Equilibrium Adsorption of Krypton and Xenon on Activated Carbon and Linde Molecular Sieves (open access)

Equilibrium Adsorption of Krypton and Xenon on Activated Carbon and Linde Molecular Sieves

Equilibrium krypton and xenon adsorption isotherms were obtained for four varieties of charcoal and for Linde Molecular Sieves Types 4A and 5A, generally at 0, 25, and 60°c. Such data are of interest in connection with design and evaluation of adsorbers for radioactive noble gas fission products. The isotherms were fitted, by linear regression analysis, to straight-line forms of the Freundlich and Langmuir equations. The Freundlich linear equation gave the better fit and the parameters of this equation are presented for each of the isotherms. Also presented are the constants for an equation representing the temperature dependence of arbitrary adsorption coefficients, the coefficients having been calculated from the Freundlich isotherm parameters. Some aspects of the applicability and accuracy of these results are discussed.
Date: February 14, 1961
Creator: Ackley, R. D. & Browning, W. E., Jr.
System: The UNT Digital Library
Removal of Radioiodine from Air-Steam Mixtures (open access)

Removal of Radioiodine from Air-Steam Mixtures

A short-term study was made to investigate the removal of radioiodine vapor from air-steam mixtures as could occur immediately following a nuclear incident in a pressurized water reactor. Activated charcoal traps, designed to simulate a small section of a commercial charcoal canister, were tested at gas velocities of 23.9 to 74.9 ft/min over the temperature range of 75 to 118°C. The iodine removal efficiency was found to range from 99.80 to 99.4% with an average of 99.9%. One test performed at a temperature of 105°C and with gas velocity of 290 ft/min indicated that the iodine removal efficiency was reduced to 99.54%. Activated charcoal exhibits a high efficiency for iodine vapor removal under these test conditions and appears suitable for application in the decontamination of air-steam mixtures.
Date: November 14, 1960
Creator: Adams, R. E. & Browning, W. E. Jr.
System: The UNT Digital Library
Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator (open access)

Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator

The designer's concept of a test program for the 30-Mw prototype intermediate heat exchanger and steam generator designed and fabricated as part of the Sodium Components Development Program is presented. The performance data will serve to verify the thermal design, or allow application of improved techniques to future designs, give an improved basis for stress analysis in design of future units, and demonstrate the capability and limitations of the units in relation to the performance specifications for which they were designed. Welding techniques for type 316 stainless steel are described. The specifications and operating conditions of the units are given along with instrumentation drawings showing test equipment design and arrangement.
Date: September 14, 1962
Creator: Alco Products (Firm).
System: The UNT Digital Library
Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3 (open access)

Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3

This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date: June 14, 1960
Creator: Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
System: The UNT Digital Library
A Spectrophotometric Atlas of the Spectrum of CH from 3000A to 5000A (open access)

A Spectrophotometric Atlas of the Spectrum of CH from 3000A to 5000A

Report of the near ultraviolet and visible emission spectrum of CH presented in the form of a spectrophotometric atlas. The spectrum was recorded photoelectrically from an acetylene-oxygen flame in the region 4900 to 3000 A by use of a high-resolution grating monochromator. Each of the lines in the CH spectrum is identified.
Date: February 14, 1961
Creator: Bass, Arnold M. & Broida, H. P.
System: The UNT Digital Library
Experimental Evaluation of the Fallout-Radiation Protection Afforded by a Southwestern Residence (open access)

Experimental Evaluation of the Fallout-Radiation Protection Afforded by a Southwestern Residence

Report regarding experiments made to determine the fallout-radiation protection offered by a "single-story stucco and frame house with a heavy shake roof and no basement," (p. 5) which is noted as being popular in the southwestern United States.
Date: March 14, 1961
Creator: Burson, Z.; Parry, D. & Borella, H.
System: The UNT Digital Library
Lung Hazards From Inhaled Radioactive Particulate Matter (open access)

Lung Hazards From Inhaled Radioactive Particulate Matter

Conclusions from the study: "Radioactive dusts are carcinogenic, and can cause cancer of the lung. complete dose response curves have not yet been determined. All the parameters that render this demonstrably toxic material (radioactive dust) have not yet been evaluated. It is strongly suggested by the experimental data that duration of radiological insult to the lung is an important factor in eliciting lung cancer. The atmospheric tolerance concentrations now in use seem to afford little margin of safety."
Date: September 14, 1960
Creator: Cember, Herman
System: The UNT Digital Library
A Proposed Mechanism and Method of Correlation for Convective Boiling Heat Transfer with Liquid Metals (open access)

A Proposed Mechanism and Method of Correlation for Convective Boiling Heat Transfer with Liquid Metals

An additive, interacting mechanism of micro and macro-convective heat transfer is proposed to represent boiling heat transfer with net vapor generation to saturated liquid metals in convective flow. Based on this mechanism, a method for calculating boiling coefficients is developed. The correlating is shown to be in fair agreement with early experimental results for convective boiling of potassium and sodium.
Date: October 14, 1963
Creator: Chen, John C.
System: The UNT Digital Library
Effects of Chronic Excess Salt Ingestion: Possible Implications of the Accelerated Induction of Experimental Hypertension by 2,4-Dinitrophenol (open access)

