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In-Reactor Autoclave Corrosion Studies II : Autoclave Z-19

Description: In order to test the effect of chromate ion on the corrosion of Zircaloy-2 a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm Cr (VI) was autoclaved with rocking at 280 C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the a rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presence of Cr (… more
Date: March 22, 1957
Creator: Warren, K. S.; Davis, R. J. & Jenks, G. H. (Glenn Herbert), 1916-
Partner: UNT Libraries Government Documents Department
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Compilation of Various Undocumented Classified Memoranda on Sherwood Program

Description: This compilation includes the following subjects: (1) Spectroscopic studies, (2) Neutral carbon in the vacuum carbon arc, (3) Anode effects, doppler blast effects, and stark broadening, (4) Neutrals in the high-current carbon arc; (5) Photon breakup of N2 in the high-current carbon arc, (6) Ion density in the high current carbon arc, and (7) Recombination cross-section for fast hydrogen ions and slow electrons. Minor revisions have been made in the subject memoranda in incorporating them in the… more
Date: June 28, 1957
Creator: McNally, J. Rand (James Rand), 1917-
Partner: UNT Libraries Government Documents Department
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Testing of Adsorptive Capacity of Charcoal Beds : HRT Test No II-A 10 b

Description: During the pre-startup phase of the HRT operations, moisture was accidentally introduced into the charcoal bed adsorbers in the off-gas system. Tests have been made to determine the effect of wetting upon the adsorptive properties of the charcoal. The work was divided into two phases, testing of fresh charcoal in the laboratory and testing of the HRT charcoal beds in situ. It is recommended that the beds be dried by heating them to about 40 C and purging each with one to two liters/min of dry i… more
Date: June 4, 1957
Creator: Van Winkle, R. & Wiethaup, R.R.
Partner: UNT Libraries Government Documents Department
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Performance of HRT Charcoal Beds

Description: The expected performance of the HRT carbon beds was calculated for various reactor operating conditions. the calculations indicated that the flow rate of sweep gas will have to be limited to prevent excessive activity discharge. Data on activity discharge are included.
Date: June 4, 1957
Creator: Weeren, Herman O. & Lee, John (W. John)
Partner: UNT Libraries Government Documents Department
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A Preliminary Study of Pre-Solvent Extraction Treatment of Stainless Steel-Uranium Fuels with Dilute Aqua Regia

Description: The continuous dissolution of 304 stainless steel and stainless steel-UO2 alloy in dilute aqua regia was studied with subsequent stripping of the dissolver product to remove chloride ion. The process has the advantage of producing, by means of a simple head end treatment, a solvent extract feed in a conventional nitric acid medium so that existing solvent extraction processes, materials of construction and waste disposal methods can be used. The purposes of this study were to investigate the va… more
Date: October 11, 1957
Creator: Kitts, F. G. & Perona, J. J.
Partner: UNT Libraries Government Documents Department
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Effect of Core Corrosion Sample Assembly on HRT Critical Concentration

Description: An estimate has been made of the critical fuel concentration in the HRT, taking into account the effect of the core corrosion sample assembly. The estimate is based on a number of previous calculations of critical concentration in an un-poisoned reactor and one calculation of critical concentration as a function of poison level. The makeup of the first core corrosion sample assembly was used in calculating equivalent neutron poisoning effects. Figure 1 shows the estimated critical concentration… more
Date: July 18, 1957
Creator: Haubenreich, Paul N.
Partner: UNT Libraries Government Documents Department
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Nuclear Computations for HRE-3 Design : Equilibrium Results

Description: Various nuclear characteristics of two-region spherical homogeneous reactors have been computed in order to provide information for the design of HRE-3. Equilibrium isotope concentrations were established using an ORACLE code, and a two-group model was used to obtain critical concentrations and flux distributions. Breeding ratio is plotted as a function of reactor size, blanket thorium concentration, and other design and operating parameters, and the time required for a demonstration breeding i… more
Date: July 10, 1957
Creator: Rosenthal, M. W. & Fowler, T. B.
Partner: UNT Libraries Government Documents Department
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Radiation Level in the Stator Region of the HRT Fuel Circulation Pump

Description: The gamma dose rate in the motor region of the HRT fuel circulation pump was measured with the pump scroll full of radioactive solution. Extrapolation of the data to the solution activity expected in the pump under normal operation gives a dose rate well below that which would result in excessive gas production in the stator can within the life of the pump. The above dose rate does not include the effects of fast neutrons from the fuel solution or of the general cell radiation level in the vici… more
Date: July 3, 1957
Creator: Engel, J. R.
Partner: UNT Libraries Government Documents Department
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Use of Hood Cells for Enclosing Low Level Radiation Processes

Description: A perspective drawing of typical hood cells arranged in series for an assembly line operation is presented. Advantages of this improved enclosure for low level radiation work are listed which recommend its use on new facilities in preference to more conventional designs.
Date: February 28, 1957
Creator: Moulthrop, H. A.
Partner: UNT Libraries Government Documents Department
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Procedures for Measurement of Aluminum Corrosion

Description: If consistent results are to be obtained in a corrosion program, all samples must be handled in a uniform manner throughout the program. The following procedures have been set up as standard for the Corrosion and Coatings Operation and have been used for all the aluminum corrosion tests in the group.
Date: January 14, 1957
Creator: Bowen, H. C. & Thiede, R. A.
Partner: UNT Libraries Government Documents Department
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Radiation Damage to Graphite from 30°C - 185°C

Description: This study was undertaken to learn more about the behavior of graphite above 30°C with the hope that the results would contribute to the understanding of radiation damage and yield data of engineering value.
Date: June 10, 1957
Creator: Nightingale, R. E. & Fletcher, J. F.
Partner: UNT Libraries Government Documents Department
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Heat Transfer "Beyond Burnout" For Forced Convection Bulk Boiling

Description: Presented are the results of experiments with forced circulation annular flow heat transfer to boiling water at 1500 psis pressure in a horizontal electrically heated test assembly.
Date: January 21, 1957
Creator: McEwen, L. H.; Batch, J. M.; Foley, D. J. & Kreiter, M. R.
Partner: UNT Libraries Government Documents Department
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Recording Surface Condition By Replication

Description: Surface finish of plutonium pieces is of importance and is difficult to evaluate directly because of the handling limitations imposed by its toxicity and radioactivity. Efforts were therefore directed towards finding a surface examination method suitable for such applications. The Faxfilm replication scheme described in this report is the result.
Date: January 29, 1957
Creator: Morgan, J. R.
Partner: UNT Libraries Government Documents Department
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A Continuous River Sampling System and Methods of Radiochemical Analyses for Strontium-89, 90, Barium-140, and Phosphorus-32

Description: The discharge of reactor cooling water to the Columbia River introduces an amount of radioactive material to the river. It was of interest to study the downstream dilution of specific isotopes and establish accurate concentration measurements for calculation of the radiological hazard and mass balance.
Date: January 14, 1957
Creator: Silker, W. B.
Partner: UNT Libraries Government Documents Department
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Pressure Drop and Critical Flow for Steam-Water Mixtures

Description: A program of experiments is proposed to provide the experimental data needed for the improved empirical pressure drop correlation and to more clearly ascertain the nature of the critical flow process of steam-water mixtures.
Date: January 5, 1957
Creator: Firey, J. C. & Moulton, R. W.
Partner: UNT Libraries Government Documents Department
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