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Serial/Series Title
NACA Research Memorandums
493
NACA Technical Notes
273
Atomic Energy Commission Reports
170
Oak Ridge National Laboratory Reports
152
CF (Series)
138
United States Geological Survey Reports
79
Trace elements investigations report
67
University of California Radiation Laboratory Reports
60
NACA Technical Reports
30
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Determination of Trace Amounts of Sulfur in Fluoride Salts
A method has been developed for the determination of total sulfur in fluoride salts using the methylene blue procedure. Reduction of sulfate to hydrogen sulfide is achieved through the use of a new reducing mixture consisting of stannous chloride dissolved in concentrated phosphoric acid. The new mixture is effective on microgram amounts of sulfate and offers a major advantage over the red phosphorous reducing mixtures in that larger samples may be taken for analysis. The procedure has been applied to fluoride salts containing from 1 to 500 ppm of sulfur. The coefficient of variation the method is 10 percent.
Date:
June 24, 1957
Creator:
Gilbert, T. W. & White, J. C.
Object Type:
Report
System:
The UNT Digital Library
The Relationship of Aqueous ThO2 Slurry Physical Properties of the Engineering Design of a Reactor System
In a reactor system the principal components affect by slurry properties are the blanket vessel, pressurizer, heat exchanger, and dump tant. The particular properties that affect the operation of these components are: caking, degree of flocculation, foaming, and slime formation. these properties are related to the characteristics of compounds in a reactor system through experience gained in the operation of slurry loops. It is pointed out that the optimum slurry for one component may not necessarily be the optimum for another.
Date:
June 17, 1957
Creator:
Thomas, D. G.
Object Type:
Report
System:
The UNT Digital Library
In-Reactor Autoclave Corrosion Studies II : Autoclave Z-19
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 (VI) had no significant effect on the radiation corrosion of Zircaloy-2 by enriched uranyl sulfate solutions. However, the data are not conclusive and may be interpreted as showing a low corrosion rate for a limited period (i.e. a short term inhibition) followed by a correspondingly rapid corrosion.
Date:
March 22, 1957
Creator:
Warren, K. S.; Davis, R. J. & Jenks, G. H. (Glenn Herbert), 1916-
Object Type:
Report
System:
The UNT Digital Library
Hedstrom Plot for the Calculation of Laminar Flow Pressure Drop for the Bingham Plastic Materials with Hedstrom Numbers from 0 to 10(15)
The results of a machine calculation of a modified Fanning-friction-factor Hedstrom plot for Hedstrom numbers from 0 to 10(10) are presented in graphical and tabular form.
Date:
June 20, 1957
Creator:
Thomas, D. G.
Object Type:
Report
System:
The UNT Digital Library
Compilation of Various Undocumented Classified Memoranda on Sherwood Program
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 compilation.
Date:
June 28, 1957
Creator:
McNally, J. Rand (James Rand), 1917-
Object Type:
Report
System:
The UNT Digital Library
Testing of Adsorptive Capacity of Charcoal Beds : HRT Test No II-A 10 b
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 instrument air.
Date:
June 4, 1957
Creator:
Van Winkle, R. & Wiethaup, R.R.
Object Type:
Report
System:
The UNT Digital Library
Performance of HRT Charcoal Beds
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)
Object Type:
Report
System:
The UNT Digital Library
A Preliminary Study of Pre-Solvent Extraction Treatment of Stainless Steel-Uranium Fuels with Dilute Aqua Regia
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 variables affecting the dissolution process and to obtain dissolver scale-up data, and to investigate the removal of chloride from the dissolver product and the variables affecting the stripping operation. A continuous flooded pot dissolver was used. It has the advantages of stability of operation and ease of control in comparison with column dissolvers and requires a minimum of mechanical processing prior to dissolution. Stripping of the dissolver product to remove chloride ion was studied in a 4-in. diameter Pyrex bubble-cap column containing 12 single bubble cap plates. Continuous dissolution rates and dissolver product stainless steel loading were correlated with aqua regia feed composition, acid feed rate and surface area exposed to reaction. Profiles of chloride concentration down the stripping column were obtained …
Date:
October 11, 1957
Creator:
Kitts, F. G. & Perona, J. J.
Object Type:
Report
System:
The UNT Digital Library
Effect of Core Corrosion Sample Assembly on HRT Critical Concentration
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 as a function of temperature with the corrosion sample assembly in place. At 280°C, the assembly raises the critical concentration by 0.6 g U-235/kg D2O. This effect is equivalent to a uniformly distributed poison equal to 4.1% of the fission cross section. The equivalent poison is greater at lower temperatures, where the uranium concentration is lower.
Date:
July 18, 1957
Creator:
Haubenreich, Paul N.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Computations for HRE-3 Design : Equilibrium Results
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 is discussed. Tables of results, including neutron balances, are given for selected reactors. a number or relations are presented for estimating the effects of fission products, copper, corrosion products, H2O, and the core tank on breeding ratio.
Date:
July 10, 1957
Creator:
Rosenthal, M. W. & Fowler, T. B.
Object Type:
Report
System:
The UNT Digital Library
Radiation Level in the Stator Region of the HRT Fuel Circulation Pump
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 vicinity of the pump. It appears that the possibility of gas production in the stator from the cell background radiation is sufficiently great to warrant the installation of a shield around the outside of the motor end of the fuel circulating pump.
Date:
July 3, 1957
Creator:
Engel, J. R.
Object Type:
Report
System:
The UNT Digital Library