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Pressure Vessel Exposure to Fast Neutrons

Description: In a gas-cooled reactor operating at very high power density the thickness of the reflector may be determine by the requirement that the steel pressure vessel be protected from an excessive dose of fast neutrons, rather than by the usual requirements of neutron economy and power distribution. It is important the the reflector not be made thicker than necessary, since an increase in pressure vessel diameter can result in a marked increase in cost, as well as a decrease in the permitted gas pres… more
Date: January 21, 1960
Creator: Carlsmith, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Xenon and Samarium Poisoning

Description: The equilibrium and maximum override values for xenon and samarium poisoning have been computed using the recently issued effective cross sections of C. H. Westcott. Values are given as a function of specific power, neutron temperature, and epithermal flux content.
Date: January 23, 1961
Creator: Carlsmith, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sources and Availability of Helium

Description: A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
Date: January 19, 1961
Creator: Fraas, A. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Revised Version of HFIR Critical Experiment-2 (HFCE-2)

Description: A listing and description is given of the experiments associated with the HFIR Critical Experiment-2. The primary experiments concern the reactivity of the bare core, reactivity worth of "gray" control plates, core-power distribution, reactivity. The secondary experiments concern the reactivity of the fuel, and the reactivity worth of a "partial" gray plate.
Date: January 16, 1961
Creator: Kasten, P. R. & Cheverton, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bremsstrahlung Absorption Measurements from Sr^90 TiO3

Description: The absorption in lead of Bremsstrahlung X radiation from a Sr^90 TiO3 pellet in the proximity of Hastelloy "C" was measured. The tenth value layer of the more energetic components of the X-ray continuum was determined to be 1.60 inches.
Date: January 13, 1961
Creator: Butler, T. A. & Pierce, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960

Description: A carrier containing 138.99 liters of solution, uranium concentration 202.04 g/liter with an isotopic concentration of 97.3% U-233, was prepared for shipment. The total uranium was 28,062 +/- 60 g (95% confidence level) and the U-233, 27,305 +/- 66 g (95% confidence level).
Date: January 11, 1961
Creator: Sadowski, G. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop

Description: Simulated reactor fuel solutions were circulated at temperatures as high as 365°C in a small titanium pump loop. A hydroclone separator separated heavy phases formed at high temperatures. As the temperature of the solution was increased beyond the two-liquid-phase temperature (327°C), the salt concentration of the light phase decreased and the acid concentration increased. The mole ratios of uranium to sulfate, uranium to copper, and uranium to nickel in the light phase decreased in the same pr… more
Date: January 6, 1961
Creator: Griess, J. C.; Baker, J. M. & Savage, H. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ORR Startup Accident and Cooling Flow Coastdown Analog Analysis

Description: Startup accident and pump run-down on the ORR have been simulated on the Reactor Controls Analog Facility. At full flow the 150% level scram (45 Mv) easily terminates the startup accident before the metal temperature gets above 180°F. For very low flows typical of criticality runs, temperature coefficients turn the excursion before it reaches 150% of full power, and temperatures climb to boiling, a potentially hazardous condition. (This same behavior can occur at full flow is the power is incr… more
Date: January 4, 1961
Creator: Stone, R. S. & Colomb, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Release Incident at Oak Ridge National Laboratory

Description: A nonnuclear explosion involving an evaporator occurred in a shielded cell in the Radiochemical Processing Pilot plant at Oak Ridge National Laboratory. Plutonium released from the processing cell contaminated areas in the pilot plant building and nearby streets and building surfaces. The explosion is considered the result of rapid reaction of nitrated organic compounds formed by the inadvertent nitration of about 14 liters of a proprietary decontaminating reagent.
Date: January 10, 1961
Creator: King, L. J. & Bresee. J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report September 1960

Description: Measurements of the interfacial tension between water and tributyl phosphate solutions were made for application to the analysis of Marengoni effect in solvent extraction. A 24 hr flame calcination run to product Th02 particles yielded 40% as product and 54% collected from the furnace walls and from a coarse particle trap. The elution rates of uranyl ion from Dowex 21K using sodium nitrate could be approximated by assuming apparent diffusion coefficients of 1.67 x 10^-7 and 1.18 x 10 ^-7 cm^2/s… more
Date: January 27, 1961
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cross Section Program at ORNL

Description: Short reports to the members of the Nuclear Cross Section Advisory Group from three groups: (1) High voltage group; (2) Fast chopper time-of flight spectrometer; and (3) Electronuclear research division.
Date: January 21, 1957
Creator: Harvey, J. A. & Fowler, J. L. (Joseph L.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cracks in HRT Flange Bolts and Ferrules

Description: When it was discovered that two HRT flange bolts of a lot of 16 spares contained serious cracks, a program was launched to (1) determine the cause for the cracking, and (2) find methods for non-destructive testing the remainder of the 672 bolts shipment, a large portion of which had been installed in the HRT. Concurrently, inspection of 8 ferrules removed from an HRT flange revealed hairline cracking in 4 of them. Magnaglo, a magnetic particle inspection method using a fluorescent dye, proved t… more
Date: January 29, 1957
Creator: Hammond, J. P.; Adamson, G. M. & Kegler, T. M., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Estimated Gamma Radiation Levels at Access Holes in the HRT Shielding

