloy is both stronger and more expensive than aluminum). The inner diameter of the new tubes would, therefore, be greater than in the present tubes. In addition to the tube change, it might also be desirable to replace the existing solid fuel elements with those known as ``I&E`` alements. These pieces would be similar to the present elements except for a longitudinal hole which would allow the passage of cooling vater through the center. The element would then be Internally and Externally cooled, and would have a more uniform temperature distribution. The combination of the larger tube inside diameter and the central hole in the fuel element would result in reduced friction loss for the reactor cooling water with a resulting increase in flaw. The 100-B process water system was chosen arbitrarily for analysis and this analysis vas undertaken to determine if the process water system would be capable of providing the additional flow required by the modification.
Date: June 1, 1957
Creator: Bainard, W. D.
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183 B-C cross tie justification and scope

Description: After the present solid slugs are replaced with the new I&E elements` in the 105-B reactor, the friction loss for the reactor cooling water will be decreased with a resulting opportunity for increase in flow through the reactor. The amount that this flow could be increased is limited by the capacity of the B water plant as well as the reactor itself. It is possible that there will be a shortage of filtered water at 183-B during the critical periods of each year. To overcome this possible shortage of water it has been proposed to construct a thirty inch tie line from the 183-C reservoir to the 183-B clear-well to supply filtered water to 183-B by gravity flow from 183-C. This report presents justification and the scope of this project.
Date: December 2, 1957
Creator: Brinkman, L. B.
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Abnormal grain growth in M-252 and S-816 alloys

Description: Report discussing an experimental investigation was carried out on air- and vacuum-melted M-252 and S-816 alloys to find conditions of heating and hot-working which resulted in abnormal grain growth. The experiments were mainly limited to normal conditions of heating for hot-working and heat treatment and normal temperatures of solution treatment were used to allow grain growth after susceptibility to abnormal grain growth was developed by various experimental conditions. Results indicated that small reductions of essentially strain-free metal were the basic cause of such grain growth.
Date: November 1957
Creator: Decker, R. F.; Rush, A. I.; Dano, A. G. & Freeman, J. W.
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Abnormal grain growth in nickel-base heat-resistant alloys

Description: From Introduction: "The data included in this report for Nimonic 80A alloy, for instance, represent experiments carried out to help clarify a production problem of grain-size control in an alloy which has been extensively used. The general procedure of the investigation was to carry out controlled laboratory experiments on samples of bar stock to find conditions of heating and hot-working which resulted in abnormal grain growth."
Date: December 1957
Creator: Decker, R. F.; Rush, A. I.; Dano, A. G. & Freeman, J. W.
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Accelerations in fighter-airplane crashes

Description: From Introduction: "This report describes some measurements of these quantities obtained by crashing fighter aircraft under circumstances approximating those observed in service."
Date: November 4, 1957
Creator: Acker, Loren W.; Black, Dugald O. & Moser, Jacob C.
open access

Accident in Continuous-Dissolver Pilot Plant of Fluoride Volatility Project on May 15, 1957

Description: A series of explosions, estimated at five, occurred over a period of ten seconds within the continuous dissolver pilot plant, of the Fluoride Volatility Project on May 15, 1957. The explosive reactions occurred in the dissolver vessels as a result of violent chemical reactions between uranium and an interhalogen mixture. Just what the conditions were which triggered the explosions, have not been definitely established. Nevertheless, based upon the evidence which has been collected, several possible explanations, listed according to probability, are presented. A number of recommendations are included to be followed before operation of the pilot plant is resumed. These recommendations relate to additional laboratory research, equipment design, facility design, and use of a review committee. Safety rules for handling BrF/ sub 3/, BrF/sub 5/, ClF/sub 3/, and Br/sub 2/ are appended. (C.H.)
Date: July 10, 1957
Creator: Strickland, G.; Horn, F. L.; Johnson, R. & Dwyer, O. E.
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Accidents from explosives at metal and nonmetallic mines

Description: Circular produced by the U.S. Bureau of Mines to promote safety through a series of reports on accident prevention in mines. According the the scope statement, "This is the fourth section of the revised series of circulars that cover various phases of accident prevention in metal and nonmetallic mines; it give information on accidents and injuries from storing, handling, and using explosive in metal and nonmetallic mines and discusses the precautions by which they can be prevented" (p. 2).
Date: 1957
Creator: Cash, Frank E.
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Action and Emission Spectra of the Luminescence of Green PlantMaterials

