Resource Type
Partner
Collection
Office of Scientific & Technical Information Technical Reports
1,077
Technical Report Archive and Image Library
729
TRAIL Microcard Collection
491
Harris and Eliza Kempner
9
Texas State Publications
7
National Advisory Committee for Aeronautics Collection
6
Abilene Library Consortium
2
Boy and Girl Scout Annual Reports
2
Congressional Research Service Reports
1
Federal Communications Reports
1
8 More
Serial/Series Title
Atomic Energy Commission Reports
225
Hanford Works Reports
182
HW (Series)
180
Oak Ridge National Laboratory Reports
100
AECU (Series)
82
University of California Radiation Laboratory Reports
61
AEC research and development report
56
United States Geological Survey Reports
44
TID
39
United States Bureau of Mines Reports
27
125 More
Country
States
Year
Month
Language
Results:
1 - 24 of
1,833
next
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
Chemical Technology Division, Unit Operations Section Monthly Progress Report for August 1959
The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed by taking a macro photograph of the desired gradient by monochromatic (436 m mu ) light transmitted by the solution normal to the gradient in an appropriate diffusion cell. Two Druhm runs were terminated due to malfunction of the sodium metering system and the third run was terminated when the UF/sub 6/ nozzle ruptured. Calculations of particle temperature versus time relations for the flame denitration-calcination method of preparing metallic oxide from nitrate solutions indicate that the times required for heat transfer are controlled by the rate of radiant heat transfer to particle surfaces instead of by conductive heat transfer within the particles. A completed experimental study indicated that electrolysis in a cell with a mercury cathode and a platinum anode is a practical process for removing nickel from HRT fuel solution. The apparent diffusion coefficient of uranium loading on Dowex 21K was shown to be directly related to the resin size. An explosion of sufficient violence to blow apart the Pyrex pipe dissolver occurred during the fifth Darex dissolution of simulated SRE fuel probably from a rapid gas phase reaction between hydrogen and oxidizing gases such as …
Date:
December 31, 1959
Creator:
Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
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
Production test IP-237-A, Irradiation of enriched seven-rod cluster elements for ETR testing: Supplement A
None
Date:
December 31, 1959
Creator:
Kratzer, W. K.
System:
The UNT Digital Library
Production test IP-262-A-11-FP, evaluation of projection fuel elements for use in ribbed process tubes: Demonstration loadings
The objective of this test is to demonstrate the feasibility of projection fuel elements for use In existing process tubing and to determine the reduction in rupture rates or hot-spot incidence so achieved. This test is to authorize, (a) charging 20 columns of bumper type fuel elements and 20 columns of control elements per reactor into B, D, DR, F, and R Reactors for irradiation up to 1200 MWD/T exposure, and (b) irradiation of four columns each of enriched (0.947%) bumper and enriched (0.947%) normal type fuel elements until two ruptures are sustained in each (or until one group shows a significant improvement).
Date:
December 31, 1959
Creator:
Hall, R. E.
System:
The UNT Digital Library
[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
SER Temperature Coefficient
Experimentally determine the overall isothermal temperature coefficient of the SER up to the design operating temperatures.
Date:
December 31, 1959
Creator:
Johnson, J. L.
System:
The UNT Digital Library
US Atomic Energy Commission Hanford Operations Office monthly status and progress report, September 1959. Part 1
This document provides details of activities of the Hanford Operations Office during the month of September 1959. (FI)
Date:
December 31, 1959
Creator:
Travis, J. E.
