Resource Type
Serial/Series Title
Development of Microorganisms With Improved Transport and Biosurfactant Activity for Enhanced Oil Recovery Progress Report
1
Direct Energy Conversion Fission Reactor Progress Report
1
Hydrogen Production via a Commercially Ready Inorganic Membrane Reactor Progress Report
1
ORNL Radioisotope Distirbution Program Progress Report
1
Decade
Month
Day
Language
566 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
566
next
Corrosion of Tuballoy-Molybdenum Alloys by Water
The primary purpose of the corrosion work was to find a tuballoy alloy which would be sufficiently corrosion resistant to be useful for canned slugs even if some of the can were to leak. The secondary purpose was to obtain general corrosion data on tuballoy alloys.
Date:
May 31, 1945
Creator:
Hopkins, J.M.; Nelson, F. & Binger, W.W.
Object Type:
Report
System:
The UNT Digital Library
100 Areas: (For technical progress letter No. 99), May 21--May 27
This report details 100 Area reactor operation for the time period of May 21 through May 27, 1946.
Date:
May 31, 1946
Creator:
Jordan, W. E.
Object Type:
Report
System:
The UNT Digital Library
Monthly Progress Report No. 61 for May, 1948
This is the University of California, Radiation Laboratory monthly progress report for May 1948. It discusses the following: (1) 184-inch Cyclotron Program; (2) 60-inch Cyclotron Program; (3) Synchrotron Program; (4) Linear Accelerator Program; (5) Experimental Physics; (6) Theoretical Physics, (7) Isotope Separation Program; (8) Chemistry Departments; (9) Medical Physics; and (10) Health Physics and Chemistry.
Date:
May 31, 1948
Creator:
Authors, Various
Object Type:
Report
System:
The UNT Digital Library
Investigation of the Stack Gas Filtering Requirements and Development of Suitable Filters. Report No. 5
Investigation of dust loading capacity for various assemblies of air filter media on atmospheric dust has continued using the small tester described in previous reports. The effect of fiber size and packing density in Fiberglas mat has been studied. The combination of very fine fibered glass mats now in use at Oak Ridge was given special investigation. Tests were made using a coarser mat as a prefilter and an economic advantage was showm for such protection. As a result of laboratory studies on gauze backed hand sheets a paper mill run is planned to make paper comparable to #6 now used by Chemical Corps for AEC filters but stronger and lower in cost In this run the paper will be made with a reenforcing gauze backing. Fabrication work is being carried on with emphasis on two special shapes of units both of which aim to simplify installation and removal and to give better protection to operating personnel when filters are being changed. These shapes namely the hollow cube and the circular will be described in detail with sketches and test data. A 950 CFM full scale model of the hollow cube has been constructed to demonstrate the practicability of the …
Date:
May 31, 1949
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Fission Product Analysis of Urine
A method has been adapted from ion exchange studies for removal of the fission products, Cs-137, Sr-90, and the rare earths for both untreated urine samples and the supernates from the precipitation steps in the TTA procedure for plutonium. Because of the excessive amount of eluant necessary to separate the fission products and the resulting time required to run a separation, a method was developed to remove the Sr-Y, Ce and Pr by chemical means and Cs from the raffinate of this extraction by ion exchange. It should be noted that Cs is easily separated from Pu in the separations plant, and that is presence as a contaminate in the outer areas is not as probable as the other long-lived fission products. This fact has been born out in three years of analyzing contaminated samples from the 200 Area by the H.I. Development Divisions.
Date:
May 31, 1950
Creator:
Thorburn, R. C.
Object Type:
Report
System:
The UNT Digital Library
THREE NEW DELAYED ALPHA EMITTERS OF LOW MASS
Two new positron active isotopes, B{sup 8} and Na{sup 20}, have been found to decay to excited states of Be{sup 8} and Ne{sup 20}, which in turn decay 'instantaneously' by alpha emission. Their half-lives are 0.65 {+-} 0.1 sec. and 1/4 sec. respectively. N{sup 12} is also found to have a low energy positron group which leads to an {alpha}-unstable excited state in C{sup 12}. The masses of B{sup 8} and Na{sup 20} are 8.027 and 20.015 respectively. B{sup 8} decays by a 13.7 {+-} 0.3 Mev positron, through the same excited state of Be{sup 8} as does Li{sup 8}. Estimates of the energies of the excited state in C{sup 12} and Ne{sup 20} are made.
Date:
May 31, 1950
Creator:
Alvarez, Luis W.
Object Type:
Report
System:
The UNT Digital Library
ELECTROMAGNETICALLY ENRICHED ISOTOPES INVENTORY MAY 31, 1951
None
Date:
May 31, 1951
Creator:
Keim, C.P.; Normand, C.E. & Weaver, B.
