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Examination of 6" Diameter "O" Ring from HRT Mockup. Metallography Report (Y-12) No. 39
A six-inch diameter "O" ring from the HRT Mockup was examined metallographically after 2452 hours exposure to uranyl sulfate solution at 300C. surface defects, except for cold work defects were found only in areas exposed to uranyl sulfates. Defects found were pits, transgranular cracks, surface cracks, and grain attacks.
Date:
January 15, 1957
Creator:
Kegley, T. M., Jr.
System:
The UNT Digital Library
Interim Report of APPR Irradiation Test Program at MTR
It is the purpose of this memo to clarify and revise burnup calculations for the APPR irradiation program and to present a proposed irradiation schedule. the report will also be in the nature of a review of the program.
Date:
January 21, 1957
Creator:
Gross, E. E. & Schaffer, L. D.
System:
The UNT Digital Library
HRT Sampler Development
A prototype sampler for obtaining samples of high radioactive UO2SO4 solution for use in the HRT is presented. It was successfully operated in conjunction with a low pressure water system and a high pressure, high temperature UO2SO4 system.
Date:
January 22, 1957
Creator:
Hannaford, B. A.
System:
The UNT Digital Library
Texas Inmate Monthly Report: December 2022
Monthly report issued by the Texas Department of Criminal Justice providing statistical information about numbers and categories of inmates held in various locations across Texas.
Date:
January 2023
Creator:
Texas. Department of Criminal Justice.
System:
The Portal to Texas History
Texas Inmate Monthly Report: [December 2021], Part 2
Monthly report issued by the Texas Department of Criminal Justice providing statistical information about numbers and categories of inmates held in various locations across Texas.
Date:
January 4, 2022
Creator:
Texas. Department of Criminal Justice.
System:
The Portal to Texas History
Texas Inmate Monthly Report: [December 2021], Part 4
Monthly report issued by the Texas Department of Criminal Justice providing statistical information about numbers and categories of inmates held in various locations across Texas.
Date:
January 4, 2022
Creator:
Texas. Department of Criminal Justice.
System:
The Portal to Texas History
Operation of In-Pile Loop L-4-12
Loop L-4-12 was the seventh corrosion test loop operated in HB-4 beam hole at the LITR. The loop was inserted on January 24, 1956, and removed on April 17, 1956. This loop had a titanium core which was attached to the 347 stainless steel loop with special titanium to stainless steel couplings.
Date:
January 7, 1957
Creator:
Walter, F. J.
System:
The UNT Digital Library
Secondary Refrigerant for HRT Refrigeration System
The criteria for selection of an HRT secondary refrigerant system refrigerant to replace Freon-11 are given. The properties of Amsco which make it desirable are tabulated and it is compared with triethyl phosphate (the second choice) and Freon-11.
Date:
January 24, 1957
Creator:
Robertson, R. C. & McLain, Howard A.
System:
The UNT Digital Library
Test of Stainless Steel Freeze Jacket to be Used on 1/2-inch High Pressure and High Temperature Process Lines
In order to test the operation of a freeze jacket in air with the process fluid closely following the conditions found in the high pressure circulation loop of a homogeneous reactor, or, 2000 psi and 300C, a test loop was built and used in conjunction with existing refrigeration equipment. The freeze jacket was made of 5/16-in. type 346 stainless steel tubing wrapped around and welded to a 1/2-in. stainless steel process line. It was concluded that for these reactor operating conditions, only a small leak rate, 11 cc/min, could be frozen off. It is recommended that, at the beginning of the the freezing operation, the temperature of the secondary refrigerant entering the freeze jacket be at least -40C and that the freeze jacket be made as long as practical.
Date:
January 21, 1957
Creator:
Draper, B. D.
System:
The UNT Digital Library
High Pressure Recombination Loop Progress Report
The operation and design of a high pressure recombination loop for the recombination of H2, D2, and O2 produced by the radiolytic decomposition of water which is used a solvent for fuel in the homogeneous reactors are presented.
Date:
January 4, 1957
Creator:
Harley, P. H.
