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335
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249
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158
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37
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139
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137
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99
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90
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73
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64
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944 Matching Results
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The Disposal of Power Reactor Waste Into Deep Wells
For various reasons it is not possible to leave the uranium or other nuclear fuel in a power reactor until all of it has been "burned up" by fission. In the case of liquid fuel (homogeneous) reactors a small part is continuously bled out, purified and returned. In the case of solid fuel reactors, fuel elements are periodically removed, reprocessed and the "unburned" fuel put back into service. In both cases the purification produces wastes which contain radioactive fission products and transuranic elements, and it is with the disposal of these wastes that we are concerned. For technical reasons, we will limit our consideration to the wastes from the processing of solid fuel elements, and from the processing of the very similar solid "blanket" elements in which fissionable fuel is made from non-fissionable isotopes of uranium and thorium by interaction with neutrons in the outer regions of the nuclear reactor.
Date:
June 13, 1957
Creator:
De Laguna, Wallace, 1910- & Blomeke, J. O.
Object Type:
Report
System:
The UNT Digital Library
A Brief Review of thermal Gradient Mass Transfer in Sodium and NaK Systems
The fact that material transport does occur under conditions of finite temperature difference in a flowing molten metal system was established. The rate mass transfer was thought to be either diffusion limited or solution rate limited. It is believed that the mass transfer of structural materials in Na or NaK systems is solution rate limited. The limiting process has not been qualitatively or quantitatively confirmed for the Inconel-Na or Inconel-NaK system. Increasing the maximum system wall temperature increases the amount of mass transfer, at least above 1300 deg F. The effect of the total temperature difference across the system on the amount of mass transfer was determined.
Date:
February 11, 1957
Creator:
DeVan, J. H. & West, J. B.
Object Type:
Report
System:
The UNT Digital Library
Abnormal grain growth in nickel-base heat-resistant alloys
From Introduction: "The data included in this report for Nimonic 80A alloy, for instance, represent experiments carried out to help clarify a production problem of grain-size control in an alloy which has been extensively used. The general procedure of the investigation was to carry out controlled laboratory experiments on samples of bar stock to find conditions of heating and hot-working which resulted in abnormal grain growth."
Date:
December 1957
Creator:
Decker, R. F.; Rush, A. I.; Dano, A. G. & Freeman, J. W.
Object Type:
Report
System:
The UNT Digital Library
A Noble Gas Scintillation Counter
The following report describes a gaseous scintillation counting system, including the production and operation of the counter.
Date:
May 28, 1957
Creator:
Dickieson, Robert W.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Maintenance of Various Reactor Types
This technical report presents an overview of nuclear reactor maintenance to be used in planning a nuclear reactor. There are certain basic maintenance fundamentals that are common to all types of reactors that may be' incorporated in a power producing facility. Basically, there are only two types of maintenance procedures. The direct type, which is common to conventional steam plants, may be used in some areas where the radioactivity is low enough. In most parts of the plant, maintenance will of necessity be remote due to the high level of radioactivity. For simplicity of description in this report all reactor types are divided into two general classes: solid fuel types and circulating fuel types. The report lists nine types of reactor power plant types with advantages and disadvantages maintenance-wise of each.
Date:
April 8, 1957
Creator:
Draper, R. D.
Object Type:
Report
System:
The UNT Digital Library
The Effect of Fluctuations in the Widths on Neutron Reaction Cross Sections
The general Wigner-Eisenbud theory is used to develop a method of analysis for the cross sections of fissionable nuclei. The method is employed in giving a reasonable description of the low energy cross sections in U/sup 235/. The single level fit for U/sup 235/ is known to be unreasonable. Many level expressions for the cross sections are derived--the only approximation to the general theory being the neglect of all but a small group of resonances. It is shown that regardless of the number or definition of the fission channels the many-level expressions require few level parameters: the E/sub lambda /, GAMMA / sub lambda n/, GAMMA /sub lambda gamma / and GAMMA /sub lambda F/ of the single level theory for each resonance and a few additional parameters pertinent to the interference between levels. The interference terms are described and shown to be important. The shape and size of the U/sup 235/ cross sections below 2 ev are fitied to within one per cent using (a) only one negative energy resonance of smaller size than in the single level fits (b) no additional levels to fit the shape other than the observed levels at positive energies (c) three interference parameters …
Date:
June 1, 1957
Creator:
Dresner, Lawrence
Object Type:
Report
System:
The UNT Digital Library
Neutrons from High Current Gaseous Discharges
Abstract: "Experiments on the neutrons produced in a high-current pulse discharge in deuterium are described. With 15 kv applied to a straight discharge tube 30 cm in length neutrons are produced at ~1.4 [mu]sec after gas break-down in a pulse 0.1 [mu]sec in length. The yield, 10-7 - 10-8 neutrons per discharge, is quite sensitive to gas purity and discharge tube wall material. The axial asymmetry in neutron energy indicates that the neutrons were produced in reactions whose center of mass moves preferentially towards the cathode. Several mechanisms for the production of these neutrons are discussed."