Effects of Chronic Excess Salt Ingestion: Possible Implications of the Accelerated Induction of Experimental Hypertension by 2,4-Dinitrophenol

Recently, we reported that the administration of the thyroid hormone, L-triiodothyronine (T3), markedly accelerated the development of experimental hypertension associated with a high-salt intake in intact rate. Earlier, Selye and his associates and Masson, Corcoran, and Page has observed a similar effect from thyroxin in uninephrectomized salt-fed rats. We were aware of the fact that oxidative phosphorylation is uncoupled by the thyroid hormone and were intrigued by the possibility that such uncoupling was instrumental in the accelerated development of the hypertension observed. The work reported here was undertaken with this possibility in mind; it was based on the well documented observation of Loomis and Lipmann that dinitrophenol reversibly inhabits oxidative phosphorylation. The present studies indicates that 2, 4-dinitrophenol, like L-triiodothyronine, can also rapidly induce hypertension in salt-fed rate. These observations have led us to develop a working hypothesis that may have general implications relative to the pathogenesis of hypertension in man.
Date: October 14, 1963
Creator: Dahl, Lewis K.; Heine, Martha & Tassinari, Lorraine
System: The UNT Digital Library
Gene Structure: Genetic Fine Structure. Remarks. (open access)

Gene Structure: Genetic Fine Structure. Remarks.

Though only recently established, this concept has been developing for a long time. More than thirty years ago Dubinin, Serebrovsky, and other, investigating the phenotypes of a number of "achaete-scute" alleles of Drosophilia melanogaster, found that the alleles could be arranged in a definite series accoding to bristle patters, and also that the heterozygotes lacked only those bristles which were affected in common by both participating alleles. They concluded that the serial classification of alleles according to bristle patters had its counterpart in a similar arrangement of portions of the achaete-scute gene locus. On this assumption they divided the locus into twelve elementary subunits. It was assumed that each allele arose by a change involving a certain combination of these centres. According to their theory, the achaete-scute locus is made up of separate, regularly spaced, and linearly arranged functional units. Several years later, Oliver described the occurrence of crossing over between two alleles of the "lozenge" locus. Then Green and a number of other workers analyzed similar phenomena in different regions of Drosophila chromosome. During the same period Lewis developed the theory of pseudoallelism, which interprets the occurrence of recombinants in interallelic crosses as the result of gene duplications. Thus …
Date: October 14, 1963
Creator: Demerec, M.
System: The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1 (open access)

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1

From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
Date: February 14, 1964
Creator: General Electric Company
System: The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2 (open access)

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2

From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
Date: February 14, 1964
Creator: General Electric Company
System: The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3 (open access)

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3

From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
Date: February 14, 1964
Creator: General Electric Company
System: The UNT Digital Library
Evaluation of Diethers as Uranium Extractants (open access)

Evaluation of Diethers as Uranium Extractants

Report on the determination of several physical properties, pertinent to uranium extraction, for a number of ethers and related compounds.
Date: January 14, 1963
Creator: Googin, J. M.; Harper, W. L.; Phillips, L. R. & Postma, Fred W.
System: The UNT Digital Library
Literature Survey on World Isotope and Radiation Technology : First Interim Report Covering the Period from June 15, 1961 to August 14, 1961 (open access)

Literature Survey on World Isotope and Radiation Technology : First Interim Report Covering the Period from June 15, 1961 to August 14, 1961

Abstract: "This is the first interim report of a literature survey investigating the uses and technology of radioscopes in the countries of the world, with particular emphasis necessarily placed on those more highly industrialized nations. Part I includes a general summary of the quantity and quality of radioisotope work being performed in these countries. Among the outstanding radioisotope applications with respect to quantity is the work of Japan in chemical research, that of USSR in metals research, and that in the USA in medical research. A detailed qualitative examination of the relatively narrow region of radioisotope applications in leak detection is also presented. Part II of this report gives a direct comparison between the progress and status of the US and the USSR in the varied uses of radio-isotopes."
Date: August 14, 1961
Creator: Haffner, J. W. & Stone, C. A.
System: The UNT Digital Library
Liquid Metal Fuel Reactor: Four-Inch Utility Test Loop: Design, Construction, Operation, and Experimental Results (open access)

Liquid Metal Fuel Reactor: Four-Inch Utility Test Loop: Design, Construction, Operation, and Experimental Results

Report issued by the Brookhaven National Laboratory discussing fuel reactor test loops. The "design, construction, operation, and experimental results" (p. 1) are presented. This report includes tables, illustrations, and photographs.
Date: July 14, 1960
Creator: Hoffman, K. C.; Isler, R. J.; Scarlett, C. H. & Schoener, G. A.
System: The UNT Digital Library
Development and Evaluation of High-Temperature Tungsten Alloys : Final Report, October 1, 1960 - September 30, 1960 (open access)

Development and Evaluation of High-Temperature Tungsten Alloys : Final Report, October 1, 1960 - September 30, 1960