Object Type:
Report
System:
The UNT Digital Library
RADIOCHEMICAL STUDIES ON THE FISSION OF Th$sup 232$ WITH PILE NEUTRONS. (Based on AECD-2862)
None
Date:
May 31, 1951
Creator:
Turkevich, A & Niday, J B
Object Type:
Report
System:
The UNT Digital Library
Future power levels of Hanford Piles
This document was prepared in response to a request from the Atomic Energy Commission for a brief review of the principal ideas and technical developments which might effect power levels over the following six years. Also requested were approximate data on any pile modifications that might be involved, including rough estimates covering possible cost and completion dates. A brief discussion of plans for increasing the power levels of the Hanford Piles is provided.
Date:
May 31, 1955
Creator:
Greager, O. H.
Object Type:
Report
System:
The UNT Digital Library
PRELIMINARY CRITICAL TESTS USING AQUARIUM FUEL ELEMENTS IN THE BSR GRID
None
Date:
May 31, 1955
Creator:
Henry, K M; Johnson, E B & Maienschein, F C
Object Type:
Report
System:
The UNT Digital Library
Tube Power Limits -- Past, Present and Future
During the history of operation of the Hanford reactors, several methods have been utilized to establish an outlet water temperature or ``Panellit`` limit based on the stability of water flowing through the process tubes. These methods have been known as ``Excess Header Pressure Limits,`` ``Trip Before Boiling Limits,`` and the most recent, ``Trip Before Instability Limits.`` Each new concept vas accepted only after considerable experimental data had proved the new method to be safe and operationally feasible. It is anticipated that in the future other tube outlet water temperature limits will be developed based on new technology. The purpose of this document is to present, in simple terms, an understandable explanation of previous operating limits, to discuss the status of the present Instability Limits, and to outline the direction of future work in raising the outlet water temperature limits.
Date:
May 31, 1955
Creator:
Carbon, M. W. & Gilbert, W. D.
Object Type:
Report
System:
The UNT Digital Library
Conceptual Design of a Nuclear Ram Jet-Rocket Missile
The conceptual design of a nuclear ram jet-rocket missile is preserved. This missile is a modified, scaled-up AC-210 nuclear ram jet carrying ammonia in the space enclosed by the spike and inlet diffuser. The payload may be a 10,000 pound thermonuclear weapon or equivalent weight of reconnaissance equipment plus local shielding as in the AC-210 missile. The payload for a missile of body size equivalent to the AC-210 will be reduced by the weight of ammonia.
Date:
May 31, 1956
Creator:
Szekely, T.
Object Type:
Report
System:
The UNT Digital Library
Index and ABstract Summary of Preliminary Reports, Department 4270, May, 1956
None
Date:
May 31, 1956
Creator:
Susano, C. D.
Object Type:
Report
System:
The UNT Digital Library
A Pilot Plant for the Reduction of Uranium Hexafluoride to Uranium Tetrafluoride with Trichloroethylene
Pilot plant experiments are described in which trichloroethylene was used for the reduction of uranium hexafluoride to uranium tetrafluoride. After unsatisfactory preliminary results with liquid phase reduction, satisfactory results were obtained with a vapor phase reduction system. It was found that vapor phase reduction at approximately 450 deg F, produced a low density product which contained only small quantities of uranium(VI); sintering the uranium tetrafluoride in a hydrogen fluoride atmosphere increased the product density to approximately 3 g/cc. The reduction was essentially complete, and the effluent gas contained less than 1 ppm of uranium hexafluoride. The purity of the uranium tetrafluoride produced was equivalent to that of the uranium hexafluoride used as feed. A complete discussion is given of the operation of the various parts of the system. (auth)
Date:
May 31, 1956
Creator:
Baker, J. E.; Klaus, H. V.; Schmidt, R. A. & Smiley, S. H.
Object Type:
Report
System:
The UNT Digital Library
Reactor transient
The authors are planning a calculation to be done on the Univac at the Louviers Building to estimate the effect of xenon transients, a high reactor power. This memorandum outlines the reasons why they prefer to do the work at Louviers rather than at another location, such as N.Y.U. They are to calculate the response of the reactor to a sudden change in position of the half rods. Qualitatively, the response will be a change in the rooftop ratio of the neutron flux. The rooftop ratio may oscillate with high damping, or, instead, it may oscillate for many cycles. It has not been possible for them to determine this response by hand calculation because of the complexity of the problem, and yet it is important for them to be certain that high power operation will not lead us to inherently unstable operation. Therefore they have resorted to machine computation. The system of differential equations that describes the response has seven dependent variables; therefore there are seven equations, each coupled with one or more of the others. The authors have discussed the problem with R.R. Haefner at the plant, and it is his opinion that the IBM 650 cannot adequately handle …
Date:
May 31, 1956
Creator:
Menegus, R. L.
Object Type:
Report
System:
The UNT Digital Library
EFFECTS OF LETDOWN RATES AND OXYGEN INJECTION RATES ON XENON POISON LEVEL AND EXCESS OXYGEN CONCENTRATION IN THE HRT
None
Date:
May 31, 1957
Creator:
Haubenreich, P.N.