Description: The action and emission spectra of the delayed light emission from Chlorella, Nostoc, and spinach chloroplasts have been measured. The action spectra for Chlorella and for spinach chloroplasts are quite similar to the absorption spectra of these materials. The action spectrum for Nostoc, on the other hand, shows a relatively low activity for chlorophyll and carotenoids and a high activity for phycocyanin. The emission spectra of these materials demonstrates that the luminescence is the result of a transition between the first excited singlet state and the ground state of chlorophyll. Low-temperature studies suggest that the triplet state of chlorophyll is not involved at all in the luminescence of spinach chloroplasts. There is some indication that part of the light emitted from Nostoc is due to a phycocyanin transition.
Date: December 29, 1957
Creator: Tollin, G.; Fujimori, E. & Calvin, Melvin
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Description: The activation cross section of sodium in the range from thermal energy through the 3-kev resonance is generally assumed to be given by the one-level BreitWigner formula, the GAMMA /sub gamma / being selected to describe correctly the known thermal absorption cross section. The contribution of this resonance to the resonance activation integral then turns out to be 0.12 barns. This somewhat indirectly inferred value is considerably larger than the value given by Dancoff et al., in an old paper, the latter value being based on experimental work. It is shown in the present memo, that Dancoff's actual measurements are quite consistent with the Breit-Wigner formula and the above mentioned GAMMA /sub gamma /. The discrepancy is a result of Dancoff's transition from the actual measurements to the resonance integral, this transition being based on data that is now obsolete. (auth)
Date: February 1, 1957
Creator: Ergen, W.K.
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Additional Experiments With Flat-Top Wing- Body Combinations at High Supersonic Speeds

Description: Memorandum presenting an experimental study of the effects of several variations in configuration geometry on the aerodynamic characteristics of flat-top wing-body combinations. Generally, the configurations consist of one half of a body of revolution mounted beneath a wing of essentially arrow plan form. Results regarding the effect of trailing-edge sweep, effect of the addition of auxiliary bodies, effect of tip-flap deflection, effect of dihedral, effect of leading-edge sweep, effect of fuselage fineness ratio, effect of fuselage profile shape, and static longitudinal stability characteristics are provided.
Date: February 19, 1957
Creator: Syvertson, Clarence A.; Wong, Thomas J. & Gloria, Hermilo R.
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Additional facilities to handle PUREX tank farm vapor wastes. Project CG-719

Description: The liquid high-level radioactive wastes from the separations plant are stored in large underground tanks where radioactive decay of the fission products in storage gives off heat. In the case of the 241-A underground storage tank farm, for Purex wastes, advantage is taken of this heat to self-concentrate the wastes. The present practice is to permit boiling and concentration in the storage tanks. The vapors given off from the boiling wastes are collected in a vapor header and passed through a deentrainment vessel and on to two contact condensers where the vapors are condensed and intermixed with waste cooling water. Samples taken of the waste vapors have shown a considerable amount of cesium{sup 137} present as well as other types of radioactive material carry over from the waste tanks. For this reason the contact condenser effluent is discharged to an underground crib 216-A-8. Underground disposal of the increasing volume of condenser effluent as larger waste volumes are accumulated in the underground tanks presents a critical problem which is further complicated by the desirability to transfer the condensate waste to new disposal facilities near the 200 West area. The intent of this report is to present the scope of the facilities required to reduce the volume of potentially radioactive condensate waste from the 241-A tank farm and to dispose of this waste through supplemental cribbing. An analysis of the 216-A-8 crib capabilities in relation to the projected flows clearly indicates that if other facilities to reduce the contaminated waste stream volume are not provided, an extensive and costly crib system will be required. The economical solution to the problem is to provide surface condensers to permit segregation of the condensed waste vapors from the cooling water, condensate collection and transfer facilities, and a new condensate disposal crib near the 200 West …
Date: January 7, 1957
Creator: Wood, V. W.
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Additional Measurements on the Army Package Power Reactor Zero Power Experiments: ZPE-1 and ZPE-2

Description: During the course of the ZPE-2 experimental program additional measurements were performed under the Alco Products Research and Development program. Included in this program were the evaluation of various absorber section compositions and reactivity studies designed to facilitate analytical techniques. The results of these measurements are presented. (auth)
Date: November 15, 1957
Creator: Giesler, H. W.
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Adsorption of Zirconium-Niobium on Silica Gel

Description: From abstract: "Adsorption of radioactive zirconium-niobium from uranyl nitrate solutions by silica gel was increased by increasing the temperature and time the solution contacts silica gel, and decreased by "aging" the solutions before contacting the silica gel."
Date: July 1957
Creator: Karraker, David G. & Parker, Sidney G.
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Aerodynamic and hydrodynamic characteristics of a proposed supersonic multijet water-based hydro-ski aircraft with a variable-incidence wing

Description: From Introduction: "The configuration described in this paper represents one approach to such an airplane and the results of the wind-tunnel and tank evaluations are presented. In the present investigation, the aerodynamic longitudinal characteristics over a Mach number range from 0.6 to 1.97 were obtained."
Date: October 23, 1957
Creator: Petynia, William W.; Hasson, Dennis F. & Spooner, Stanley H.
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Aerodynamic characteristics at Mach number of 4.06 of a typical supersonic airplane model using body and vertical-tail wedges to improve directional stability

Description: Report presenting an investigation at Mach number 4.06 on a typical supersonic airplane model with a 40 degree sweptback wing. The purpose of the investigation was to determine the effectiveness of using wedges on the body and on the vertical tail to increase the static directional stability. Results regarding the longitudinal characteristics and lateral characteristics are provided.
Date: December 3, 1957
Creator: Dunning, Robert W.
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