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Absorption of Organic Acids on Thoria
The adsorption of acetic and oleic acids on the surface of thoria was studied by means of infrared spectroscopy. An infrared analysis of the adsorbates before and after adsorption using differential double bean methods indicated that the adsorption of organic acids on thoria surfaces occurs by an esterification reaction between the organic acid and the hydroxylated thoria surface. Ammonia vapor will not adsorb on thoria, indicated the basic character of the hydroxylated surface.
Date:
December 31, 1959
Creator:
Bradford, Harold R. & Wadsworth, Milton E.
System:
The UNT Digital Library
Annual Report of Research Progress
This technical report constitutes a brief review of the work undertaken, entirely or in part, under the Contract AT(30-1)-1772 with eh United States Atomic Energy Commission. The work published during 1959 is listed at the end of this report and copies of the reprints or reports are attached where available. These investigations have been concerned with the examination of defect production and behavior as it may be observed by high frequency ultrasonic attenuation and velocity (modulus) changes in such materials as quartz, silicon, germanium, alkali halides (especially NaCl and XCl), high purity aluminum, and glass containing boron. The irradiations used are cobalt 60 gamma-ray irradiation and the reactor irradiation obtained in the Brookhaven National Laboratory graphite reactor.
Date:
December 31, 1959
Creator:
Truell, Rohn, 1913-1968
System:
The UNT Digital Library
Attempted Modification of Susceptibility of Tumors to X-Radiation : Final Report for August 1 1957 to August 31, 1959
Attempts to secure a high degree of synchronization of cell division of the Krebs mouse ascites carcinoma, by combined use of aminopterin and citrovorum factor, and by use of colchicine and N-acetyl colchinol, were unsuccessful. In the course of the work, a new method for securing smears of ascites tumor cells was out, which we believe will be found useful
Date:
December 31, 1959
Creator:
Beck, Lyle Vibert, 1906-
System:
The UNT Digital Library
[Daily Cash Balances for Sugar Land State Bank, December 31, 1959]
Report of the daily cash position for Sugar Land State Bank.
Date:
December 31, 1959
Creator:
Sugar Land State Bank
System:
The Portal to Texas History
Final Report on the Design, Construction and Operation of a Pulsed Subcritical Uranium Assembly for Eduational Uses
This report describes the design, construction and operation of a sub-critical nuclear reactor, intended for college teaching of reactor physics and of nuclear phenomena.
Date:
December 31, 1959
Creator:
Rensselaer Polytechnic Institute
System:
The UNT Digital Library
[Imperial Agency, Trial Balance, December 31, 1959]
Imperial Agency trial balance report featuring assets, liabilities, and expenses.
Date:
December 31, 1959
Creator:
Imperial Agency
System:
The Portal to Texas History
[Report On Examination, December 31, 1959]
Imperial Agency examination report featuring a balance sheet, statement of partners' equity, and statement of earnings.
Date:
December 31, 1959
Creator:
Imperial Agency
System:
The Portal to Texas History
Corrosion of INOR-8 and Inconel Dissolver Components of the Fluoride-Volatility Process
The corrosion of INOR-8 and Inconel dissolver components used in the fluoride volatility process for the dissolution of zirconium with anhydrous HF in molten salts was investigated. Ten dissolution runs were made using simulated subassemblies formed from Zircoloy-2. The dissolver and components were made from INOR-8. Both the dissolver vessel and draft tube were examined several times during the series of runs. The solids which formed at different areas in the system were also analyzed. The results showed that the corrosion of the INOR-8 dissolver was greatest at the salt-off gas interface and at the HF gas inlet. Almost all of the corrosion took place during run 10 when no zirconium was present. Portions of the dissolver were cleaned after run 10 and sent to BMI for evaluation. The results of the Battelle metallographic examinations of the portions are included along with several photographs. The results with Inconel tubes in the copper-lined hydro-fluorinator confirmed the observations that the liquid gas interface areas were the most susceptible to attack.
Date:
December 30, 1959
Creator:
Fink, Frederick W.