Object Type:
Report
System:
The UNT Digital Library
AQUEOUS HOMOGENEOUS REACTOR FUEL PROCESSING--THE BEHAVIOR OF INSOLUBLE CORROSION AND FISSION PRODUCTS
For presentation at the American Chemical Society's Nuclear Technology Symposium, Boston, Apr. 5-10, Information is presented from studies with materials and conditions simulating those expected in anm aqueous homogeneous reactor for the formation of insoluble corrosion and fission products in aqueous UO/sub 2/ SO/sub 4/ solutions used as a reactor fuel. Sulfate salts which become insoluble as the temperature inereases deposited preferentially and reversibly on hot walls. Oxides from hydrolysis of sulfate salts deposit on any surfaces while insoluble corrosion products released into the solution show variable degrees of circulation. (auth)
Date:
May 31, 1958
Creator:
Haas, P.A.
Object Type:
Report
System:
The UNT Digital Library
An Evaluation of Data on Nuclear Carbides
Data on the properties, constitution, compatibility, radiation behavior, fabrication, preparation, storage, and handling of uranium, thorium, and plutonium carbides are reviewed. 187 references. (C.J.G.)
Date:
May 31, 1960
Creator:
Rough, F.A. & Chubb, W. eds.
Object Type:
Report
System:
The UNT Digital Library
Fuels Preparation Department monthly report, April 1960
This document details activities of the Fuels Preparation Department during the month of April 1960. (FI)
Date:
May 31, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Sub-Cooled Burnout Relative to Hanford Reactors
In the Hanford production reactors, failure of fuel element cladding is known as subcooled burnout since the bulk coolant temperature is below the saturation temperature at time of failure or burnout of the fuel cladding. The heat generation rate at which subcooled burnout occurs, establishes a limit to allowable reactor power level. This document compares present and potential power level limits at the Hanford production reactors with power level limits established by subcooled burnout.
Date:
May 31, 1960
Creator:
Carlson, P. A. & Trumble, R. E.
Object Type:
Report
System:
The UNT Digital Library
USE OF SILICON SURFACE-BARRIER COUNTERS IN FAST-NEUTRON DETECTION AND SPECTROSCOPY
A neutron-sensitive semiconductor counter was constructed by depositing a thin layer of Li/sup 6/F between two silicon surface-barrier counters. Neutrons are detected by observing the alpha + T pair resulting from the Li/sup 6/(n, alpha )T reaction; pulses from the two counters are added, and the sum pulse is amplified and recorded on a multichannel analyzer. Since the sandwich geometry permits simultaneous detection of both reaction products, the magnitude of the resulting sum pulse is proportional to the energy of the incoming neutron. Pulse-height spectra from slow neutrons and monoenergetic fast neutrons. in the energy region 0.6 to 3.5 Mev, were recorded from two counters of this type; in both counters the sensitive area was about 0.7 cm/sup 2/, with a Li/sup 6/F layer of order 150 mu g/cm thick. In all cases. a well defined neutron peak was observed in the pulse-height spectrum. In a typical case the full width at half maximum of the fast-neutron peak was about 300 kev. Counters of this type are relatively insensitive to background effects, notably gamma rays, and thus may prove to be useful in the detection and spectroscopy of fast neutrons. (auth)
Date:
May 31, 1960
Creator:
Love, T A & Murray, R B
Object Type:
Report
System:
The UNT Digital Library
VARIABLE MODERATOR REACTOR DEVELOPMENT PROGRAM. Quarterly Progress Report No. 4
None
Date:
May 31, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Defect-tests of power generating co-extruded fuel rods
The effect of the many parameters which may influence the failure behavior of coextruded fuel material are being evaluated by Reactor & Fuels Research & Development Operation. This knowledge will be helpful in the design, fabrication, and operation of fuel elements so that the hazards and time involved at failure may be minimized. Many of the various tests performed on unirradiated coextruded fuel material have been in isothermal systems. The tests reported here were performed on power generating coextruded fuel rods. One of the purposes of these tests was to assess the effect of simulated in-reactor power generation and associated thermal gradients and thermal stresses on the defect-test behavior. Another purpose of these tests was to determine the degree of damage that might result to fuel components as a result of interaction (e.g., touching produced by warping or distortion of a failing rod) while at operating powers.
Date:
May 31, 1961
Creator:
Goffard, J. W. & Hayden, K. D.
Object Type:
Report
System:
The UNT Digital Library
EFFECT OF TEMPERATURE ON RADIATION-INDUCED CONTRACTION OF REACTOR GRAPHITE
The distortion behavior of graphite as a function of irradiation temperature is reviewed. The behavior of needlecoke and CSF graphite was examined over moderate exposures in the GETR. Results showed needle-coke to be less contracting than CSF. Details of contraction show a minimum contraction rate per 10/sup 21/ nvt at 600 to 800 deg C for both types. Limitations to be placed on the data presented are listed. (P. C.H.)
Date:
May 31, 1961
Creator:
Davidson, J. M. & Helm, J. W.
Object Type:
Report
System:
The UNT Digital Library