Addendum to Hazards Summary Report for the Gcre Critical-Assembly Experiments (open access)

Addendum to Hazards Summary Report for the Gcre Critical-Assembly Experiments

None
Date: September 22, 1959
Creator: Chastain, J. W.; Epstein, H. M.; Hogan, W. S. & Dingee, D. A.
Object Type: Report
System: The UNT Digital Library
All In-Well Permeability Testing Packer (open access)

All In-Well Permeability Testing Packer

Disposal of liquid radioactive wastes to ground requires knowledge of the area ground-water hydrology. Information is desired on direction and velocity of ground-water flow. Direction of flow can be determined from maps showing contours on the water table surface, such contours being derived from well water elevations. Ground-water velocity is more difficult to ascertain.
Date: September 29, 1959
Creator: Raymond, J. R.
Object Type: Report
System: The UNT Digital Library
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
Analytical Program for Processing Stainless Steel Uranium Dioxide Reactor Fuel Elements (open access)

Analytical Program for Processing Stainless Steel Uranium Dioxide Reactor Fuel Elements

Analytical programs have been described for uranium recovery processes for aluminum-uranium and zirconiumuranium reactor fuel elements. It is the purpose of this paper to describe the analytical program for the uranium recovery process involving stainless steel-uranium reactor fuel elements. The recovery process consists of a two step dissolution and the regular liquid-liquid solvent extraction using TBP in kerosene. Sulfuric acid is used to dissolve the stainless steel. As a result of the sulfuric acid dissolution the uranium is converted to a slurry. The uranium slurry is then dlssolved in nitric acid. After the nitric acid dissolution the feed material is compatible with the extraction columns used at the Idaho Chemical Processing Plant for other type fuel elements previously described. In order to analyze samples of dissolver solutions for constituents necessary for plant operation, three new analytical methods were developed. These methods are a rapid method for determining uranium, one for nitrate and one for sulfate. Methods are described for urarium, acidity, specific gravity, nitrate, and sulfate in the dissolver solution; also for small amounts of uranium in the extraction column raffinates. Samples of dissolver solution and first cycle aqueous raffinate contain large amounts of fission products. These samples require shielded …
Date: September 18, 1959
Creator: Huff, G. A.
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
Automatic Reader for Air-Monitoring Filter Paper (open access)

Automatic Reader for Air-Monitoring Filter Paper

An automatic reader was developed for scanning 4 x 9in. filter papers from systems that monitor particulate airborne activity. Paper tape shows alpha and betagamma activities, together with counting times and identifying data, for any samples exceeding a predetermined value a special indicator mark is added. (auth)
Date: September 28, 1959
Creator: Thaxter, M. D. & Taussig, Thomas
Object Type: Report
System: The UNT Digital Library
Behavior of Bond Under Dynamic Loading (open access)

Behavior of Bond Under Dynamic Loading

The objectives of this research program are to determine bond strength under dynamic loading, to compare bond strengths under static and dynamic loading, and to test the adequacy of ACI Building Code bond requirements for structural elements subjected to blast loads. The tests have shown that local static bond strengths may be as high as 0.75 fc and that under dynamic loading this strength increases to fc. For all practical lengths of embedment of bars, steel failure is to be expected both under static and dynamic loading. Such bars loaded dynamically will carry a larger load than bards loaded statically, this increase in load carrying capacity of bars being sole due to the increase of steel strength under dynamic loading.
Date: September 1959
Creator: Liepins, A. A. (Artis A.)
Object Type: Report
System: The UNT Digital Library
A Bibliography on Gas Lubricated Bearings-Revised. Interim Report (open access)

A Bibliography on Gas Lubricated Bearings-Revised. Interim Report

A compilation of 290 references on gas bearings is presented. In most cases an English resume' of each reference is included a translation being made when required. The references are arranged alphabetically by first author. Indexes included are the year of origin corporate author, subject, patent number, and country of origin. (J.R.D.)
Date: September 15, 1959
Creator: Sciulli, E. B.
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
Blast Biology. Technical Progress Report (open access)

