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Loading and operating conditions for NIN-1 and NIE-1 elements in the KER loops under PT-IP-377-A

Description: This document provides the loading and operating conditions for eight 16-inch or five 24-inch elements, either natural NIN-1 or .947% enriched NIE-1, in any of the four KER loops. The loadings are tabulated; operating conditions for either charge in KER 2, 3, 4, or 1 are given in figures.
Date: December 23, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Scope report Safety Circuit Trip Identification System

Description: The purpose of this report is to establish the scope of a project to provide a system which will quickly and accurately identify the sources of all reactor scrams.
Date: March 23, 1960
Creator: Deichman, J. L.
Partner: UNT Libraries Government Documents Department
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Anticipated power generation rates for NAA-111 fuel plates

Description: Three fuel element assemblies, each containing U-Mo fuel plates, will be irradiated in a side test hole at KE-Reactor. This document presents efforts made to determine the heat generation rate of the fuel plates from data from a capsule mockup irradiation in HTR.
Date: November 23, 1960
Creator: Franklin, F. C.
Partner: UNT Libraries Government Documents Department
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Vapor Pressures of the Rare Earths

Description: Abstract: This report presents the vapor pressures versus temperature data graphically for the rare earth elements, yttrium and scandium.
Date: December 23, 1960
Creator: Beavis, L. C.
Partner: UNT Libraries Government Documents Department
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Analysis of quality certification data: WARP, TFC and delta OD{sub 2} as a function of reactor operating conditions

Description: This report is the second in a series on the definition of performance of irradiated fuel elements as measured by the Quality Certification Program. Objectives of this analysis are to establish empirical mathematical relations which fit observed data from > 2000 fuel elements measurements for WARP, TFC, and DELTA OD{sub 2}, as a function of reactor conditions (power, surface temperature, time).
Date: November 23, 1960
Creator: Hagie, L. T. & Jaech, J. L.
Partner: UNT Libraries Government Documents Department
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An evaluation of five possible HCR sleeve materials for K Reactor

Description: The graphite stacks of the K reactors have been distorted to the extent that steel balls from the ball 3X system have entered some of the horizontal control rod channels and have interferred with the proper operation of the control system. One possible method of eliminating this potential hazard and attendant recurring production loss would be to place stationary sleeves around the horizontal control rods. Liners or sleeves in the vertical-ball and rod channels would prevent future leakage of b… more
Date: November 23, 1960
Creator: Bunch, W. L. & Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Summary of Progress on the Study of Beta Treatment of Uranium, November 1, 1959-August 31, 1960

Description: Variables affecting the texture and grain size of uranium during beta treatment are summarized. The study of the effect of time and temperature in the beta phase on the growth index (G3) and grain size of the final alpha product is tentatively believed to show that higher beta temperatures for short times (up to about seven minutes) tend to promote slightly more negative growth indices and that higher beta temperatures give rise to somewhat finer grain sizes. Results of studies of both Jominy e… more
Date: September 23, 1960
Creator: Russell, R.B.
Partner: UNT Libraries Government Documents Department
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Thermal and Total Epithermal Neutron Flux Distributions in the Experimental Gas Cooled Reactor

Description: The thermal and total epithermal neutron flux distributions in the EGCR from the center of the core through the biological shield were calculated. The maximum values of the flux distribution are presented in graph form. Ordinary concrete was found to permit a thermal flux buildup, similar to that found in the graphite reflector. In heavy concrete there was no such buildup seen, since the thermal flux is attenuated through the complete shield. A Val Prod code using multigroup diffusion theory wa… more
Date: February 23, 1960
Creator: Wagner, E.
Partner: UNT Libraries Government Documents Department
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High-Temperature Irradiation of Metals and Graphite in Flowing Helium

Description: As part of the coolant-core evaluation studies in an early phase of the Maritime Gas-Cooled Reactor program, nickel. K-Monel, niobium-1 wt.% zirconium, and graphite were irradiated in a convective flow of helium. A capsule of novel design was used to study the corrosion of the metals at 1500 and 960 ction prod- F in a 243-hr BRR experiment. Four heliumfilled quartz tori, containing the specimens, were encapsulated in a stainless steel capsule. A convective flow of helium was maintained in the c… more
Date: February 23, 1960
Creator: Miller, N. E.; Hamman, D. J.; Diethorn, W. S. & Goldthwaite, W. H.
Partner: UNT Libraries Government Documents Department
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Radioactive Fallout From Nuclear Explosions

Description: A nontechnical description of the mechanisms of local and world-wide fall-out from nuclear explosions is given. The relative importance of local fall-out in a nuclear war is discussed. The effects upon man of world-wide fall-out from past nuclear testing is discussed. It is pointed out that doses to man frcm testing are quite small when compared to the natural radiation background. (auth)
Date: March 23, 1960
Creator: Parker, E.N.
Partner: UNT Libraries Government Documents Department
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THE OXIDATION OF CHROMIUM(III) TO CHROMIUM(VI) IN THE PRESENCE OF PLATINUM METALS

Description: BS>Ruthenium, either as soluble salts, powdered metal, or oxide, catalyzed the oxidation of Cr(III) to Cr(VI) in dilute oxygenated sulfuric acid solutions. Under the same conditions, in the absence of ruthenium, Cr(Vl) was not produced. In a 2 M Al(NO/sub 3/)/sub 3/-1 M HNO/sub 3/ solution at atmospheric boiling point, ruthenium and compounds of ruthenium, platinum, palladium, rhodium, and osmium very markedly increased the rate at which Cr(III) was oxidized to Cr(VI). Very low concentrations o… more
Date: May 23, 1960
Creator: Wisdom, N E; Greeley, R S & Griess, J C
Partner: UNT Libraries Government Documents Department
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DESIGN STUDIES ON CESIUM-137 AS A SOURCE FOR HIGH LEVEL GAMMA IRRADIATORS. Quarterly Progress Report No. 3 Covering the Period from December 1, 1959 to March 1, 1960

