Search Results

open access

A Monitor for Surface Adsorbed Tritium

Description: From abstract: "A monitor for detection of surface-adsorbed tritium beta particles has been developed. The detecting element is a windowless Geiger tube with the counting gas flowing through it. The normal limit of detection of a single-tube probe is 800 d/m of tritium, while a three-tube probe is probably limited to about 2000 d/m. Both probes have a counting efficiency of about 10% for tritium."
Date: December 1953
Creator: Karraker, D. G.
Partner: UNT Libraries Government Documents Department
open access

Thermocouples and Cables for Nuclear Reactors

Description: From abstract: "The development, design, specification, and manufacture of special-purpose thermocouples sheathed in stainless steel for use in nuclear reactors are described. In connection with this work, a three element cable for transmitting the signal from neutron-flux measuring devices was developed."
Date: October 1953
Creator: Stone, J. M.
Partner: UNT Libraries Government Documents Department
open access

Transformation and Non-Bond Tester for Flat Elements

Description: From abstract: "A composite ultrasonic unit was developed to indicate the size and location of non-bonded areas and the presence of non-transformed regions in flat uranium fuel elements clad with aluminum. A two-dimensional recorder was developed to yield instantaneous, permanent records of the non-bonded areas on electrosensitive paper. Panel lights indicate the presence of non-transformed regions that have not received proper heat treatment. Defects 1/8" in diameter are consistently detected at an inspection rate of approximately 50 sq. in./min."
Date: November 1954
Creator: Blucke, W. L.
Partner: UNT Libraries Government Documents Department
open access

A Detector for Sub-Surface Cracks

Description: From abstract: "An instrument was developed to detect cracks within 1/8 inch of the surface of cylindrical uranium fuel slugs. The instrument measures changes in eddy currents that are induced at a frequency of 2 KC."
Date: August 1954
Creator: Goodwin, L. E.
Partner: UNT Libraries Government Documents Department
open access

Operation of TNX Evaporator

Description: From abstract: "Performance data were obtained for the TNX replacement evaporator when operated within the limits imposed by a new control system. This system was designed to avoid conditions which might lead to a repetition of an earlier explosion due to inclusion of organic material in the uranyl nitrate-nitric acid system, which was heated to elevated temperature. The true heat transfer coefficient was found to be 280 BUT/hr-ft2-ºF for all concentrations of solutions to be evaporated in the plant, and will allow operation at design capacities."
Date: October 1954
Creator: Nichols, G. S. & Occhipinti, E. S.
Partner: UNT Libraries Government Documents Department
open access

Radioactivity in the Environs of the Savannah River Plant January to July - 1954.

Description: From abstract: "There were significant increases in radioactivity in the environs of the Savanna River Plant during the period from January 1954 to July 1954. All of these increases were relatively small as compared to the maximum permissible concentration. Although fallout from Pacific tests was the main contributor to the increased activity, some of the increase was due to normal Plant operations."
Date: November 1954
Creator: Horton, J. H., (J. Henry)
Partner: UNT Libraries Government Documents Department
open access

Corrosion in Hydrogen Sulfide - Water Systems

Description: From abstract: "This report gives a detailed account of the corrosion test work carried out by the Engineering Research Laboratory on the behavior of materials of construction in the hydrogen sulfide-water system. Results developed during the period from October 1950 through November 1954 are included."
Date: October 1955
Creator: Snyder, J. A. & Warren, D.
Partner: UNT Libraries Government Documents Department
open access

A Safety Rod Actuator

Description: From abstract: "A windlass that operates a safety rod for a nuclear reactor was developed to decelerate the rod after it drops under emergency conditions into the reactor. The windlass is designed to convert the kinetic energy of the falling rod as it nears its limit of travel to rotational energy in the windlass. The conversion is accomplished without the aid of an external power source or an auxiliary snubbing mechanism."
Date: December 1954
Creator: Baker, D.; Llewellyn, W. E. & Maloney, J. P.
Partner: UNT Libraries Government Documents Department
open access

Ion-Chamber Water Monitor

Description: From abstract: "An instrument capable of detecting fission-product contamination in the moderator has been developed. It consists of a thin-walled ion chamber and associated electronic equipment for automatically detecting deviations from normal moderator decay rate. Indication of fission-product activity is independent of power level, flowrate, and other ambient conditions. Tests show the sensitivity and long-term stability to be good."
Date: February 1955
Creator: McCarthy, R. L.
Partner: UNT Libraries Government Documents Department
open access