This report summarizes investigations taken between October 1, 1959, to September 30, 1960 with the objectives of developing high-tungsten alloys which are readily fabricable into massive and complex shapes and which possess adequate strength for operation at temperatures up to 2000 F. Within this report, studies are divided into two main categories: alloy development and material fabrication techniques
Date: December 14, 1960
Creator: Holtz, F. C. & Van Thyne, R. J.
System: The UNT Digital Library
The Uranium-Rhenium Alloy System (open access)

The Uranium-Rhenium Alloy System

Abstract The phase diagram of the uranium-rhenium alloy system is presented along with a discussion on transformation kinetics of the uranium solid solutions. The phase diagram is of the double eutectic type with the intermediate phase having the composition URe2. This phase exhibits allotropy at 180°C and melts congruently at 2200°C. URe2 reacts sluggishly with the uranium solid solutions below 750°C to form the peritectoid compound U2Re. Eutectic reactions occur at 1105° and 2105°C at respective compositions of 10.5 and 65.5 wt. % Re. Eutectoid reactions occur at 643° and 681°C at compositions of 1.4 and 6 wt. % Re, respectively. The maximum solubility of rhenium in α uranium is about 0.4 wt. % at 643°C and in β uranium is 1.9 wt. % at 681°C. The solubility of rhenium in γ uranium is 6 wt. % at 681°C and increases to about 7 wt. % at 975°C. The solubility of uranium in rhenium is 0.6 wt. % at room temperature with little variation up to 2000°C. Alloys of β and γ uranium containing more than about 1.2 and 7 wt. % Re respectively, can be readily supercooled to room temperature. Rapid cooling of γ alloys containing less than about …
Date: January 14, 1963
Creator: Jackson, R. J. (Robert James), 1929-; Williams, D. E. & Larsen, W. L.
System: The UNT Digital Library
Hydromagnetic Ionizing Fronts (open access)

Hydromagnetic Ionizing Fronts

One of the techniques by which highly ionized plasmas can be generated in the laboratory makes use of strong, electromagnetically driven shock waves propagating into a cold gas. In this paper the phenomenon is analyzed as a one-dimensional single-fluid hydromagnetic problem, neglecting dissipation behind the wave. We hypothesize that the rarefaction wave remains attached to the front. In the limit of essentially complete ionization behind the front the problem can be solved analytically as long as the transverse magnetic field there remains small compared with the longitudinal field.
Date: December 14, 1961
Creator: Kunkel, Wulf B. & Gross, Robert A.
System: The UNT Digital Library
Contaminant effects study : final report, January 5 to September 15, 1962 (open access)

Contaminant effects study : final report, January 5 to September 15, 1962

From abstract: "This report describes work done on ARF Project C 216 from January 5, 1962 to September 15, 1962. The objectives of the program include evolution of an analytical research program to evaluate effects of environment contributed contamination on precise devices"
Date: November 14, 1962
Creator: Lieberman, A.
System: The UNT Digital Library
Design Criteria for Reactor Test Support Facility at NRTS (open access)

Design Criteria for Reactor Test Support Facility at NRTS

This technical report provides a design criteria for a technical support facility for the Lithium Cooled Reactor Experiment (LCRE) and SNAP-50-DR-1 Test Facilities. The support facility is adjacent to the LCRE Test Facility and is located completely within the existing Building 629 structure at the former ANP area of the National Reactor Testing Station (NRTS) near Idaho Falls, Idaho. The information and specifications presented establish the basis for the design of laboratories, shops and engineering areas required to support the installation, operation, maintenance and disassembly of the LCRE and SNAP-50 tests. The construction and modification required to adapt the building to reactor test support operations are described in detail in the following report.
Date: September 14, 1962
Creator: Macfarlane, D. B.
System: The UNT Digital Library
Statue of Pilot Plant Section Equipment Development Program (open access)

Statue of Pilot Plant Section Equipment Development Program

A development program is being carried out in the pilot plant to improve the equipment involved in monitoring, metering and pumping process streams. The equipment under development includes an alpha monitor, a gamma monitor, a waste water monitor, a liquid flow rate meter, a canned rotor pump, a diaphragm pump, air lifts and a pressure tank pump. This report presents the present status of the testing program.
Date: October 14, 1960
Creator: Mackey, T. S.
System: The UNT Digital Library
Effect of Radiation Damage on SM-1, SM-1A and PM-2A Reactor Vessels (open access)

Effect of Radiation Damage on SM-1, SM-1A and PM-2A Reactor Vessels

Report describing the status of the SM-1, SM-1A, and PM-2A reactors, specifically regarding the effects "of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture." (p. iii)
Date: October 14, 1961
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A.; Coombe, J. R.; Kelleman, R. W.; Bobe, P. E. et al.
System: The UNT Digital Library
A Useful Solution for Short Cylindrical Shells and Other Applications (open access)

A Useful Solution for Short Cylindrical Shells and Other Applications

The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notation is used throughout the derivations; however, a knowledge of matrix theory is not need for application of the results.
Date: February 14, 1961
Creator: Moore, S. E.
System: The UNT Digital Library