Description: Experiments were carried out on a Cs/sup 137/ plaque source of 40 x 40 x 1/2 inches. Measurements were made of dose distributions in water and of photon spectral distributions in paraffin. For 9-inch-thick water siab absorbers without air gaps, it was found from the preliminary experiments that the depth dose uniformity can be varied over the range 1.10 to 1.40. The absolute dose rates found were in general agreement with design predictions which indicate irradiator efficiencies in the region o… more
Date: March 23, 1960
Creator: Voyvodie, L.
Partner: UNT Libraries Government Documents Department
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Experimental Gas Cooled Reactor-Creep Test, Agot Graphite

Description: Tests were conducted to determine the cumulative and permanent deflection of a beam subjected to two-point loading for (1) ambient temperature- atmospheric environment, and (2) 800 deg F-atmospheric environment, for 8OO psi maximum flexural stresses. Deflection curves are given for five specimens. An analysis of the data indicated that if the core graphite creeps while at EGCR conditions by approximately 1.5 times its creep rate at ambient temperature, the stresses will level off below 1000 psi… more
Date: August 23, 1960
Creator: Lain, P. J.
Partner: UNT Libraries Government Documents Department
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OPERATING MANUAL FOR THE AE-6 REACTOR

Description: An attempt is made to provide a single reference source for material pertinent to the maintenance and operation of the AE-6 Reactor. Descriptions of various components are included, as well as the common operational and maintenance procedures and check lists. Information is given on the subcritical assemblies that may be studied. (W.D.M.)
Date: June 23, 1960
Creator: Moore, E.A. Jr.
Partner: UNT Libraries Government Documents Department
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SM-2 Clutch Testing

Description: The criteria and methods for test evaluation of electromagnetic clutch characteristics are discussed. An evaluation of the relative merits of two commercial clutches, both of the multiple disk friction type, is presented with test results. One of these clutches was incorporated in the clutch assembly design for the Array Reactor (SM-2). (auth)
Date: March 23, 1960
Creator: Hauenstein, G. C.
Partner: UNT Libraries Government Documents Department
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Measuring Reactor Neutron Spectra with Threshold Detectors

Description: The use of threshold detector foils to measure the external neutron spectrum of two reactors is described. The foils employed are Pu236 to measure the total fast flux, U238 for the region above 1.5 Mev, S32 above 2.5 Mev, and Au197 for thermal neutrons. Scintillation counters ae used to determine the activity induce din the detectors. The foil-counting system is calibrated by used a Cockcroft-Walton accelerator as a fast neutron source. The results indicate a fission type spectrum at each react… more
Date: September 23, 1960
Creator: Grader, Roderick J.
Partner: UNT Libraries Government Documents Department
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A Mathematical and Statistical Approach to the Design and Analysis of a Reactor Containment Vessel Pressure Test

Description: This report discusses the mathematical and statistical questions concerned with the estimation of a leak rate from data collected during a reactor containment vessel pressure test such as that performed on the PRTR vessel in May, 1959. A mathematical method is suggested in Section 3 for the construction of a total number of gas molecules in the containment vessel time series using vessel absolute pressure and temperature readings at several positions within the vessel. A formula for the precisi… more
Date: March 23, 1960
Creator: Nicholson, W. L.
Partner: UNT Libraries Government Documents Department
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Volatilization of Cesium During Calcination and Hydrolysis of Cs2ZnFe(CN)6 Precipitates

Description: The feasibility of removing and recovering cesium-137 from various HAPO process solutions by precipitation of Cs2ZnFe(CN)6 has been demonstrated previously. Pilot plant studies of calcination and steam hydrolysis of non-radioactive Cs2ZnFe(CN)6 precipitates by members of the Process Equipment Development Operation are currently in progress. In support of these pilot plant studies, experiments were performed to determine the extent, if any, to which cesium volatilizes during calcination and hydr… more
Date: March 23, 1960
Creator: Bouse, Donald G. & Schulz, Wallace W.
Partner: UNT Libraries Government Documents Department
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Use of the DD2 Amplifier with the RIDL 200-and 400-Channel Analyzers

Description: The use of the DD^3 amplifier with the RIDL 200- and 400-channel analyzers has been found advantageous for certain applications. In order to use the DD2, certain modifications to the input circuits of the Analog-to Digital Converter Unit are necessary. In addition, the modifications improved the linearity of the analyzer in the low channels. Using the analyzer with the RIDL Type 30-7 Scintillation Pulse Amplifier, it was noted that non-linearity of as much as 5 or 6 channels was present below c… more
Date: September 23, 1960
Creator: Todd, H. A. & Smiddle, R. D.
Partner: UNT Libraries Government Documents Department
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Low Energy Nuclear Physics : Second Annual Report for the Period February 1, 1959 to January 31, 1960

Description: The general expression for the angular correlation between radiations produced in successive cascade transitions is derived by use of Racah algebra. The result is then specialized to the beta - gamma correlation and applied to two cases in which additional properties of the photon are specified, the circular polarization and the plane polarization. The prospect of testing time reversal and determining nuclear matrix element ratios by beta - gamma correlation measurements is explored using the n… more
Date: January 23, 1960
Creator: Jastram, Philip S. (Philip Sheldon), 1920-1992
Partner: UNT Libraries Government Documents Department
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