Aluminum testing in KER loop 3 from May 23, 1959 to July 26, 1959 (open access)

Aluminum testing in KER loop 3 from May 23, 1959 to July 26, 1959

None
Date: September 1, 1959
Creator: Jackson, M. E.
Object Type: Report
System: The UNT Digital Library
Argonne Cancer Research Hospital Semiannual Report on Medical Research to the Atomic Energy Commission (open access)

Argonne Cancer Research Hospital Semiannual Report on Medical Research to the Atomic Energy Commission

Progress is reported in the following studies: carbohydrate metabolism in human erythrocytes; the development of a system of electron therapy employing a linear electron accelerator and an electromagnetic beann deflector; the capacity of progesterone to inhibit the sodium-retaining influence of aldosterone and desoxycorticosterone; use of tritium-labeled cholesterol in measuring the lability of cholesterol in human atherosclerotic plaques; the capacity of a number of steroid hormone metabelites to provoke fever in man; the failure of human placental tissue homogenates to convent progesterone to estrogens; and tracer studies on enzyme requirements for the incorporation of cytidine triphosphate into ribonucleic acid in a mammalian system. (L.H.)
Date: September 1, 1959
Creator: Jacobson, Leon O.
Object Type: Report
System: The UNT Digital Library
Atmospheric Turbulence (open access)

Atmospheric Turbulence

Some characteristics of turbulence near the ground can begin to be interpreted There is yet little information about others (even near the ground) such as spectra measured along the vertical lines, or cross spectra between two variables. Further, results of turbulence characteristics over water are few and confusing, and no information exists about the effects of cities and deserts. As we go aloft, our information about spectra becomes more scanty, although the general areas of large turbulence intensity are fairly well known (auth)
Date: September 1, 1959
Creator: Panofsky, H. A.
Object Type: Report
System: The UNT Digital Library
Bibliography on General Test Reactors (open access)

Bibliography on General Test Reactors

Bibliographies on the MTR ETR, G. E. Materials Testing Reactor, Vallecitos Boiling Water Reactor, and Westinghouse Testing Reactor are presented. In addition, bibliographies of miscellaneous reactors and inpile loops are included. Sources used are Engineering Index, 1951 to 1958, Industrial Arts Indes. 1951 to July 1959, and Nuclear Science Abstracts, 1948 to August 15, 1959. (J.R.D.)
Date: September 1, 1959
Creator: Duke, D. M.
Object Type: Report
System: The UNT Digital Library
Biological Blast Effects (open access)

Biological Blast Effects

The scope and nature of several blast hazards are delineated. Tentative criteria are set forth for threshold damage to humans. These criteria are related 10 nuclear weapons in terms of ground ranges and areas involved for one MT and ten MT surface detonations. To allow appreciation of the relative importance of blast with other effects, appropriate values are noted for ionizing and thermal radiation. Four categories of blast hazards are defined, and the character of each is described. The occurrence of combined injuries from pressure, missiles, and displacement is discussed. Experiences in the Texas City disaster of 1947 are reviewed. Selected data relate environmental conditions to gross biologic damage from overpressures, missiles, and impact loading. 86 references. (C.H.)
Date: September 1, 1959
Creator: White, C. S.
Object Type: Report
System: The UNT Digital Library
CALCULATION OF THE TEMPERATURE DEPENDENCE OF Pu$sup 239$/U$sup 235$ FISSION RATIO FOR A GRAPHITE-U$sup 235$ SYSTEM (open access)

CALCULATION OF THE TEMPERATURE DEPENDENCE OF Pu$sup 239$/U$sup 235$ FISSION RATIO FOR A GRAPHITE-U$sup 235$ SYSTEM

None
Date: September 1, 1959
Creator: Meneghetti, D. & Phillips, K.E.
Object Type: Report
System: The UNT Digital Library
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR APRIL, MAY, JUNE 1959 (open access)

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR APRIL, MAY, JUNE 1959

Chemical-Metallurgical Processing. A direct-cycle Pyrometallurgical fuel-reprocessing plant is being designed in conjunction with the EBR-II reactor. Studies were continued on processing of melt-refining residues (crucible skull material). Skull oxlde reductions in Mg--Cd solutions are in progress. Methods of isolation of Pu from EBR-II bIanket material are being examined. Cadmium contafntng ~2% U and 0.2% Mg is betng circulated at 550 deg C by an electromagnetic pump. Solubilities of Ru, Ce, and La in Cd were measured at temperatures from 325 to 625 deg C; the solubility of U fn Zn was measured at temperatures from 425 to 800 deg . The high-Cd covers of the termary systems Cd-- U--Zn amd Cd--U-- Mg were investigated. Sixteen colorimetric combustions in oxygen were completed with natural MoS/sub 2/. Eight successful colorimetric combustions of Mo in F/sub 2/ were completed. Fuel Cycle Application of Volatility and Fluidization Techniques. Studies on the rates of fluorination of UO/sub 2/, as ft would appear in irradiated fuels, are in progress. Equilibrium constants are being obtained at various temperatures for the dissociation reaction of PuF/sub 6/ to F/sub 2/ and PuF/sub 4/. A systematic study of the reaction of Ni with F/sub 2/ is in progress as a …
Date: September 1, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Chemical Technology Division, Chemical Development, Section C, Monthly Progress Report, August 1959 (open access)

