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Adsorption of Radioactive Gases on Activated Carbon

Description: The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.
Date: August 31, 1960
Creator: Madey, Richard; Barker, J. J.; Beebe, M. R. & Stephenson, T. E.
Partner: UNT Libraries Government Documents Department
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Coolant backup design study basis and objective

Description: Preliminary studies have, in general, indicated the need for modifications and improvements to the reactor last ditch coolants systems in order to provide adequate safety of operation at power levels programmed for the future. These studies have indicated the need for improved reliability as well as increased capacity for the last ditch coolant systems. A design study is being prepared by Reactor Modification Design to define the scope of the modifications required to provide adequate last ditc… more
Date: August 31, 1960
Creator: Schack, M. H. & Tupper, W. J.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-344-A-FP, determination of the limitations of the Al-Si process

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can bond separation following irradiation. Such evidence h… more
Date: August 31, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Pebble Bed Friction Factor and Thermal Expansion Tests

Description: Tests were conducted to determine the friction factor of randomly packed beds of 3/4-inch diameter spheres in 8-inch and 15-1/4-inch diameter beds, and of 1-1/2-inch diameter spheres in 15-1/4-inch diameter bed. The bed depths were varied in an attempt to isolate the effects of entrance and exit losses. The bed Reynolds number, base on sphere diameter, was varied from 5,000 to 50,000.
Date: August 31, 1960
Creator: Leeman, C. A.
Partner: UNT Libraries Government Documents Department
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BEFCYF And DBDT: IBM 704 Codes For Preparing Input For Bevatron Orbit Code (BOC)

Description: Two IBM-704 codes have been written which are auxiliary to the Bevatron orbit code BOC. The first, BEFCYF, interpolates among tabulated values of the median-plane magnetic flux density of the Bevatron to produce an equivalent array of values in a form appropriate to BOC. The second, DBDT, produces azimuthal derivatives of the fields produced by BEFCYF. The internal operation of BEFCYF and DBDT is described, and instructions for their execution are given.
Date: August 30, 1960
Creator: Gardner, C. Gerald
Partner: UNT Libraries Government Documents Department
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Visible Spectra of Some Metal Tris-Acetlacetonates

Description: "The visible absorption spectra of VA3, CrA3, MnA3, FeA3 and CoA3 (A=C5H7O2, the acetylacetonate anion) are reported. The interpretation of the data in respect to the symmetry and strength of the ligand fields is discussed, with special attention to the presence and magnitudes of trigonal components in ligand fields and its consistency with certain results of paramagnetic trigonal fields of appreciable magnitude are present."
Date: August 30, 1960
Creator: Cotton, F. Albert (Frank Albert), 1930-2007 & Holm, Richard Hadley, 1934-
Partner: UNT Libraries Government Documents Department
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SPACE HANDBOOK TURBINES

Description: Turbine specific weight vs. power plant output was investigated for rubidium, potassium, and sodium at several inlet temperatures to obtain order of magnitude performance and weight of possible nuclear power plant systems. (W.L.H.)
Date: August 29, 1960
Creator: Grimaldi, J.
Partner: UNT Libraries Government Documents Department
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Dissolution of Power Reactor Fuel Cores

Description: Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
Date: August 26, 1960
Creator: Blaine, H. T.
Partner: UNT Libraries Government Documents Department
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Production test PT-IP-355-I K reactor backup water supply test

Description: The objective of this test is to measure the emergency reactor flow through the high pressure crosstie line (HPCT) after the removal of the flow limiting orifices in the HPCT. The flow limiting orifices in the HPCT were removed on July 5, 1960, as per Design Change No. 383. The removal of the flow limiting orifice allowed increased emergency flow and brought the crosstie coolant flow more nearly into conformance with the coolant supply reliability criteria. The purpose of this test is to measur… more
Date: August 25, 1960
Creator: Smit, W. R. & Jones, S. S.
Partner: UNT Libraries Government Documents Department
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Proposal for charging the fifth rupture fuel experiment: GEH-10, 34, 35

Description: The objective of this irradiation is to further verify the corrosion rate of tubular-type fuel elements under conditions of high specific power and central core temperatures. This fuel will be the inner tube only of an NPR fuel assembly. As in previous tests, this inner tube rupture will be used to further substantiate the rupture detection instrumentation that is being used in the development of the NPR. Previously unirradiated fuel will be used in this test. The reactor is to operate at full … more
Date: August 25, 1960
Creator: Call, R. L. & Kaulitz, D. C.
Partner: UNT Libraries Government Documents Department
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Pulsed Neutron Measurement of Control Rod Worth

Description: Reactivity measurements made by the pulsed neutron technique were compared with results obtained by conventional techniques. The pulsed neutron results were in good agreement with those obtained by stable period measurement and rod drop. Differential effectiveness of partially inserted rods was shown to be well represented by elementary perturbation theory. Finally, the pulsed neutron technique was found to be the only good method for measurement of large reactivity changes.
Date: August 25, 1960
Creator: Kolar, O. C. & Kloverstrom, F. A.
Partner: UNT Libraries Government Documents Department
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Experimental Gas Cooled Reactor-Creep Test, Agot Graphite