System:
The UNT Digital Library
Rupture Kinetics of Zircaloy-Clad Fuel Elements in High Temperature Water and Steam Interim Report 6 Effects of Carbon and Zirconium Content on Uranium Corrosion and Rupture Mechanism
This is the sixth in a series of interim reports describing various phases of the study of fuel element rupture kinetics and mechanisms. Previous reports issued are: No. 1- Experimental Methods and Procedures, HW-61378, No. 2- Coextruded Rod Elements with Pinhole Defects, HW-61379, No. 3 - Mechanism of the Uranium-Water Reaction, HW - 61799, No. 4 Coextruded Tube Elements with Pinhole Defects and Various Annular Spacings, HW- 62348, No. 5- Comparison of In-Reactor and Ex-Reactor Ruptures, HW-62766. This work is being done in cooperation with the Fuel Element Design Operation of the Hanford Laboratories Operation. J. W. Goffard has been particularly helpful in supplying samples and useful discussions of the results.
Date:
December 30, 1959
Creator:
Troutner, V. H.
System:
The UNT Digital Library
Self-Shielding Cross Sections : a Bibliography
This bibliography contains 37 references on self-shielding cross sections. The bibliography is limited to the period from 1951 through November 1959 with the references arranged alphabetically by title. The sources used in compiling this bibliography were: Abstracts of Classified Reports Nuclear Science Abstracts
Date:
December 29, 1959
Creator:
Cernak, Elizabeth A.
System:
The UNT Digital Library
Development and Testing of an Improved Agitator for the Redox and Purex Separations Plants
Relatively frequent agitator failures in HAPO Separations Plants have interfered with process continuity, contributed to process difficulties, and resulted in considerable maintenance expense. Predominantly the failures have been because of gear-reduction drive unit break-down or because of metallic fatigue and degeneration of the shaft-paddle assemblies. A simplified, slow-speed, direct drive agitator, previously described in HW-52755, proved to be quite durable and satisfactory during extended testing, operating without incident for over 10,000 hours. Subsequent operation of the agitator in the Redox Plant has been equally smooth. Total operating time (combined test and production use) is now in excess of 21,000 hours. Since the slow speed agitation principle has been adequately demonstrated at Redox and Purex canyon applications. This report describes the development and testing of such a "universal" agitator.
Date:
December 24, 1959
Creator:
Dunn, J. & Sloat, R. J.
System:
The UNT Digital Library
Organic Coolant Reclamation Annual Report : December 15, 1958 through December 14, 1959
Potential methods have been examined for the reclamation of high boiler arising from the degradation of polyphenol materials in use as reactor coolants and moderators. To define the chemistry of potential reclamation processes, model polyphenol compounds were used. These include biphenyl, o, m and p-terphenyl, and p-quaterphenyl. Emphasis has been on hydrocracking, redistribution (reaction with benzene), and partial reduction. Preliminary study has been made of the application these techniques to high boiler from Santowax-OM used in the OMRE. The three methods show promise but require detailed investigation to minimize carbon formation to locate optimum operating conditions,.
Date:
December 23, 1959
Creator:
Wineman, Robert J.; Adams, J. S.; Gudzinowicz, Benjamin J. & Scola, D. A.
System:
The UNT Digital Library
Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients
It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stability but also determine many operational characteristics.
Date:
December 23, 1959
Creator:
Allen, C. W.
System:
The UNT Digital Library
Design Criteria for PRP- Critical Facility Project CAH-842
The PRP Critical Facility is an experimental reactor for use in determination of basic nuclear constants of heterogenous reactors recycling plutonium, and exponential and criticality studies at power levels up to 100 watts and neutron fluxes of about 109 nv. Provision is made for changing reactor lattices using irradiated and unirradiated fuel elements with either a light or heavy water moderator.
Date:
December 18, 1959
Creator:
Nelson, H. K. & O'Neill, G. L.
System:
The UNT Digital Library
Report of the Forty-Fourth National Conference on Weights and Measures, 1959
Report of the annual conference on weights and measures, hosted by the U.S. National Bureau of Standards in Washington D.C. It includes conference proceedings, a list of attendees, information about committees and officers, and other reports or commentaries discussed at the meetings.
Date:
December 18, 1959
Creator:
United States. National Bureau of Standards.
System:
The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Tenth Letter Report, October 1 to December 1, 1959
Introduction: "This is the tenth letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from October 1 to December 1, 1959."
Date:
December 18, 1959
Creator:
Stockham, John D. & Rosinski, John
System:
The UNT Digital Library
Development of a Beta-Ray Particle Size Analyzer : Progress From November 15 to December 14, 1959
Monthly letter report on the research on the development of a beta-ray particle size analyzer (BPSA).