Description: An estimate has been made of the gamma radiation levels at access holes in the HRT Shielding when the plugs have been removed to service or maintain the reactor. In every case the radiation level at the holes was greater than the maximum permissible exposure rate of 0.3 roentgens per week. The radiation through the holes can be attenuated to some extent by flooding the reactor cell up to the flange to be disconnected. However, shielding would still be required and it is more practical to provid… more
Date: January 24, 1957
Creator: Collins, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Corrosion Group for the Period Ending January 31, 1957

Description: A second test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel has been completed. The joint and bellows have now received 104 thermal cycles and 148 mechanical deflections. The joint and bellows have functioned properly; corrosion damage has been negligible, except for a small area on the bellows which has undergone pitting attack. Long-term runs with uranyl sulfate solutions of the concentration proposed or use in the HRT have shown the soluti… more
Date: January 31, 1957
Creator: Griess, J. C. F.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thorex Pilot Plant ; System for Concentrating Second Uranium Cycle Product

Description: A system for concentrating uranyl nitrate solutions was designed and installed in the Thorex Pilot Plant. A total of 16,060 g of uranium was concentrated in the system in 68 batch runs. A total of 14,400 g total uranium (14.180 g U/sup 233/) was recovered as product suitable for shipment. Uranium loss to the evaporator condensate was 0.03% of the total uranium processed. The material balance across the system was 98.4%. The average concentration of uranium in the evaporator feed solution was 29… more
Date: January 28, 1957
Creator: Albrecht, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRT Temperature Measurement System - Issue No. 3

Description: The following temperature measurement tabulation consists of two parts. Part I lists all HRT thermocouples, their location, the junction box thru which the leads pass, and their termination, if on an instrument. Part II lists all temperature read out instruments and their location. A total of 577 thermocouples are listed in this tabulation. The roughly 77,000 ft of wire used in connecting them up cost $6,799. Temperatures are read on 24 instruments. Cost of these was approximately $15,688. Acce… more
Date: January 17, 1957
Creator: Grimes, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stress-Corrosion Cracking Problems in the Homogeneous Reactor Test

Description: Chloride-induced stress-corrosion cracking has been encountered in the Homogeneous Reactor Test during the preliminary testing. The rector is constructed of austenitic stainless steels. It is unique in that it will operate at 250 to 300 C with an aqueous uranyl sulfate solution fuel containing 200 to 500 ppm of dissolved oxygen. The cracking has occurred in a secondary system used for detecting leaks in the flanged joints of the primary systems and in the grooves of flanges in the primary syste… more
Date: January 31, 1957
Creator: Bohlmann, E. G. & Adamson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes

Description: The method is based on caustic precipitation and centrifugation (which removes the Cs and small amounts of Sr, rare earths, Zr, Nb, and Ru). These are removed in the supernatant and run through a cation exchange column. This separates Zr-NB and Ru. The effluent is precipitated and the Zr-Nb is stored in an asphalt pit. The Ru then may be recovered from the precipitate. The precipitate from the original centrifugation is calcined, pressed and transported to a deep well.
Date: January 17, 1957
Creator: Higgins, I. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Chemical Processing of Two-Region Aqueous Homogenous Reactors

Description: A promising scheme for the chemical processing of a thorium breeder reactor of the two-region aqueous homogeneous type consists of the following operations: concentration of insoluble fission and corrosion products from the core system into a small volume of fuel solution, combining this slurry with irradiated thorium oxide slurry taken from the blanket, recovery of D2O by evaporation, dissolution of the thorium and uranium in HNO3, and, after a suitable cooling period, recovery of the uranium … more
Date: January 29, 1957
Creator: Ferguson, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Irradiation of Thorium and Uranium Oxides Slurries

Description: Thorium and thorium-uranium oxide slurries were irradiation in the Low Intensity Test Reactor (LITR) at temperatures up to 300C in small stirred autoclaves. Stirring was accomplished by means of an electromagnetically operated lunger. Stirrer operations was monitored suing an oscilloscope. Relative slurry viscosities were determined both in and out-of-pile using calibration curves of apparent viscosity versus stirrer rise time. Post-irradiation examination of selected slurries indicated no gros… more
Date: January 29, 1957
Creator: Krohn, N. A. & McBride, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium Recovery for Spent Fuel by Dissolution in Fused Salt and Fluorination

Description: A promising nonaqueous process for the recovery of uranium from spent fuel elements is under development at Oak Ridge National Laboratory. This process consists of dissolution of the fuel element in a fluoride melt by hydrofluorination at 600 to 700°C, direct fluorination with fluorine for the production and volatilization of UF6, with further decontamination of the product UF6 from fission product activity being secured in a NaF absorption-desorption step. Good decontamination is obtained in t… more
Date: January 29, 1957
Creator: Cathers, G. I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Submicron Particle Sized by an Activation Analysis - Centrifugation Method

Description: The feasibility of determining particle sizes in the submicron range by employing an activation analysis - centrifugation method has been demonstrated. It is believed that this method is now applicable to the analysis of thorium oxide for submicron particles. The same techniques are, in most instance, usable in determining particle sized in other sample materials.
Date: January 29, 1957
Creator: Bate, L. C. & Leddicotte, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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