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A Transistorized Pulse Height Analyzer for Gamma Spectroscopy

Description: From abstract: "A scintillation detector has a pulse height output which is a linear function of the energy of impinging gamma radiation. A pulse height analyzer system determines the amplitude distribution of this train of pulses. The system also displays this information graphically in a form which is convenient for further analysis."
Date: March 23, 1959
Creator: Graveson, R. T.
Partner: UNT Libraries Government Documents Department
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Geological Survey Investigations in the U12b.01 Tunnel, Nevada Test Site

Description: From introduction: This report includes a brief description of the stratigraphy and structure, and data on petrology, mineralogy, and chemical and physical properties of the rocks that are exposed in the U12b.01 tunnel of the U12b (Rainier) tunnel system.
Date: March 1959
Creator: Diment, William H.; Wilmarth, V. R.; McKeown, F. A.; Dickey, D. D.; Botinelly, Theodore; Hinrichs, E. Neal et al.
Partner: UNT Libraries Government Documents Department
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Fuel Enrichment for the Enrico Fermi Reactor

Description: Report issued by the APDA over fuel enrichment processes at the Enrico Fermi Atomic Power Plant. As stated in the introduction, "the results that directly apply to the determination of the enrichment will be given" (p. 6). This report includes tables, and illustrations.
Date: March 12, 1959
Creator: Garelis, Edward
Partner: UNT Libraries Government Documents Department
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1024 Channel Time-of-Flight Analyzer for MTR Fast Chopper - Operating Manual

Description: Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.
Date: March 11, 1959
Creator: Petree, F. L.
Partner: UNT Libraries Government Documents Department
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High Isotope Reactor Preliminary Design Study

Description: A comparison of possible types of research reactors for the production of trans-plutonium elements and other isotopes indicates that a flux-trap reactor consisting of a beryllium-reflected light-water-cooled annular fuel region surrounding a light-water island provides the required thermal neutron fluxes at minimum cost. The preliminary design of such a reactor was carried out on the basis of a parametric study of the effect of dimensions of the island and fuel regions heat removal rates, and f… more
Date: March 20, 1959
Creator: Lane, J. A.; Cheverton, R. D.; Claiborne, H. C.; Cole, T. E.; Gambill, W. R.; Gill, J. P. et al.
Partner: UNT Libraries Government Documents Department
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Poison Rod Requirements for a Solid-fuel Leacher Tank

Description: Estimates were made of the amount of neutron poisoning, in the form of boron rods, required to maintain subcriticality in a tank used for dissolution of solid fuel elements. The tank under consideration was a cylinder 19.5 inches in diameter and 6 ft in height. Maximum concentrations of fuel and fertile material resulting from dissolution of various type fuel elements are tabulated. Below the maximum concentrations listed, it was found that the limiting poisoning requirements are associated wit… more
Date: March 2, 1959
Creator: Prince, B. E.
Partner: UNT Libraries Government Documents Department
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Post-Irradiation Examination of APPR Fuel Element Irradiation Program Specimens

Description: APPR-type dispersion fuel element specimens containing temperature to respective burnups of approximately 50, 20, and 20% of uranium with no evidence of gross dimensional changes or loss of structural integrity. Blistering and/or core cracking has occurred when sections of 17.9 wt.% UO/sub 2/ specimens irradiated to burnups over 40% of uranium were subjected to post-irradiation annealing at 600 deg F for 24 hours. Post-irradiation core hardness measurements indicate that significant differences… more
Date: March 9, 1959
Creator: Richt, A. E.
Partner: UNT Libraries Government Documents Department
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The Use of Inconel as a High Temperature, Corrosion Resistant, Thermal Neutron Flux Monitor

Description: Inconel can be used for thermal neutron flux measurements by means of its cobalt impurity or its chromium constituent where conventional monitors are unsuitable. The use of cobalt should also be applicable to other nickel alloys. Discriminatory counting is required. (auth).
Date: March 16, 1959
Creator: Guss, D. E. & Leddicotte , G. W.
Partner: UNT Libraries Government Documents Department
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Calculational Models of Pot Calcination

Description: A simplified model for solids deposition in the pot calcination of waste was analyzed, and numerical calculations were made. In long calcination pots of 10 to 12 in. diameter, calcination times should not exceed 24 hours and might be as low as three hours if the pot is kept full. If the pots are fed at a constant rate, the cake might form with a steady state V'' when viewed in vertical section which would progress from bottom to top. Cake deposition rates appear to be independent of pot radius.… more
Date: March 23, 1959
Creator: Whatley, M. E. (Marvin E.), 1926- & Perona, J. J.
Partner: UNT Libraries Government Documents Department
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Temperature Structure in the Gas Cooled Reactor Fuel elements Using a Scalloped Coolant Channel

Description: An analysis of the temperature structure in the GCR2 fuel elements and coolant stream at the position where the maximum fuel element surface temperature exists was presented in a previous paper (CF-58-5-97). It was felt that the peripheral temperature variation existing on the fuel rods as brought out in that analysis was due mainly to the poor flow distribution of the coolant with respect to the heat flux. The most expedient way to alleviate this situation without changing the fuel element ass… more
Date: March 26, 1959
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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HRT Chemical Plant Run 17 Summary