Chemical Technology Division, Chemical Development, Section C, Monthly Progress Report, August 1959

The solvent extraction of U from carbonate solutions was studied. The prevention of silica staabilized emulsions in the Amex and Dapex processes by solventcontinuous mixing is reported. The recovery of U and Pu from H/sub 2/SO/ sub 4/ decladding solutions by continuous countercurrent extraction with primary amines, HNO/sub 3/ stripping from primary amine, U/sup 6+/ extraction by primary amine, and U extraction by dialkylphosphoric acid is being studied. Plutonium was effectively freed from Am contamination by extraction from 2 M HNO/sub 3/ with 0.1 M di(2-ethylhexyl)phosphoric acid. ( For preceding period see CF-59-7- 68), (W.L.H.)
Date: September 1, 1959
Creator: Brown, K. B.; Allen, K. A.; Coleman, C. F.; Crouse, D. J. & Ryon, A. D.
Object Type: Report
System: The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report for June 1959 (open access)

Chemical Technology Division, Unit Operations Section Monthly Progress Report for June 1959

The addition of a surface active agent to an aqueousorganic interface produced a resistance to mass transfer equivalent to slightly more than 1 cm of water. Five semicontinuous Druhm runs were made with 1/2-in. thick MgO liners and terminated due to either failures of the UF/sub 6/ nozzle or a top gasket leak. In preliminary scale-up tests of the flame calcination equipment, a maximum feed rate equivalent to 720 g oxides/hr was achieved using a 3-in. i.d. magnesia reflector with an outside wall temperature of 1500 ction prod- C. In a test with a light water feed, 99% Cu, 25% Ni, and 0% Mn were removed from a UO/ sub 2/SO/sub 4/ solution by electrolysis with a mercury cathode in 7800 ampere hours. The effect of varying the total sulfate concentration on the kinetics of the absorption of uranyl sulfate on Dowex 21K at a uranium concentration of 0.005779 M and a sulfuric acid concentration of 0.020 M was studied in a series of runs using a stirred bath containing enriched uranium. Chloride was removed to 64 ppm in Yankee Atomic and to 70 ppm in APPR solvent extraction feeds using a reference Darex flowsheet with air sparging during a …
Date: September 1, 1959
Creator: Bresee, J. C.; Haas, P. A.; Watson, C. D.; Whatley, M. E. & Horton, R. W.
Object Type: Report
System: The UNT Digital Library
Civilian Power Program. Part 1, Summary, Current Status of Reactor Concepts (open access)

Civilian Power Program. Part 1, Summary, Current Status of Reactor Concepts

This study group covered the following: delineation of the specific objectives of the overall US AEC civilian power reactor program, technical objectives of each reactor concept, preparation of a chronological development program for each reactor concept, evaluation of the economic potential of each reactor type, a program to encourage the the development, and yardsticks for measuring the development. Results were used for policy review by AEC, program direction, authorization and appropriation requests, etc. This evaluation encompassed civilian power reactors rated at 25 MW(e) or larger and related experimental facilities and R&D. This Part I summarizes the significant results of the comprehensive effort to determine the current technical and economic status for each reactor concept; it is based on the 8 individual technical status reports (Part III).
Date: September 1, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
DISSOLUTION OF ZIRCONIUM AND ZIRCALOY-2 IN NITRIC-HYDROFLUORIC ACID MIXTURES AT REFLUX TEMPERATURES (open access)

DISSOLUTION OF ZIRCONIUM AND ZIRCALOY-2 IN NITRIC-HYDROFLUORIC ACID MIXTURES AT REFLUX TEMPERATURES

BS>The initial rate constants were obtained for zirconium and Zircaloy-2 dissolution at reflux temperatures in nltric--hydrofluoric acid mlxtures. Variation of the nitric acid concentration in these solutions had very little effect on the initial dissolution rate, except for the change in the reflux temperature. The nitric acid concentration exhibited an appreciable effect on the average dissolution rate over longer periods of time. An empirical treatment of the rates over extended periods is presented. The maximum attainable rates for zirconium dissolution, adjusted to an initial lM hydrofluoric acid concentration, were determined at lower temperatures. Stability of resultant Zircaloy-2 dissolver solutions is reported for both nitric--hydrofluoric acid mixtures and nitric--oxalic--hydrofluoric acid mixtures. Possible reactions and some analyses of off-gases from these dissolutions are given. (auth)
Date: September 1, 1959
Creator: Vander Wall, E.M. & Whitener, E.M.f Bauer, D.L.
Object Type: Report
System: The UNT Digital Library
Experimental Determination of the Pressure Drop Through a Pebble Bed (open access)