MTR Test Equipment

Description: From abstract: "Sample holders and monitoring equipment were designed and fabricated for use in the irradiation of experimental shapes of fuel and target materials in the beryllium reflector of the Materials Testing Reactor. The samples were held in aluminum cases designed to replace certain beryllium blocks of the reflector. Sample holders of alternate designs were made to permit irradiation of samples in the reflector at locations where the shape or position of the reflector blocks would not permit the use of the original design."
Date: January 1956
Creator: Bell, W. F.
Partner: UNT Libraries Government Documents Department
open access

Stress Analysis of the SRP Reactor Tank

Description: From abstract: "Equations are derived from the discontinuity stress in a cylindrical tank that is mounted vertically on a header and is open at the top. The analysis includes a derivation of equations for the prediction of the deflection and slope of the header by relating the strain energy in bending a circular plate to the strain energy in bending the header. The stresses that result from pressure and temperature are included in the analysis."
Date: October 1955
Creator: Walker, J. W.
Partner: UNT Libraries Government Documents Department
open access

Nondestructive Measurement of the Uranium Content Uranium-Aluminum Alloys

Description: From abstract: "An instrument is described which measures the uranium content of a 0.080-inch thick plate of uranium-aluminum alloy. The content is measured by gamma-ray transmission to an accuracy of +/- 0.0006 gram per square centimeter over the range of 0.085 to 0.115 gram per square centimeter of contained uranium."
Date: October 1955
Creator: Goodwin, L. E.
Partner: UNT Libraries Government Documents Department
open access

Mixer-Settler Development: Operation Characteristics of a Large-Scale Mixer-Settler

Description: From abstract: "A pump-mix mixer-settler was demonstrated to have an overall efficiency greater than 90 per cent for the extraction of uranyl nitrate from tributyl phosphate at total flow rates up to 45 gallons per minute. Phase separation was satisfactory at 45 gallons per minute, at which flow rate the residence time in the settlers was 1-1/2 minutes. It appeared possible that a throughput approaching 60 gallons per minute would be operable although at an over-all efficiency of less than 90 per cent. The tests were made on a three-stage unit, but the data can be extrapolated to multistage units. The effects of design of the impeller and mixing section, impeller speed, flow rates and ratios, and operating temperatures were studied. The mechanical performance and dependability of the unit were excellent."
Date: October 1956
Creator: Colven, Thomas J., Jr.
Partner: UNT Libraries Government Documents Department
open access

The Nuclear Test Gauge

Description: From abstract: "The 'Nuclear Test Gauge', a slightly subcritical assembly for quality control of reactor components, was designed, constructed, and placed in operation. calibration experiments demonstrated that the sensitivity of the unit is adequate, and that the speed of testing is increased y a factor of ten over that of a critical test pile."
Date: June 1956
Creator: Parkinson, Thomas F.; Goosey, Malcolm H.; Heston, William M. & Hollberg, Herbert J.
Partner: UNT Libraries Government Documents Department
open access

Irradiation of Thorium Slugs

Description: From abstract: "Ninety-two thorium slugs were irradiated in the Hanford piles to study the dimensional stability of the metal. The burnups that were incurred covered the range from 300 to 2800 ppm of the Th232. Slugs with burnups as high as 800 ppm were examined for visual and dimensional changes. The dimensional stability of these slugs was excellent, and no significant corrosion occurred on the aluminum cans. A cursory examination of slugs with burnups of greater than 800 ppm showed no gross dimensional instability."
Date: May 1956
Creator: Marshall, Robert P.
Partner: UNT Libraries Government Documents Department
open access

A Nonbound Detector for Hollow Slugs

Description: From abstract: "A tester was developed to detect nonbonded areas between the cladding and the core of hollow slugs. These slugs are one inch in diameter and eight inches long, and have a 3/8 inch axial hole. The tester employs an ultrasonic detector previously developed at the Savannah River Laboratory. A transducer 5/16 inch in diameter was developed to pass down the inside of the slug and a mechanical feeder was constructed to provide an automatic inspection cycle."
Date: October 1956
Creator: Ross, John D. & Leep, Richard W.
Partner: UNT Libraries Government Documents Department
open access

An Automatic Flaw Detector for Aluminum Cans

Description: From abstract: "A tester, utilizing eddy currents, was developed to detect inclusions and voids in aluminum cans. The sensing element is a small probe that does not touch the can under inspection. An experimental feeder, developed along with the tester, permits the automatic inspection of one can per minute."
Date: October 1956
Creator: Ross, John D.
Partner: UNT Libraries Government Documents Department
open access

