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2,265 Matching Results
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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.
Object Type:
Report
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.
Object Type:
Report
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
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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)
Object Type:
Report
System:
The UNT Digital Library
Low Energy Nuclear Physics : Second Annual Report for the Period February 1, 1959 to January 31, 1960
The general expression for the angular correlation between radiations produced in successive cascade transitions is derived by use of Racah algebra. The result is then specialized to the beta - gamma correlation and applied to two cases in which additional properties of the photon are specified, the circular polarization and the plane polarization. The prospect of testing time reversal and determining nuclear matrix element ratios by beta - gamma correlation measurements is explored using the nuclide Tm/sup 170/ as an example. The directional angular correlation between the 2.31-Mev beta and the subsequent 0.605-Mev gamma emitted in the decay of Sb/sup 124/ was measured as a function of the beta energy. The K-conversion coefficient of the 279-kev gamma following beta decay of Hg/sup 203/ was measured by comparing the x-ray and gamma intensities in a scintillation spectrometer. The measured valve of alpha /sub k/ = 0.195 plus or minus 0.014 indicates that the transition is M1 with E2 mixed to the extent of 63%. The angular correlation of the 107-1.24 Mev gamma cascade in Zn/sup 68/ following the decay of 68-min Ga/sup 68/ is shown. The Legendre polynomial expansion coefficients were deter-gular correlation in the decay of Sb/ sup 118/ was …
Date:
January 23, 1960
Creator:
Jastram, Philip S. (Philip Sheldon), 1920-1992
Object Type:
Report
System:
The UNT Digital Library
Research on Krypton 85 : Seventh Monthly Progress Report Covering December 1, 1959 to December 31, 1959
Work during this report period includes a continuation of the study of the effect of krypton 85 on the polymerization of styrene; an attempt at evaluation of the polymers produced; and the effect of krypton radiation on the electrical properties of gases, such as the rare gases, and nitrogen, and oxygen. the results obtained are summarized in the report.
Date:
January 21, 1960
Creator:
Miller, H. S.; Marancik, W. G. & Zufall, J.
Object Type:
Report
System:
The UNT Digital Library
Upper Atmosphere Monitoring Program : Progress Report No. 8 for May 1, 1959 through July 31, 1959
The overall scope of the program encompasses both research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication and calibration of balloon-borne sampling equipment to enable the precise determination of stratospheric particle concentration and particle size distribution.
Date:
January 15, 1960
Creator:
Baumstark, J.; Jones, S.; Stern, S.; Torgeson, L. & Zeller, W.
Object Type:
Report
System:
The UNT Digital Library
The Influence of Point Defects on the Mechanical Properties of Lithium Fluoride : First Technical Report
Lithium fluoride crystals were quenched into silicone oil from near the melting point. The return to an equilibrium structure during annealing was observed by means of mechanical tests and etching techniques. Crystals containing three levels of impurity, zone refined, commercially pure, and doped with 0.05 mole per cent magnesium, were used in order to separate the effects of foreign ions from those of thermal vacancies. The changes of mechanical properties produced by quenching and by subsequent annealing were generally attributable to point defect-dislocation interactions. Precision density determinations indicated that about 10% of the equilibrium concentration of vacancies at the melting point was retained at room temperature by the quench. The density could be restored to its normal value by annealing. Two important annealing stages were observed. At about 200 deg C the precipitation of impurities retained in solution by the quench caused a sharp increase in the hardness as measured at room temperature. Isothermal annealing revealed the hardening process to have an activation energy of about 0.5 ev which is probably the energy for migration of an associated magnesium ion-lithium vacancy pair. Between 300 and 400 deg C the removal of dislocations and probably vacancy clusters resulting from the quench …
Date:
January 1960
Creator:
Nadeau, J. & Washburn, J.
Object Type:
Report
System:
The UNT Digital Library
The SNAP II Power Conversion System. Topical Report No. 3. Dynamic Analysis
SNAP II is the designation for a nuclear auxiliary power unit, designed primarily for utilization in the WS117L satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine, and an alternator. Dynamic analysis of the power conversion system was conducted utilizing a comprehensive analog computer simulation. Feasibility of a parasitic load control for numerous system disturbances was demonstrated. This analysis was performed under a subcontract to to Atomics International as part of the Atomic Energy Commission Contract No. AT(11-1)-GEN-8.
Date:
January 15, 1960
Creator:
Deibel, David L.; Mrava, Gene L. & Seldner, Kurt
Object Type:
Report
System:
The UNT Digital Library
ORR Startup Accident and Cooling Flow Coastdown Analog Analysis
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 increased to the point where the level scram must be set above 50 Mw).
Date:
January 4, 1961
Creator:
Stone, R. S. & Colomb, A. L.
Object Type:
Report
System:
The UNT Digital Library
Summary of Runs 1, 2, and 3 in High-Temperature, High-Pressure Titanium Loop
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 proportion in the temperature range of 330 to 365°C. Corrosion of titanium and Zircaloy-2 specimens was insignificant during the relatively short exposure periods.
Date:
January 6, 1961
Creator:
Griess, J. C.; Baker, J. M. & Savage, H. C.
Object Type:
Report
System:
The UNT Digital Library
Bremsstrahlung Absorption Measurements from Sr^90 TiO3
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.
Object Type:
Report
System:
The UNT Digital Library
Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960
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.
Object Type:
Report
System:
The UNT Digital Library