Date:
December 16, 1959
Creator:
Hewitt, Eric J.
System:
The UNT Digital Library
Periodic Radiation Survey. Section I. EFPH-5465.2. Second Performance. Core I, Seed 1. Test Results DL-S-231, T-612394
The purpose of the test was to determine the radiation levels in a Reactor Plant Boiler Compartment with the respective loop shut down and the remainder of the plant operating at power. The highest radiation levels recorded in the IC Boiler Compartment were located in the vicinity of the reactor coolant loop pipe penetrations of the Compartment. Except for the above mentioned areas, personnel could continuously occupy the IC Boiler Compartment without exceeding the maximum dose rate of 300 mr per week. The areas in the vicinity of the reactor coolant pipe penetrations, however, could be occupied only 1 to 2 hours per person per week because of the high radiation levers (200-250 mr/hr) present at these locations.
Date:
December 16, 1959
Creator:
McTish, James M.
System:
The UNT Digital Library
Thermodynamic Properties of Selected Minerals and Oxides at High Temperatures
A report about thermodynamic properties of several minerals which have been constructed in a form convenient for calculation of chemical equilibria of minerals and of problems related to the heat content of rocks.
Date:
December 16, 1959
Creator:
Robie, Richard A.
System:
The UNT Digital Library
Fission Gas Generation and Consequent High Temperature Irradiation Effects on Natural Uranium, Including Creep Properties : a Literature Search
Sixty-two references, some annotated, were taken from foreign literature to determine the status of work done in this area of metallurgy during 1958 and 1959. The references are grouped into two categories: references pertinent to the subject and general metallurgical references on metallic fuels.
Date:
December 15, 1959
Creator:
Scott, Myra
System:
The UNT Digital Library
Ionium (Thorium-230) for Radioisotope Preparation (Status Report)
For many years effort has been directed toward the development of means for the practical utilization of the heat evolved from the radioactive decay of certain fission and irradiation products. Fission products, in view of their availability in the plentiful, high-level wastes resulting from the processing of irradiated, nuclear reactor fuels have been most intensively studied for applications where their heat of decay might be converted into useful energy such as electricity for the operations of certain devices in place of chemical batteries . In addition other materials having desired radioactive properties may be produced by neutron bombardment of readily available elements.
Date:
December 15, 1959
Creator:
Coppinger, E. A. & Rohrmann, C. A.
System:
The UNT Digital Library
Nuclear Powered Tanker Design and Economic Analysis - Direct Cycle Boiling Water Reactor
A design and economic analysis is presented for a 44,000 DWT tanker utilizing a 27,300 shp direct cycle boiling water reactor propulsion system. Included are design descriptions and drawings, estimates of operating and capitol costs for the reference ship, estimates of long range potential, descriptions of required research and development programs, a preliminary safeguards analysis, an analysis of ship's motion on boiling water reactor performance, a summary reactor physics analysis, and a discussion of direct cycle accessibility considerations. Also included are summary descriptions for various design alternatives which were considered.
Date:
December 15, 1959
Creator:
General Electric Company
System:
The UNT Digital Library
Studies of Nuclear Debris in Precipitation : Second Quarterly Progress Report
A sequential method is described for the determination of strontium- 89, strontium-90, barium-140, and tungsten185 in rain water samples. A comparison is made of data on radioactivity in individual rain samples and in monthly pot samples. Data are included on the total strontiuro-90 fall-out collected in steep walled stainless steel pots during the period. Results are compared with cumulative data for 1958 end 1959. (C.H.)
Date:
December 15, 1959
Creator:
unknown
System:
The UNT Digital Library
Magnetic Recorder for Nuclear Pulse Application : Covering the Period from October 6, 1959 to December 5, 1959
"Abstract: Data on analog magnetic tape characteristics are presented along with results from conventional and modulator playback system operational tests. Theoretical considerations imply that the modulator head should be loss sensitive to short term variations in record and playback tape speed. It is also pointed out that although a tape recorder operating at 7.5 in./sec has only 12 kcs bandwidth for sinusoidal wave forms. the record and play-back amplifiers for pulse recording can operate with other bandwidths. These amplifiers must be capable of passing a square wave with a frequency of 1.5 kcs. A square wave of such frequency represents the condition of 350 microsecond pulses with a 700 microsecond period. (J.R.D)."
Date:
December 14, 1959
Creator:
Burgwald, G. M.
System:
The UNT Digital Library