Blast Biology. Technical Progress Report

Experimental data regarding the biologic consequences of exposure to several environmental variations associated with actual and simulated explosive detonations were reviewed. Blast biology is discussed relative to primary, secondary, tentiary, and miscellaneous blast effects as those attributable, respectively, to variations in environmental pressure, trauma from blast-produced missiles (both penetrating and nonpenetrating), the consequences of physical displacement of biological targets by blast-produced winds, and hazards due to ground shock, dust, and thermal phenomena not caused by thermal radiation per se. Primary blast effects were considered, noting physical-biophysical factors contributing to the observed pathophysiology. A simple hydrostatic model was utilized diagrammatically in pointing out possible etiologic mechanisms. The gross biologic response to single. "fast"-rising overpressures were described as was the tolerance of mice, rats, guinea pigs. and rabbits to "long"-duration pressure pulses rising "rapidly" in single and double steps. Data regarding biological response to "slowly" rising over-pressures of "long" duration are discussed. Attention was called to the similarities under certain circumstances between thoracic trauma from nonpenetrating missiles and that noted from air blast. The association between air emboli, increase in lung weight (hemorrhage and edema), and mortality was discussed. Data relevant to the clinical symptoms and therapy of blast injury are presented. …
Date: September 18, 1959
Creator: White, C. S. & Richmond, D. R.
Object Type: Report
System: The UNT Digital Library
Calculation of K reactor flow decay transient (open access)

Calculation of K reactor flow decay transient

The process water pumping system for the K-reactors consists of six parallel sets of two series-connected pumps. A BPA outage could sever the power to all pumps. It is of major concern to known how the reactor flow decays with time following the power severance. The following analysis gives the general solution of this problem without recourse to the assumptions which have been used heretofore. The solution of the decay problem was programmed on the IBM 709. The program will give the flow transient for two series-connected pumps arbitrary physical characteristics, initial conditions, system and supply curves. It will give the decay characteristics for loss of power to either or both pumps. A full description of the program and its output is given in the Appendix.
Date: September 17, 1959
Creator: Massena, W. A.
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 Development Section C Monthly Progress Report August 1959 (open access)

Chemical Development Section C Monthly Progress Report August 1959

Uranium extractions from carbonate solutions were effective and phase separation rates were rapid using a new commercial quaternary extractant, Alamine 336. Extraction coefficients were approximately proportional to the quaternary concentration. Addition of -0.5 mole tridecanol/mole quaternary to the solvent gave optimum extraction efficiency and phase separation rates.
Date: September 8, 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 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 Processing Department Monthly Report: August 1959 (open access)

Chemical Processing Department Monthly Report: August 1959

This report, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.
Date: September 21, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
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
CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JUNE 20, 1959 (open access)

CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JUNE 20, 1959

The H-F conductance and susceptance were determined for coil-type vessels over a range of frequencies from 2 to 30 mc. The ultraviolet absorption spectra of organic compounds in the vapor phase were determined, and a maximum was assigned to each compound. The dielectric constant values for five alpha substituted ketones at 25 deg C are reponted. A series of acids in dimethylformamide was titrated with the alkali methoxides by the high-frequency and conductance methods. The titration curves by these two methods were very similar in shape and also very similar to the curves for the corresponding type of acid in aqueous solution (W.L.H.)
Date: September 14, 1959
Creator: unknown
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
A Collection of Excerpts and a Bibliography relative to the Proposition "That Congress should be given the Power to Reverse Decisions of the Supreme Court" (open access)

A Collection of Excerpts and a Bibliography relative to the Proposition "That Congress should be given the Power to Reverse Decisions of the Supreme Court"

This report is a Collection of Excerpts and a Bibliography relative to the Proposition "That Congress should be given the Power to Reverse Decisions of the Supreme Court".
Date: September 28, 1959
Creator: American Law Division
Object Type: Report
System: The UNT Digital Library
Comparison of BEO Versus Graphite as a Moderator for MGCR (open access)

Comparison of BEO Versus Graphite as a Moderator for MGCR

The comparison is made on the basis of nuclear requirements, properties, cost, and performance under irradiation. Results of published work were reviewed on the effects of irradiation on beryllium oxide and beryllium oxide - uranium dioxide dispersions. A research proposal for a Maritime Gas-cooled Reaotor Moderator is included. (J.R.D.)
Date: September 11, 1959
Creator: Wallace, W. P. & Simnad, M. T.
Object Type: Report
System: The UNT Digital Library