Experimental Determination of the Pressure Drop Through a Pebble Bed

The pressure drop associated with the flow of air through a cylindrical bed of spherical pebbles has been investigated experimentally. The results of this investigation are reported here. (auth)
Date: September 1, 1959
Creator: Randall, D. E. & Millwright, S. S.
Object Type: Report
System: The UNT Digital Library
GAS-COOLED REACTORS BIBLIOGRAPHY (open access)

GAS-COOLED REACTORS BIBLIOGRAPHY

A compilation of 517 references to the unclassified literature to May 1959 on gas-cooled reactors is presented. It includes articles, reports, books, and patents, Reactors cooled by air are included, as well as all types of reactors by function--power reactors, research reactors, design studies, and prototypes. (W.D.M.)
Date: September 1, 1959
Creator: Richardson, W.H. & Strachwitz, F. comps.
Object Type: Report
System: The UNT Digital Library
GRAPHS OF THE HYPERGEOMETRIC O.C. AND A.O.Q. FUNCTIONS FOR LOT SIZES 10 TO 225 (open access)

GRAPHS OF THE HYPERGEOMETRIC O.C. AND A.O.Q. FUNCTIONS FOR LOT SIZES 10 TO 225

Graphs of the hypergeometric operating characteristic (O.C) and average outgoing quality (A.O.Q.) functions are given for lot sizes 10 to 225 and various sample sizes. Graphs for acceptance numbers O(1)2 and 0(1)3 are included. (auth)
Date: September 1, 1959
Creator: Clark, C. R. & Koopmans, L. H.
Object Type: Report
System: The UNT Digital Library
Heat-transfer studies (open access)

Heat-transfer studies

None
Date: September 1, 1959
Creator: Core, T. C.; Harkee, J. F.; Misra, B. & Sato, K.
Object Type: Report
System: The UNT Digital Library
An Improved Gamma Detector Using Gamma Moderation (open access)

An Improved Gamma Detector Using Gamma Moderation

Theoretical and experimental results of the effect of gamma moderation are described. A 6.7-fold enhancement factor was obtained with a 1/8-in-thick sodiumiodide crystal when using gamma moderation and a Co/sup 60/ gamma source. A counter was designed and built to make the most use of gamma moderation The results indicate that this counter can be made energy independent over a wide region Though the cost of the counter is about 1/3 that of a 1-in-diam,, 1-in- thick sodiumiodide crystal plus photomultiplier, the counting efficiency for gammas such as Na/sup 24/ is over two times greater. (auth)
Date: September 1, 1959
Creator: Fox, R.
Object Type: Report
System: The UNT Digital Library
The Internal Environment of Underground Structures Subjected to Nuclear Blast. Ii. Effects on Mice Located in Heavy Concrete Shelters (open access)

The Internal Environment of Underground Structures Subjected to Nuclear Blast. Ii. Effects on Mice Located in Heavy Concrete Shelters

A cage containing 20 mice was placed in each of 12 underground shelters in an attempt to assess biologically the inside environment of the shelters. Two samples of 20 mice each acted as controls. The structures, of French and German design, were located at ranges between 840 ft and 4320 ft from Ground Zero. A nuclear device was exploded atop a 700-ft tower and had a yield of 43 kt. All but one group of mice were recovered on D + 2 days. Aside from two samples placed in unrealistic locations, all animals were alive at recovery. With one exception, the peak pressures in the chambers that contained mice were insignificant, ranging from a fraction of 1 psi to 1.6 psi. The one high pressure of 14.4 psi did not kill any of the mice. According to the film-badge dosimeters, one group of mice received 190 r of gamma radiation. The others were exposed to 54 r of gamma or less. The mice were observed for a 60-day postshot period. The deaths that occurred were attributed to a Salmonella infection in the animal colony and not to radiation. Although the gamma radiation doses that most of the animal groups received …
Date: September 1, 1959
Creator: Richmond, D. R.; White, C. S.; Sanchez, R. T. & Sherping, F.
Object Type: Report
System: The UNT Digital Library
Investigation of Graphite Bodies. Progress Report No. 4 for Period June 1, 1959 to August 31, 1959 (open access)

