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The FCC Fairness Doctrine

Description: This report discusses two questions: (1) What is the legal basis for the FCC's jurisdictional authority to promulgate the Fairness Doctrine, (2) What is the normal way in which dissatisfied parties may attempt to have a ruling eliminated or amended.
Date: November 3, 1967
Creator: Yadlosky, Elizabeth
Partner: UNT Libraries Government Documents Department
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BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. December 1961, January andFebruary 1962

Description: It has been known for a hundred years that formaldehyde polymerizes to carbohydrate substances in alkaline media. Although the reaction has long attracted much attention, only recently has a detailed qualitative analysis of the products been carried out by chromatographic methods. We have started to re-examine this reaction by combining chromatography with radioactive tracer techniques in the hope of refining the quantitative aspects of the analysis. Our particular interest has been to develop … more
Date: April 3, 1962
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium: Quarterly Report Number 1, September - December 1961

Description: Abstract: "The purpose of this investigation is to determine the extent to which zirconium exhibits delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress. Both notched and unnotched specimens of unalloyed zirconium and Zircaloy-2 are being initially hydrogenated to 200 ppm by means of a modified Sieverts apparatus, and delayed failure studies are proceeding at room-temperature. Thus far only preliminary data on unnotched, unalloyed zirconium are ava… more
Date: January 3, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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The Escape of Fission Products From an Uranium Rod; Application to the B. N. L. Reactor

Description: Technical report covering the functions of the Oak Ridge reactor, difficulties encountered with cartridge failures in the Oak Ridge reactor, and possible solutions including the incorporation of leak detection systems into the design of the reactor.
Date: November 3, 1968
Creator: Chernick, J. & Kaplan, I.
Partner: UNT Libraries Government Documents Department
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SNAP re-entry orbit; comments on the atmospheric entry and discussion of a proposed test

Description: In order to evaluate entry into the atmosphere of an oblate (equatorial bulge) earth a standard atmosphere was used in conjunction with the standard rotating oblate spheroid. The density variation encountered in any one polar orbit around the earth will vary by about a factor of ten, due to oblateness. Therefore, the important effects on the re-entry trajectory are atmospheric density and oblateness of the earth. The SNAP configuration burn up characteristics will differ considerably between th… more
Date: August 3, 1962
Creator: Ackermann, W. O.; Arthur, P. D. & Nelson, D. K.
Partner: UNT Libraries Government Documents Department
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Effect of S8DR chromium diffusion treatment on the creep rupture properties of processed Hastelloy-N tubing

Description: Process development personnel have been seeking means of improving the (after thermal exposure) adhesion of the S8DR ceramic coating to chromized Hastelloy N tubing. This effort has led to the incorporation of an elevated temperature chromium diffusion treatment prior to the application of the ceramic coating. This report describes the results of tests performed to ascertain the influence of the additional thermal treatment on the 1400/sup 0/F creep-rupture properties of S8DR tubing.
Date: June 3, 1967
Creator: Allaria, G.G.
Partner: UNT Libraries Government Documents Department
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Savannah River Plant 200 Area technical manual. Part SP. Processing of Np/sup 237/ and Pu/sup 238/

Description: This manual covers the technology involved in the 200 Area process for the recovery of Np/sup 237/ from certain aqueous waste streams in the separations plants, for the recovery of NP/sup 237/ and Pu/sup 238/ from irradiated NpO/sub 2/-Al slugs and for the fabrication of NpO/sub 2/-Al slugs. The manual contains sections on the fundamental chemistry, the primary recovery of Np by ion exchange, the decontamination of Np by ion exchange, the processing of NpO/sub 2/-Al targets, the separation and … more
Date: January 3, 1963
Creator: Hill, A.J. (comp.)
Partner: UNT Libraries Government Documents Department
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Electromotive Force of Transfer Systems Containing Membranes

Description: Report describes a few experiments designed to test the analysis of some systems where chemical energy can be converted to electric energy. From Abstract: "If a chemocouple is defined as an isothermal closed circuit, composed of two or more homogeneous ionic aqueous phases separated by two or more barriers of different sets of ionic transport numbers, we find that a spontaneous electric current flows in the closed circuit."
Date: March 3, 1962
Creator: Nime, Leslie F. & Kuo, Jean
Partner: UNT Libraries Government Documents Department
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Status of plant assistance irradiations as of July 16, 1965

Description: This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of materials undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, {open_quotes}Status Report Equations.{close_quotes} The integrated exposure reported is the average exposure received by the surrounding uranium columns. … more
Date: August 3, 1965
Creator: Ferguson, J. H.
Partner: UNT Libraries Government Documents Department
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Fast Neutron Fluxes in Hanford Reactors

Description: The results of a multi-group, diffusion type code computation for the fast neutron flux distribution in C, K, and N reactors are presented. Relative Ni activations in conjunction with the calculated neutron spectra are used to obtain values for the integrated fast flux per MWD/AT for C and K reactors. The relative, theoretical, integrated fast flux values at the same adjacent fuel powers in C, K, and N reactors in the mid-plane of the filler layers are: (1) C = 1.0; (2) K = 1.3; and (3) N = 2.6… more
Date: May 3, 1960
Creator: Yoshikawa, H. H.
Partner: UNT Libraries Government Documents Department
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Hanford Production cut-back studies

Description: This report provides a compilation of memorandums and studies related to a Hanford production cut-back.
Date: February 3, 1969
Creator: Chapman, V. R.
Partner: UNT Libraries Government Documents Department
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Summary of KER-1 operation, February 15, 1958--March 1, 1960