System:
The UNT Digital Library
Estimation of the Thermal Conductivity and the Viscosity of Gases at High Pressure
Few data exist for the thermal conductivity and viscosity of gases at very high pressure. The possibility of using gases for heat transfer media at pressures up to 100 atmospheres and above raised the problem of estimating variations in the conductivity and viscosity at high pressure. Generalized plots are presented which are based on the work of Enskog, Eucken, and Hirschfelder et al. Some pertinent data from Hirschfelder et al and from Hilsenrath et al are presented.
Date:
January 17, 1957
Creator:
Lyon, Richard Norton
System:
The UNT Digital Library
Thermal Characteristics of a Delta Array Heat Exchanger
The heat transfer and fluid friction characteristics have been determined for a liquid flowing parallel to the tube bundle of a heat exchanger consisting of one hundred and two 1/16-inch O.D. tubes arranged in a delta or triangular array. These results may be expressed by empirical equations.
Date:
January 28, 1957
Creator:
Wantland, J. L.
System:
The UNT Digital Library
Delay Time Prior to Dumping the HRT
Some refined calculations have been made, relative to a proposed delay prior to a dump, to determine the expected D2 concentration in the vent stream from the pressurizer gas bleeds during a dump of the Homogeneous Reactor Test (HRT). These calculations indicate that for vent valves have a Cv of 0.07 (venting time from 2000 psia to D2O saturation pressure of approximately 12 minutes), a delay period is not required since the D2 concentration is well below lower explosive limit. For vent valves having a Cv of 0.3 (venting time approximately 2.4 minutes), the calculation indicate that a delay before venting of approximately two minutes will be required. This is due entirely to the possibility of mass ebullition the D2. Since the pressure drops so quickly, the reactor solution becomes saturated with D2 before appreciable recombination can occur.
Date:
January 10, 1957
Creator:
Gift, E. H. & McLain, Howard A.
System:
The UNT Digital Library
Eddy-Current Measurement of Clad Thickness on Mark X MTR Fuel Plates
At the request of the Alloy Preparation Group, the Nondestructive Test Development Group investigated the feasibility of determining the clad thickness on Mark X MTR Fuel Plates. As the use of induced eddy-currents was considered to be the most promising approach, a prototype instrument and probe coil utilizing this principle was developed to measure clad thickness. The results of the investigation conducted with this instrument indicate that the clad thickness of this type of fuel plats can be measured to withing +- 0.001 in.
Date:
January 23, 1957
Creator:
Oliver, R. B.; Allen, J. W. & Nance, Roy A.
System:
The UNT Digital Library
HRT Source Shield Calculations
Calculations indicate that the proposed shielding arrangement will give a dose rate at the surface of the water tank of about 100 mrem per hr., practically all gammas. This is adequate for transportation and handling, but if the radiation actually proves to be this high, a storage location isolated from normal working areas must be provided. The isolation area need not be large, however, since the calculated dose rate at 10 feet from the shielded sources is only 3.5 mrem pr hr. For the short time required to transfer the source from the water tank into the reactor the Pb carrier alone will provide sufficient shielding. At one meter from the source shielded by the Pb carrier, the dose rate is estimated to be 170 mrem per hr., with neutrons contributing he major part. With reasonable care, the operations should be carried out without excessive exposures. The results of the calculations are summarized.
Date:
January 8, 1957
Creator:
Haubenreich, P. N. & Rivenbark, G. W.
System:
The UNT Digital Library
Metallurgical Examination of HRT Leak Detector Tubing and Flanges
After several failures had occurred in the HRT leak detector system, several lengths of this tubing were removed for metallurgical examination. The tubing was of type 304 stainless steel and was 1/4" in diameter with a 0.065 wall. The tubing had been purchased as three different lots, the first in 45 ft. lengths and the other two as standards lengths. Tubing from the first lot was used primarily for the shield penetration and, therefore, sections of it are present in all lines of the system. It appears that chloride contamination entered the system in a portion of the first lot of tubing used for the shield penetration. The exact source of the chloride cannot be determined, but after considering the results and visiting the manufacturer's plant, it appears most likely the contamination was during the manufacturing process.
Date:
January 31, 1957
Creator:
Adamson, G. M; Hammond, T. M.; Kegley, T. M. & White, J. K.