Description: Tests were conducted to determine the cumulative and permanent deflection of a beam subjected to two-point loading for (1) ambient temperature- atmospheric environment, and (2) 800 deg F-atmospheric environment, for 8OO psi maximum flexural stresses. Deflection curves are given for five specimens. An analysis of the data indicated that if the core graphite creeps while at EGCR conditions by approximately 1.5 times its creep rate at ambient temperature, the stresses will level off below 1000 psi… more
Date: August 23, 1960
Creator: Lain, P. J.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for July 1960

Description: Production of Pu nitrate from separations plant during this month was below forecast. UO{sub 3} production, shipments met schedules; so did unfabricated Pu shipments. Purex plant was stopped to replace the final waste concentrator (F-11) (leak). Two Pu-U partition failures were attributed to foreign organic material in the nitric acid; the Pu product was kept within specifications by adding NaF and ANN to ion exchange feed stream. A Np recovery run was started in Redox, and dissolution was star… more
Date: August 22, 1960
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Reactor Project Quarterly Progress Report: June 1960

Description: Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. Design Investigations: The effects on the power distribuestablished. A mathematical model was developed for studying shifting of the coolant stream as it moves along a rod in order to predict the temperatures of the parallel streams as they progress through the reactor. A fuelelement life code developed for computing the internal temperature structure, the amount of fission g… more
Date: August 22, 1960
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Magnetic Core Tests for Pulsed Operation at 30 Nanoseconds Pulse Width

Description: The magnetic properties of core materials ae investigated for a pulse width of 30 nanoseconds. Methods of testing which are necessitated by the sort pulse width are explained and the design of the pulser which is capable of 0.2 megawatt peak power is described. The data obtained if evaluated and presented for the various materials which were tested.
Date: August 22, 1960
Creator: Reeser, Gilbert A.
Partner: UNT Libraries Government Documents Department
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STUDIES OF THE USE OF COAGULANT AIDS IN THE LIME-SODA TREATMENT OF LARGE- VOLUME, LOW-LEVEL RADIOACTIVE LIQUID WASTE

Description: Studies on the use of coagulant aids in the lime-soda treatment of large- volume, low-level radioactive liquid waste revealed that a combination of Hagan Aids No. 50 and No. 18 gave fairly good results under most conditions. The effects of feed solution concentrations, mode and point of addition, and water temperature were studied. (C.J.G.)
Date: August 22, 1960
Creator: Subbaratnam, T; Cowser, K E & Struxness, E G
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part I. Summary of Technical and Economic Status as of 1960. Heavy Water-Moderated Power Reactors

Description: A revision of section 8 of TID-8516, Part I, is presented. The reactor concept which is presented is a change from the former design, a pressurized- pressure vessel-indirect cycle plant to a boiling-pressure tubedirect cycle plant. A description of the plant and a summary of characteristics for the 110- and 325- Mwe systems are given. (J.R.D.)
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part II. Economic Potential and Development Program. Heavy Water-Moderated Power Reactor

Description: The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel de… more
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part III. Status Report on Large (100 and 300 MWe) Heavy Water-Moderated Power Reactors--as of 1960

Description: An evaluation of 300- and 100-Mwe power plants was conducted using ground rules prescribed by the USAEC for this study. Costs corresponding to two average discharged fuel burnups are: 8.6 mills/kwh (8500 Mwd/ metric ton) and 8.8 mills/kwh (7500 Mwd/metric ton) for the 300-Mw plant. Costs for the 100 Mw plant are 14.7 mills/kwh for an average discharged fuel burnup of 6010 Mwd/metric ton. Estimates of future potential indicate that the 300 Mw/sub 3/ (8500 Mwd/metric ton) plant could produce powe… more
Date: August 19, 1960
Creator: Hutton, J. H.; Davis, S. A.; Graves, C. C. & Duffy, J. G.
Partner: UNT Libraries Government Documents Department
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A POTENTIOMETRIC STUDY OF ZIRCONIUM-NITRATE AND ZIRCONIUM-FLUORIDE SYSTEMS

Description: The potentiometric behavior of zirconium in fluoride, nitrate, and fluoride-nitrate systems is correlated and discussed in terms of the zirconium species present. A potentiometric titration was used successfully for the determination of total nitrate and zirconium in aqueous or organic (tributyl phosphate) zirconium-nitrate systems. (auth)
Date: August 18, 1960
Creator: Moffat, A. J.
Partner: UNT Libraries Government Documents Department
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Summary of Available Data on the Strontium 90 Content of Foods and of Total Diets in the United States

Description: From Present Programs: "There has been a gradual expansion of the Sr^90 food analysis program to include vegetable foods and finally entire diets. In some cases the analyses have also been extended to other nuclides but these data are so limited that they will not be emphasized in this report. It is expected that considerable data on Ra^226 and other naturally occurring radionuclides will be generated in coming year."
Date: August 18, 1960
Creator: Harley, John H. & Rivera, Joseph
Partner: UNT Libraries Government Documents Department
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