Investigation of Graphite Bodies. Progress Report No. 4 for Period June 1, 1959 to August 31, 1959

Preliminary data are presented illustrating the properties of molded multicrystalline graphite made using calcined petroleum coke (in some instances mixed with a thermal carbon) bonded with coal tar pitch, furfuryl alcohol, or limited mixtures of the two. No conclusions have yet been drawn regarding the relation between these properties, since a large number of specimens remain to be measured. Most obvious is the difficulty of achieving a sound structure from bodies of maximum green density, particularly when the binder is not thermoplastic. Graphitized specimens made with furfuryl alcohol reflect the high density of the binder coke. Xray data show that this coke is poorly graphitizable as compared to pitch; modulus and electrical resistance data show it to be more dense. A full description of the use of differential thermal analysis and dilatometry in investigating the behavior of thermosetting resins is appended. For preceding period see ARF-6039-3. (auth)
Date: September 1, 1959
Creator: Bradstreet, S.W.
Object Type: Report
System: The UNT Digital Library
KER loop 2 operating report (open access)

KER loop 2 operating report

None
Date: September 1, 1959
Creator: Small, T. A.
Object Type: Report
System: The UNT Digital Library
KER Loop I operating report -- A report on the irradiation of zircaloy-2 jacketed tube-and-tube elements in KER Loop I (open access)

KER Loop I operating report -- A report on the irradiation of zircaloy-2 jacketed tube-and-tube elements in KER Loop I

The objective of this test was to determine the in-reactor performance of co-extruded Zr-2 jacketed tube-and-tube elements. The effect of power, surface temperature, and uranium alloying on dimensional stability and uranium swelling and cracking was to be measured. The charge consisted of two unalloyed tube-and-tube elements, which were Zr-2 jacketed and were 36 inches in length. The rest of the charge consisted of spacer material and coupon holders. The test started on 6-29-59 and ran for a period of 32 days. On 7-30-59, the delayed neutron monitor reading and loop activities increased to a point that required reactor shutdown scram. The reactor was shut down, and the fuel elements were discharged. Loop water samples were analyzed for fission products. Evidence was found of high activity of Iodine isotopes of very short half-life. There was also some indication of other fission products. Visual inspection of the fuel elements after discharge disclosed small wrinkles on the jacket surface of the two unalloyed elements.
Date: September 1, 1959
Creator: Eikum, L. M.
Object Type: Report
System: The UNT Digital Library
The Lifetime and Decay Modes of Negative K Mesons (open access)

The Lifetime and Decay Modes of Negative K Mesons

None
Date: September 1, 1959
Creator: Nickols, Norris A.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
NUCLEAR TRAINING REACTOR. Preliminary Report and Hazards Analysis (open access)

NUCLEAR TRAINING REACTOR. Preliminary Report and Hazards Analysis

Complete descriptions of the reactor, building, and site are given. Reactor operation, bazards associated with the reactor, and the maximum credible accident are discussed. The reactor is a BSR swimming pool type with a design power level of 10 kw and a maximum thermal flux in the fuel region of 2.23 x 10/ sup 11/ n/cm/sup 2/-sec. (W.D.M.)
Date: September 1, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
OXIDATION OF ZIRCONIUM AND ZIRCONIUM ALLOYS (open access)

OXIDATION OF ZIRCONIUM AND ZIRCONIUM ALLOYS

Zirconium oxidation was investigaied in the temperature range 400 io 900 deg C at oxygen pressures of 50, 200, and 800 mm. The reaction rate of massive (parallelepiped) samples was best expressed by the cubic rate law. At an oxygen pressure of 200 mm the activation energy was calculated to be 42.7 kcal per mole, and the cubic rate constant in ( mu g per sq cm) per minute can be expressed as k = (5.94 x 10/sup 16/)e/sup -42//sup ,70//sup 0//< sR>s/sup T/. The oxidaiion rate was found to be relatively insensitive to various types of surface preparations in ihe temperature range 400 to 700 deg C. No dependence of reaction rate on oxygen pressure was observed. The cubic rate law also was obeyed by foil specimens at 700 deg C; however, the rate constants were slightly larger than values obtained from parallelepiped samples. The oxidations of zirconium binary alloys containing nominally one, two, and four atom% additives of aluminum, beryllium, carbon, chromium, cobalt, copper, hafnium, iron, lead, molybdenum, nickel, niobium, platinum, silicon, tantalum, tin, titanium, tungsten, uranium, and vanadium were studied at 700 deg C and 200 mm oxygen. The alloys were grouped according to four types of …
Date: September 1, 1959
Creator: Porte, H.A.; Schnizlein, J.G.; Vogel, R.C. & Fischer, D.F.
Object Type: Report
System: The UNT Digital Library