System:
The UNT Digital Library
Determination of Submicron Particle Sized by an Activation Analysis - Centrifugation Method
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.
System:
The UNT Digital Library
Catalysts for Recombination of Radiolytic Gases Over Thorium Oxide Slurries
Catalysts for use in recombining the gases produced by the radiolytic decomposition of water in thorium oxide slurries under neutron irradiation were investigated in out-of-pile tests using stoichiometric mixtures of hydrogen and oxygen. Most favorable results were obtained with a molybdenum oxide catalyst. Satisfactory rate also were attained with palladium and silver oxides. Copper, nickel, vanadium and chromium compounds were less effective.
Date:
January 29, 1957
Creator:
Morse, L. E.
System:
The UNT Digital Library
Uranium Recovery for Spent Fuel by Dissolution in Fused Salt and Fluorination
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 the fluorination step due to the low volatility of most of the fission product fluorides. An over-all decontamination factor greater than 106 with adequate uranium recovery has been demonstrated in laboratory scale tests using a double bed procedure for the NaF step. A pilot plant has been constructed for testing the process with various heterogeneous fuel elements. The engineering and operational features of the pilot plant are described
Date:
January 29, 1957
Creator:
Cathers, G. I.
System:
The UNT Digital Library
Reactor Irradiation of Thorium and Uranium Oxides Slurries
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 gross changes occurred in the particulate properties.
Date:
January 29, 1957
Creator:
Krohn, N. A. & McBride, J. P.
System:
The UNT Digital Library
The Chemical Processing of Two-Region Aqueous Homogenous Reactors
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 and thorium by solvent extraction for return to the reactor. The use of a hydroclone and underflow container arrangement for concentrating insoluble fission and corrosion products under simulated reactor conditions has been successfully demonstrated on dynamic loops. Solids concentration factors greater than 103 were demonstrated, and equilibrium solids concentration in the circulating solution less than 1 ppm was attained in these tests. Present data indicate that proper design and operation will minimize solids deposition in the reactor system and that the insoluble impurities can be effectively removed by the hydroclone. An alternate method of processing the slurry removed from the core system by the hydroclone consists of removing the room temperature insolubles by centrifugation, recovering the uranium from the supernatant by peroxide precipitation, thermal …
Date:
January 29, 1957
Creator:
Ferguson, D. E.
System:
The UNT Digital Library
The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes
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.
System:
The UNT Digital Library
Advanced converter technology. Technical progress report, May 23, 1979-May 22, 1980
The overall objective of this program is to define an advanced converter system employing 1980's technology in all subsystem and component areas for use in electrochemical energy storage systems. Additional experimental effort will validate elements of the advanced commutation circuitry on a full-scale breadboard basis. Improved models of battery electrical characteristics are being defined and experimental apparatus is being designed to measure these characteristics and to enable better definition of the battery-power conditioner interface. Improvement of energy-storage system performance through modification of battery converter characteristics will also be investigated. During this first year of the contract, a new more advanced concept for power conditioning based on a concept defined by United Technologies Corporation for fuel cell use was evaluated. This high switching frequency concept has the potential for significantly reducing the size and cost of battery plant power conditioners. As a result, the Department of Energy authorized redirection of the program to first evaluate this new concept and then to reorient the program to adopt this concept as the primary one. Progress is reported. (WHK)
Date:
January 1, 1980
Creator:
Banic, C. V.; Eckhouse, S. A.; Kornbrust, F. J.; Lipman, K.; Peterson, J. L. & Rosati, R. W.
System:
The UNT Digital Library
Studies of Reactor Containment : Monthly Technical Progress Report No. 32
The report covers work performed during the period December 1, 1959 through December 31, 1959. The general objectives of the program of "Studies of Reactor Containment" are to accomplish theoretical and experimental investigations of the loads to which external containment structures for nuclear reactors are subjected in the vent of a violent incident at the reactor core, the evaluation of methods of reducing that loading, and the study of the response of and design criteria for external containment structures as a result of such loading. Progress of technical effort during the report period is summarized for each of the eight tasks of the program..
Date:
January 15, 1960
Creator:
Zaker, T. A. (Thomas Allen)
System:
The UNT Digital Library