Description: The HRT chemical plant hydro clone loop was operated for 839 hr during reactor run 17 and removed 708 g of corrosion product solids from the reactor fuel stream. The composition of corrosion product solids removed 49% zirconium, 22% iron, and 4% chronicum, markedly different from solids removed during run 16 which analyzed 51% iron, 7$ zirconium, and 5% chromium. The qu8antite of solids removed by the chemical plant was equivalent to approximately 19% of the stainless steel and 2.5% of the zirc… more
Date: March 6, 1959
Creator: Yarbro, O. O.
Partner: UNT Libraries Government Documents Department
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Thermal Stress Analysis of Cylindrical Shells

Description: This report is an extension of the method described in "Stress Analysis of Cylindrical Shells", by F.J. Stanek, ORNL CF 58-9-2 (1958) and this report is written to be used in conjunction with the table in Section 2 of Stanek's work. Part one of this report describes the analysis of a cylindrical shell subjected to a temperature variation in the axial direction. This part is divided into two sections. Section 1 gives the formulas and the procedure for the application. In Section 2, the derivat… more
Date: March 26, 1959
Creator: Witt, F. J.
Partner: UNT Libraries Government Documents Department
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Removal of Fission Products from High Level Radioactive Waste Solutions

Description: Ion exchange, electrolysis, solvent extraction, scavenging and precipitation have been studied as methods for removing radioactive isotopes from high level wastes. Process development has been limited to laboratory research and small scale engineering tests so that the efficiency of these methods in large scale operations is unknown. Emphasis has been placed on removal of Strontium90 and Cesium137 which are the most biologically hazardous of the long lived radioisotopes. Continuous processing o… more
Date: March 30, 1959
Creator: Blanco, R. E. (Raymond Eugene), 1918-1987. & Roberts, J. T.
Partner: UNT Libraries Government Documents Department
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Estimate of the Fast Effect in the Lid Tank Source Plate

Description: An estimate was made of the fast effect in the lid tank source plate. The number of fast fissions per thermal fission is 0.019.
Date: March 31, 1959
Creator: Dresner, Lawrence
Partner: UNT Libraries Government Documents Department
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Trapping of Energetic Ions by Neutralization of a Polarized Beam

Description: Recent experiments show that a positive ion beam with a density exceeding 10/sup 8/ ions/cm/sup 3/ will neutralize its space charge by trapping electrons within the beam. This trapping of electrons converts the ion beam to a neutral plasma suitable for injection and polarization experiments in a cross magnetic field. The ion energy used is about 500 volts. The beam moves readily across the magnetic field due to polarization of positive and negative charges. To create a hot plasma, it will be ne… more
Date: March 17, 1959
Creator: Luce, J. S.
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance Program: Comments by HAPO, dated March 12, 1959, on Questions by E. L. Nicholson

Description: Eurochemic requested information relative to the performance and operation of silver reactors. Mr. W.C. Schmidt of Purox Technology Operation, Chemical Processing Department, HAPO, provided answers to the questions. Also, it is our opinion that serious consideration should be given to radioactive decay as a method of removing significant quantities of radio-iodine. The technology of iodine suppression by chemical means is expensive, complected, and incompletely defined. Although the decay metho… more
Date: March 26, 1959
Creator: Bupp, L. P & Schmidt, W. C.
Partner: UNT Libraries Government Documents Department
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Effects of Fuel Burn-Up on the Dissolution Process-I

Description: Data on the effects of nuclear fuel burnup on dissolution rates and U losses of a few fuel types are summarized. Burnup to the 40% level produced very little effect on the rate of solution of stainless steel-UO/sub 2/ fuel elements in solutions of the Darex type. Beyond passivation, burnup to the 250 Mwd/T level did not produce a large effect on the rate of decladding nor on the U losses in the Sulfex process. Burnup to the 15% or 4300 Mwd/T level produced little or no effect on the rate of dec… more
Date: March 25, 1959
Creator: Davis, W., Jr.
Partner: UNT Libraries Government Documents Department
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Comparison of Two Colorimetric Methods for Uranium

Description: In order to establish the feasibility of using two colorimetric methods for the determination of uranium interchangeably, according to the interferences encountered in a particular sample. Results were obtained by each of the methods and compared. The dibenzoyl methane method and the ethyl acetate-ammonium thiocyanate procedure were compared on the basis of values secured on the same day, on different days, on an analysis of the variance, and on an analysis of the residual error for the methods… more
Date: March 25, 1959
Creator: McCutchen, Roberta L.
Partner: UNT Libraries Government Documents Department
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Spectrophotometry of Molten Fluoride Salts: Status Report

Description: Progress made in the field of spectrophotometry of molten fluoride salts is summarized. The high-temperature cell assembly designed and fabricated for use in this work is described, as well as the various types of sample containers used. Spectra of nickel fluoride, cobalt fluoride, chromic fluoride, and uranium tetrafluoride in LiF--NaF-KF (46.5-11.5--42 mole%) are presented. (auth).
Date: March 25, 1959
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department
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Linear Accelerator for Heavy Ions

Description: The following report discusses the construction of two heavy-ion linear accelerators, one at the the University of California Radiation Laboratory and the other at Yale University. The goal for these accelerators is to produce ions of masses up to that of neon with energies of 10 Mev per nucleon.
Date: March 27, 1959
Creator: Wells, Don
Partner: UNT Libraries Government Documents Department
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