System:
The UNT Digital Library
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
THERMONUCLEAR PROJECT SEMIANNUAL REPORT FOR PERIOD ENDING JULY 31, 1959
None
Date:
December 30, 1959
Creator:
unknown
System:
The UNT Digital Library
Effect of Additions to Zircaloy on Hydrogen Pickup During Aqueous Corrosion
An investigation was conducted into the possibility of alloy additions to Zircaloy-2 to diminish hydrogen absorption during aqueous corrosion. The nickel in Zircaloy-2 is believed to be the major constituent responsible for the relatively high hydrogen absorption. Additions of up to 0.5 wt.% antimony, arsenic, bismuth, or tellurium were selected on the basis of their known ability to poison the catalytic effects of nickel in hydrogenation reactions of other systems. Results of tests conducted for a total of 224 days in 600 and 680 deg F water and 750 deg F steam revealed no decrease in hydrogen absorption in modified Zircaloy-2 containing the aforementioned alloy additions. Hydrogen absorption increased when these alloying elements were present in the range of 0.1 to 0.2 wt.%. Corrosion resistance also decreased with alloy additions in these ranges. A 2-atm. partial pressure of hydrogen in the steam or above the water did not affect hydrogen absorption in the alloys appreciably. The hydrogen partial pressure did not affect time to transition in corrosion rates, but did appear to produce higher weight gains than degassed water. (auth)
Date:
December 29, 1959
Creator:
Berry, W. E.; White, E. L. & Fink, F. W.
System:
The UNT Digital Library
Fuels Preparation Department monthly report, November 1959
This document details activities of the Fuels Preparation Department during the month of November 1959. (FI)
Date:
December 29, 1959
Creator:
unknown
System:
The UNT Digital Library
Plant Expansion Task Force technical feasibility and R&D efforts
The Expansion Study Task Force has evaluated several cases of Hanford reactor operation at power levels considerably higher than is presently obtained in the six older reactors. These higher power levels result in more rigorous operating conditions of temperature, heat flux, neutron flux, hydraulics, reactor control, etc. The purpose of this document, the various components of which were prepared by Process and Reactor Development Sub-Section personnel, is to assess the technical feasibility of operation under the proposed conditions, and to delineate those specific areas of development effort which may be necessary to provide adequate support for an expansion program.
Date:
December 29, 1959
Creator:
Gilbert, W. D.
System:
The UNT Digital Library
Prototype Freeze Trap Test
A performance evaluation was made of a prototype liquid cooled freeze trap with sodium at 350 and 1000 deg F. The sodium freeze-off function was adequate for all test conditions encountered. The freeze-off occurred satisfactorily with the larger clearance provided by a test modification to provide 0.030 eccentricity to the rotating shaft. Turning the freeze-trap handle was successful in opening the unit for gas venting when 350 deg F sodium was used. For a seal formed with 1000 deg F sodium, 16 turns of the trap handle gave no measurable gas venting at pressures up to 30 psi. Melting out the seal opened the vent satisfactorily. All the major problems encountered during the test were mechanical and associated with the rotating feature of the unit. (M.C.G.)
Date:
December 29, 1959
Creator:
Cygan, R.
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
Control and Dynamics Performance of a Sodium Cooled Reactor Power System. Report No. 171
None
Date:
December 28, 1959
Creator:
Hansen, P. D. & Eaton, J. H.
System:
The UNT Digital Library
INTERACTION OF TWO METAL SLABS OF PLUTONIUM IN PLEXIGLAS
Neutron multiplication measurements were performed on two identical finite Pu-metal slab assemblies separated and reflected by plexiglas. (auth)
Date:
December 28, 1959
Creator:
Schuske, C.L.; Goodwin, A. Jr.; Bidinger, G.H. & Smith, D.F.
System:
The UNT Digital Library
Net return course - operational severity index formuli
This document presents a nomograph from which the relationship between reactor operating parameters, tube power, and outlet temperature can be correlated with rupture rate. The index indicates the severity of the reactor climate during irradiation and does not include the metal quality parameters defined in the rupture rate equation. The general form of the Operational Severity Index Equation is OSI=P{sup 3.3}/1000{times}t{sub 0}{sup 8.7}/100, where OSI, is the unitless Operational Severity Index, P is the tube power in kW, and t{sub 0} is the tube outlet temperature, in degrees C.
Date:
December 28, 1959
Creator:
unknown
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