Description: Recent borescoping of the KER-1 tube revealed several scratches, pits, and gall marks on the internal wall of the tube. These deformations could limit the operating temperature and pressure of KER-1. This report is a summary of operating history and is compiles to assist in determining what contributed to the condition of the tube.
Date: March 3, 1960
Creator: Buckner, C. L.
Partner: UNT Libraries Government Documents Department
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Effect of process tube dimensions on tube life

Description: In recent months, several process tubes installed during 1961 have been removed and examined out-of-pile in connection with Tube Corrosion Monitor Studies.1 Most of the tubes were believed to be uniform-wall .080in.-nominal-rib-height tubes. The ex-reactor dimensional measurements obtained near the inlet flange showed,that the tubes did not have uniform walls or .08011 nominal rib heights. Subsequently, dimensional measurements were obtained on approximately 200 new process tubes in an effort t… more
Date: December 3, 1962
Creator: Hough, C. G.; Fuller, N. E. & Jensen, R. D.
Partner: UNT Libraries Government Documents Department
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Effects of Hanford Operations on Columbia River temperatures: Interim report No. 2

Description: A research and development project for study of the effects of reactor effluent on Columbia River water quality is being sponsored by the AEC Division of Production. Work was started in October 1962, the first effort being aimed at furnishing an immediate answer to a security question: how closely can Hanford production be estimated by measurement of river temperatures? An interim progress report gave the results of the preliminary investigation. During the calendar year 1963, the study was exp… more
Date: December 3, 1964
Creator: Corley, J. P.
Partner: UNT Libraries Government Documents Department
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Flowsheet for americium recovery and purification

Description: Americium (atomic weight 241) grows into plutonium as a result of the 13-year half-life beta decay of Pu{sup 241}. An appreciable quantity of Am{sup 241} has.grown into the scrap that accumulated following shut-down of the Recuplex facility, and which will be processed during the initial period of operation of the plutonium reclamation facility. Current interests in trans-plutonium research and in isotopic heat sources make it desirable to consider the recovery of this Am{sup 241}. The americiu… more
Date: September 3, 1963
Creator: Szulinski, M. J. & Curtis, M. H.
Partner: UNT Libraries Government Documents Department
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241-SX tank farm waste storage

Description: Salt wastes from the Redox solvent extraction process have been routed to the 241-SX tank farm for storage since May 21, 1954. Tanks in this farm contain wastes from three types of irradiated uranium processing: (1) low (approximately 250 MWD/T) and (2) high (approximately 600 MWD/T) natural uranium; and (3) E-metal. It is estimated that approximately 1.6 Kgs of Am-Cm, 17 Kgs of Np-237, 20 Kgs of Pu and 8 tons of uranium are present in the sludges from wastes generated through 4-30-64. A total … more
Date: September 3, 1964
Creator: Hanson, G. L.
Partner: UNT Libraries Government Documents Department
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Final report B, D, F reactor side shield hole boring technology

Description: Four years of intermittent development has culminated in the successful test drilling on-reactor, of one step plug hole. Since 1960, several different drive units and many diamond, carbide, and tool steel cutting heads were tried unsuccessfully in attempts to bore a stepped hole in a mockup of B, D, P side shielding. Success was finally achieved in 1963 using a standard horizontal boring mill and tool steel cutters. With slight modifications, this same equipment was successfully used in an on-r… more
Date: February 3, 1964
Creator: Clemans, W. H.
Partner: UNT Libraries Government Documents Department
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Proposal for the Irradiation of Cladding Studies Capsules, Series 2

Description: Localized cladding instability or necking has resulted in failures of the Zr-2 cladding of rod cluster and tubular fuel elements and fuel rods in NaK filled capsules. The cause of this non-uniform cladding strain is thought to be a combination of the effects of irradiation and nonuniform cladding thickness. To determine the influence of these two factors and that of temperature on the susceptibility to failure, and to obtain data related to cladding thickness tolerances for the NPR fuel element… more
Date: May 3, 1962
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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In-reactor rupture testing of Zircaloy-2 clad seven-rod cluster fuel elements: Interim report

Description: The high pressure loop installed in the 3X3 reflector position of the ETR and the associated instrumentation to detect and study failure mechanisms handled the rupture tests without difficulty. Failure of the elements was initiated by shearing off a projection on the fuel elements. The first test of the series used previously unirradiated seven-rod clusters. After the projection was sheared off the fuel elements were operated for seven hours with no failure. Failure is defined as having occurre… more
Date: May 3, 1960
Creator: Call, R. L.; Green, J. W. & Kaulitz, D. C.
Partner: UNT Libraries Government Documents Department
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Re-evaluation of metal performance levels of C-II-N and C-II-E material

Description: This report presents an analysis of rupture experience at C Reactor over the past two years. The purpose of the study was to provide a basis for revising, if necessary, the current metal performance level multipliers for C-II-N and C-II-E material.
Date: March 3, 1961
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Measured cadmium burnup in C reactor HCR`s

Description: C Reactor horizontal control rods were originally designed to have 32 feet of poison, made of 64 six inch ``cans`` each consisting of two concentric cylinders sealed at each end and the annular space between them filled with boron carbide powder. It was discovered before startup that under irradiation the neutron, alpha reaction in the boron could cause a pressure buildup and rupture of the sealed section. As an expediency cylinders wrapped with 72 miles thick cadmium metal were substituted for… more
Date: May 3, 1961
Creator: Chitwood, R. A.
Partner: UNT Libraries Government Documents Department
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