Date:
1957
Creator:
Dunaway, Robert E.
Object Type:
Report
System:
The UNT Digital Library
Exploratory drilling in the Posey and Markey localities, Red Canyon area, San Juan County, Utah
A report discussing exploratory diamond drilling in the Posey and Markey localities.
Date:
March 18, 1957
Creator:
Easton, William W. & Oertell, Eudene W.
Object Type:
Report
System:
The UNT Digital Library
Geology of the Aluminum Phosphate Zone in the Lakeland Highlands Area and Clark James-South Ridgewood Tracts, Land-Pebble Phosphate District, Polk County, Florida
The following report is based mainly on information obtained from lithologic and gamma-ray logs of drill holes in the Lakeland Highlands area and Clark James-South Ridgewood.
Date:
June 1957
Creator:
Emerick, W. L.
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
Effect of Pressure Differentials on Deflection of the Outer Fuel Plates of Brazed APPR Fuel Elements
One of the considerations in designing a flat plate fuel element is the resistance of the fuel plates, especially the outer plates in the fuel plate array, to deflection and permanent deformation as a result of pressure differentials. An investigation was recently initiated wit the objective of obtaining preliminary information on the APPR-type fuel element to determine the effect of pressure differentials on the outer plates in the fuel assembly. The APPR-1 fuel element consists of 18 flat composite stainless steel fuel plates, joined to grooved 50 mil thick type 304L stainless steel side plates by brazing with Coast Metals N. P. alloy.
Date:
February 7, 1957
Creator:
Erwin, J. H. & Beaver, R. J.
Object Type:
Report
System:
The UNT Digital Library
The Crystal Structures of Three New Vanadium Oxide Minerals
This report analyzes the characteristics of three vanadium-uranium ores of the Colorado Plateau by prevalence of a number of low-valence vanadium oxide minerals, usually occurring as fine-grained mixtures. The ores being analyzed are haggite, doloresite, and duttonite.
Date:
June 1957
Creator:
Evans, Howard T., Jr. & Mrose, Mary E.
Object Type:
Report
System:
The UNT Digital Library
Investigation of Tuffs Near Lysite, Wyoming for Selenium
Report issued by the Bureau of Mines over studies conducted on seleniferous tuff deposits in Wyoming. Results of the tuff samples obtained are presented. This report includes tables, maps, photographs, and illustrations.
Date:
January 1957
Creator:
Everett, Floyd D. & Bauerle, L. C.
Object Type:
Report
System:
The UNT Digital Library
Interactions of Negative K Mesons in Flight in Nuclear Emulsion
The following report discusses a survey of seventy-seven interactions of K- mesons in flight in nuclear emulsion with seven decays in flight, and finding four inelastic scatterings.
Date:
April 30, 1957
Creator:
Featherston, Frank Hunter
Object Type:
Thesis or Dissertation
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
Exploration drilling in the Haystack Butte area, McKinley County, New Mexico
The US Atomic Energy Commission conducted a drilling program in McKinley County, New Mexico, from August 19, 1953, through April 19, 1954, to explore the Jurassic Todilto limestone for uranium occurrences on the eastern, northeastern, northern and northwestern sides of Haystack Butte
Date:
January 1957
Creator:
Fincher, Forrest R. & Konigsmark, Ted
Object Type:
Report
System:
The UNT Digital Library
Trip to Selas Corporation of America
On May 23, 1957, a visit was made by the writer to the Selas Corporation of American in Dresher, Pennsylvania. The purpose of the visit was to discuss further investigations into methods of tubesheet brazing by direct heating. Original work along these lines has been carried out at ORNL and is covered by a memo (CF-57-4-57) to W.D. Manly, dated April 16, 1957, and entitled : Investigation of Tubesheet Brazing by a Method of Direct Heating.
Date:
June 18, 1957
Creator:
Franco-Ferreira, E. A.
Object Type:
Report
System:
The UNT Digital Library
High Pressure Flange Studies
Twenty-five hundred psi ring-type flanges, ring gaskets, bolts, and special connectors were tested for adaptability to the aqueous homogenous reactor. High pressure line closures were studied to obtain empirical data pertinent to the selection or design of a connector capable of withstanding sustained thermal cycling and high pressures encountered in the aqueous homogenous reactor. Specialized stress-strain measurement techniques yielded information concerning flange deformation, ring type gaskets, bolts, and special connectors. The results indicated that no totally acceptable connector is currently available. Most promising of the combination of components tested during this period was a 2500 psi ring type flange with an accurately machined octagonal gasket and Grade B-7 bolts.
Date:
January 5, 1957
Creator:
Fritz, K. J.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Design Requirements Argonne Boiling Reactor (ARBOR) Facility
From Introduction: "Descriptions of the functional requirements of the facility, together with preliminary concepts of methods for meeting them, are presented in this prospectus."
Date:
July 15, 1957
Creator:
Fromm, L. W.; Bernsen, S. A.; Bullinger, C. F. & Matousek, J. F.
Object Type:
Report
System:
The UNT Digital Library
Bibliography
From abstract: This bibliography consists of references pertaining to "Effects of Nuclear Radiation Upon Electronic and Electrical Components", and to "Electronic and Electrical Components for Critical Environments". References were compiled from the Classified and Unclassified report literature and the published literature. The following indexes and abstract journals were used: Weapons Data Index, AEC Card Catalog, Engineering Index (1950-55), and Office of Technical Services, Research Reports (1956-March '57).
Date:
April 30, 1957
Creator:
Frost, Frederick E.
Object Type:
Report
System:
The UNT Digital Library
Drying of Charcoal Used for Adsorption of Gaseous Fission Products from Homogeneous Reactors
In homogeneous nuclear reactors significant quantities of radioactive inert gaseous fission products must be separated from the fuel solution for disposal. The present disposal scheme, which is employed on the HRT, is to pass the mixture of fission product gases and oxygen through a charcoal adsorption bed. the oxygen passes through the bed relatively un-adsorbed, but the radioactive inert gases are adsorbed and are displaced from the bed bed very slowly giving the gases a much greater residence time than would exist if no bed were used. This long residence or "holdup" time permits the short-lived inert gases to decay away before emission to the atmosphere and thus greatly reduces the safety hazard produced by disposal of the gases to the atmosphere. The same effect could be obtained by using a large holdup tank, but the charcoal bed is much more compact and thus required less shielding.
Date:
December 20, 1957
Creator:
Funderburg, J. M. & Moss, L. I.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Loop Components and Admixed Thorium-3% Uranium Oxide Slurry in 200A Loop (Summary of Run 200A-10)
A slurry addition system, a venturi in the circulation loop, and two types of sampling systems were tested with 500 and 800 g Th/kg H2O slurries in the 200 gpm loop at 250 C and 1000 psig. The addition system worked satisfactorily while the venturi gave erratic readings during part of the run. Both the capillary and in-line sampling systems proved satisfactory with the capillary sampler being much easier and more convenient to operate. The addition of uranium to the slurry had no appreciable effect on the handling characteristics, the attack rate on 347 SS, the particle size and crystallite size of the thorium oxide. The attack rate was found to be 1 mpy during the first 100 hours of circulation and decreased to 0.4 mpy at the end of the run.
Date:
June 13, 1957
Creator:
Gallaher, R. B.; Kitzes, A. S. & VandenBulck, C. F.
Object Type:
Report
System:
The UNT Digital Library
Steam Slip and Burnout in Bulk Boiling Systems
In concurrent flow of two phase mixtures there exists a velocity difference between the vapor and liquid phases. This difference in velocity is known as the slip velocity. The prediction of slip is the subject of Part I. In boiling systems there is some heat transfer rate at which nucleste boiling becomes unstable. At this point the separate bubbles coalesce forming an insulating vapor film on the heat transfer surface resulting in the destruction, or burnout, of the heater. The prediction of the conditions causing burnout is the subject of Part II.
Date:
June 5, 1957
Creator:
Gelson, A. E.
Object Type:
Report
System:
The UNT Digital Library