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Extrusion of Uranium Tubes

Description: Technical report. From Abstract : "Several hundred long, thin-walled uranium tubes were extruded to close dimensional tolerance by a potentially low cost fabrication process in commercial facilities. The principal process steps were; forging uranium ingots, machining the forged ingots into billets, and extruding the billets into tubes. Some 750 tubes (maximum dimensions: 3.5 inches in diameter and 15 feet long) were fabricated by this process. Dimensional control was excellent in that 88% of th… more
Date: July 1961
Creator: Fisher, R. E.
open access

Fabrication of UO2 Fuel Elements by Vibrational Compaction

Description: Technical report. From Abstract : "Arc-fused UO2 was vibrationally compacted to as high as 93.4% of theoretical density inside a stainless steel sheath tube. Selected particle sizes were used, and the assembly was vibrated axially in the frequency range of 300 to 1500 cycles per second. The same blend of UO2 particle sizes was vibrationally compacted to 87.5% of theoretical density within the annulus between two concentric stainless steel sheath tubes. The effects of particle size distribution,… more
Date: February 1962
Creator: Marah, Harold G.
open access

A Facility for Chemical Separation of Pu238

Description: Technical report. From Abstract : "A facility for separation of Pu238 and Np237 from irradiated neptunium dioxide target slugs was designed, constructed, and operated at the Savannah River Laboratory. This report describes the facility and includes design details of equipment." From Summary : "The main problems encountered during the design of the facility were: (1) to provide adequate containment and shielding of the radioactive materials, (2) to select chemical- and radiator-resistant materia… more
Date: August 1962
Creator: Coogler, Arthur L. & Fowler, Bill F.
open access

Fuel Meltdown Experiments

Description: From Abstract: "Fuel tubes of enriched uranium-aluminum alloy were melted to various degrees of severity in the SPERT I reactor as a part of a program to evaluate reactor operating hazards. The heat flux encountered during the tests ranged from 200,000 to 650,000 pcu/(hr)(ft^2). The time required for the metal temperature to reach the melting point from the time when burnout began varied from 1.3 to 4.9 seconds. During these tests, pressure pulses were produced at a frequency of about one per s… more
Date: October 1958
Creator: Seaboch, James R. & Wade, James W.
open access

Identification of Curium-242 in Irradiated Neptunium

Description: Technical report. From Abstract : "Curium-242 was experimentally identified as a minor product of the irradiation of neptunium-237 in a nuclear reactor." From Introduction : "Determinations of the half-life, alpha energy, and daughter product of the purified curium nuclide were made in this study to confirm the identity as curium-242."
Date: August 1961
Creator: Carothers, Glenn A.
open access

Initial Operation of the Standard Pile

Description: From abstract: "The Standard Pile was first brought to criticality on July 25, 1953. The first two months of operation permitted calibration of the reactor and preparation of it for use as a neutron source in exponential experiments."
Date: December 1953
Creator: Axtmann, Robert C.; Heinrich, L. A.; Robinson, R. C.; Towler, O. A. & Wade, J. W.
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.
open access

Irradiation of Powder Metallurgy Plates

Description: From abstract: "Four plates of uranium that were fabricated by powder metallurgy techniques and clad with 1100 aluminum by hot pressing were irradiated in the Materials Testing Reactor. Increases of about one-half per cent in length and one per cent in thickness were observed after exposure of 1600 megawatt days per ton. The surfaces of the plates remained smooth."
Date: April 1957
Creator: Angerman, C. L.; Douglass, D. L. (David Leslie), 1931-; Marshall, R. P. & Caskey, George R., Jr.
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 … more
Date: May 1956
Creator: Marshall, Robert P.
open access

Irradiation of Wrought Uranium Plate

Description: From abstract: "Wrought uranium plate, clad in 1100 aluminum with a nickel bonding layer, was irradiated to a maximum exposure of 1600 MWD/T in the MTR and was demonstrated to be suitable as a fuel element material. Beta-transformed plate, or beta-transformed plate that was cold stretched 2-1/4 per cent, did not change appreciably in dimensions but roughened on the surface. As-rolled plate increased in length, but did not roughen. Irradiation reduced the strength and virtually eliminated the du… more
Date: July 1957
Creator: McDonell, William R. & Marshall, Robert P.
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… more
Date: May 1958
Creator: Johnson, B. S., Jr.; Grace, J. T.; Meyer, L. H.; Karraker, D. G. & Nicholson, C. K.
open access

Kinetics of the Beta Transformation of Uranium

Description: From abstract: "When uranium is heat treated at low beta-phase temperatures and air cooled, the rate of loss of preferred orientation is markedly less than the rate of coarsening of the grain structure. A coarse-grained structure cannot therefore be taken as an infallible indication of satisfactory heat treatment. The final grain size of incompletely transformed metal is essentially equal to or larger than the starting grain size. Large-grained specimens can not be refined by interruption of th… more
Date: September 1957
Creator: McDonell, William R.
open access

Manganese Dioxide Precipitation in Uranium - Aluminum Nitrate Solutions

Description: Technical report. From Abstract: "Precipitation of manganese dioxide in solutions of uranium-aluminum alloy effected maximum removal of fission products when the alloy solutions were acid deficient. Minimum adsorption of uranium and minimum volume of centrifuged MnO2 were obtained by precipitation in acidic solutions with vigorous agitation."
Date: February 1959
Creator: Henry, Hugh E.
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 p… more
Date: October 1956
Creator: Colven, Thomas J., Jr.
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.
open access

Mounting Thermocouples on SPERT Test Assemblies

Description: Technical report. From Abstract: "A method of fastening thermocouples to 0.030-inch-thick aluminum cladding on test fuel elements was developed. The installation does not lead to hot spots by the addition of extra metal of the distortion of the cooling water channels. Fuel element temperatures were faithfully followed in SPERT tests up to the melting point. The method has been useful for fastening thermocouples to aluminum sections in general."
Date: December 1959
Creator: Sanders, Harold S.
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 … more
Date: January 1956
Creator: Bell, W. F.
open access

Neutron Spark Counter

Description: Technical report. From Abstract : "Spark counters of the wire plate type are rugged and simple, and their sensitivity is directly proportional to the specific ionization of incident particles. Spark counters are insensitive to beta and gamma radiation but readily respond to alpha particles. With a suitable converter, the spark counter can also be employed as a neutron counter. Spark counters thus appear to be very good candidates for the measurement of neutron flux at reactor startup, where the… more
Date: October 1960
Creator: Caiati, Frank P.
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.
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.
open access

Nonlinear Analogue to Digital Converter

Description: Technical report. From Abstract: "An electromagnetical instrument is described which produces a shaft rotation which is a linear function of the quantity being measured from a non-linear input signal. The instrument was used to convert the output function of the Nuclear Test Gage (NTG) which is nonlinear with respect to fuel concentration to a form that will directly drive an automatic production recorder (APR). The output shaft is also geared to a Veeder Root counter so that the value of the i… more
Date: August 1959
Creator: Goodwin, Leslie E.
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.
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