Shearing Irradiated Uranium Plates

Description: From abstract: "Natural uranium plates that were irradiated to 600 and 1500 MWD/T were cut under water by a guillotine-type shear. Irradiation reduced the force required for shearing to 50 per cent of that required for unirradiated uranium. Measurements were made of radioactivity released to treated and untreated water in which the cut sections were stored."
Date: November 1956
Creator: Delicate, W. Scott; Osterman, Edmund J.; Zeh, Carl W. & Wither, W. T.
Partner: UNT Libraries Government Documents Department
open access

Concentration of Plutonium by Cation Exchange Part I - New Elutriants

Description: From summary: "The concentration of plutonium by cation exchange was significantly improved by using a solution of ammonium lactate and sulfamate as the elutriant instead of nitric and sulfamic acids. The new elutriant permitted essentially complete elution of the plutonium and also avoided formation of gases in the resin bed during elution. At 45ºC, 2.8M ammonium lactate plus 0.15M ammonium sulfamate eluted 99.3 per cent of the total plutonium at an average concentration of 43.8 grams per liter. It was found necessary to elute hydrogen and hydroxylammonium ions from the resin beds before elution of plutonium. The hydroxylammonium ions decompose to form gases in the resin bed at the desired temperature for plutonium elution. The hydrogen ions exchange with ammonium ions of the elutriant and decrease the concentration of plutonium in the eluate."
Date: December 1956
Creator: Bonner, Oscar D.; Burney, Glenn A. & Tober, Frank W., 1919-1995
Partner: UNT Libraries Government Documents Department
open access

A Simple Leak Detector for Tritium

Description: From abstract: "An ionization chamber of the integrating type was built that could detect a tritium leak rate of 10[^-13] cc per second within a few minutes, after a gas-collecting period of 16 hours. Electronic circuitry was avoided by using a quartz fiber voltmeter to indicate the rate of discharge of the chamber."
Date: January 1957
Creator: Colvin, D. W.
Partner: UNT Libraries Government Documents Department
open access

Isotopic Purification of Tritium by Electrolysis

Description: From abstract: "An electrolytic refining process was developed to produce tritium of high isotopic purity with negligible loss. The operation is semicontinuous, with multiple stages in cascade. All tritium oxide is handled within the confines of a hermetically sealed enclosure. The mechanical operability of the process was demonstrated in a five-stage prototype line designed to process 15 gram-mols of feed per day. An average separation factor per stage of 5.3 was obtained with a feed of tracer-level tritium. The equipment is described in detail."
Date: May 1958
Creator: Johnson, B. S., Jr.; Grace, J. T.; Meyer, L. H.; Karraker, D. G. & Nicholson, C. K.
Partner: UNT Libraries Government Documents Department
open access

Distribution of Uranyl Nitrate Between Al(NO3)3 and Tributyl Phosphate

Description: From abstract: "The distribution of uranyl nitrate was measured from aluminum nitrate and nitric acid solutions into diluted tri-n-butyl phosphate. This information is useful for designing solvent extraction processes for recovery of uranium from aluminum nitrate or nitric acid solutions."
Date: March 1958
Creator: Ames, Donald P. & Karraker, David G.
Partner: UNT Libraries Government Documents Department
open access

Effect of Solvent Degradation on the Purex Process

Description: From abstract: "The combined attack of HNO3 and HNO2 on tributyl phosphate - kerosene solvent used in the Purex process produces degradation products that cause abnormal quantities of zirconium to be extracted along with the plutonium and uranium and thus limits the decontamination."
Date: May 1958
Creator: Siddall, Thomas H., III; Wallace, Richard M. & Prout, W. E.
Partner: UNT Libraries Government Documents Department
open access

Scavenging of Ruthenium From Purex Uranyl Nitrate Solution

Description: From introduction: "In previous work on the ion exchange adsorption of ruthenium, it was observed that when certain compounds of sulfur were added to dilute uranyl nitrate solutions, precipitates formed which carried ruthenium. The purpose of this investigation was to develop a similar method for scavenging ruthenium from concentrated uranyl nitrate solutions. Such a method, combined with the silica gel treatment for removing zirconium and niobium, might provide an integrated process to remove all three contaminants."
Date: June 1958
Creator: Prohaska, Charles A.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen