Routine 107 basin inlet samples (open access)

Routine 107 basin inlet samples

None
Date: August 25, 1956
Creator: Reid, D. L.
Object Type: Report
System: The UNT Digital Library
The Constitution of Delta-Phase Alloys of the System Uranium-Molybdenum-Titanium (open access)

The Constitution of Delta-Phase Alloys of the System Uranium-Molybdenum-Titanium

None
Date: September 25, 1956
Creator: Saller, H. A.; Rough, F. A.; Bauer, A. A. & Doig, J. R.
Object Type: Report
System: The UNT Digital Library
THE ELECTRICAL PROPERTIES OF URANIUM OXIDES (open access)

THE ELECTRICAL PROPERTIES OF URANIUM OXIDES

None
Date: September 25, 1956
Creator: Willardson, R.K.; Moody, J.W. & Goering, H.L.
Object Type: Report
System: The UNT Digital Library
ORNL ceramic information meeting trip report, October 1--3, 1956 (open access)

ORNL ceramic information meeting trip report, October 1--3, 1956

The meeting was opened by Leo Brewer, who spoke on a ``Self-Purifying Reactor.`` This is a reactor with theoretically designed-in separations processes, involving calculations to show that it is possible to vaporize many fission products away from fuels. The reactor would be analogous to a graphite rod impregnated with a uranium or thorium compound, vapor-coated with zirconium, and cooled by liquid metal. The fission products will vaporize when the rod gets hot enough, and will be carried out of the pile in a flow of helium. The details of what will happen to the rest of the pile at these temperatures, and of the materials of construction required to handle the situation are yet to be worked out. Remarks were heard from representatives of BMI, GE, Lockland, ANL, ORNL, KAPL, AEC and MCW on properties of uranium oxides and other refractory oxides.
Date: October 25, 1956
Creator: O`Leary, W. J.
Object Type: Report
System: The UNT Digital Library
Inert-Gas-Shielded Consumable-Electrode Welding of Molybdenum (open access)

Inert-Gas-Shielded Consumable-Electrode Welding of Molybdenum

None
Date: April 25, 1957
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Preliminary Experimental Results of Pressure and Temperature Response to Slow Plugging of a Process Time (open access)

Preliminary Experimental Results of Pressure and Temperature Response to Slow Plugging of a Process Time

This report presents the results of preliminary experiments of a program directed toward determining the limit of protection afforded by the Panellit system against gradual plugging of a process tube.
Date: April 25, 1957
Creator: Hesson, G. M. & Thorne, W. L.
Object Type: Report
System: The UNT Digital Library
Some Effects of Thickness of the Layer in Protection Against Flash Burns by Creams (open access)

Some Effects of Thickness of the Layer in Protection Against Flash Burns by Creams

None
Date: April 25, 1957
Creator: Payne, F. W. & Hinshaw, J. R.
Object Type: Report
System: The UNT Digital Library
A Martensitic Reaction for Uranium (open access)

A Martensitic Reaction for Uranium

Hardness measurements of specimens quenched from the beta yields alpha phase at different cooling rates support the proposed martensitic beta yields alpha transformation for urnnium. Specimens held in 635 and 600 deg C isothermal baths prior to subsequent quenching to --5 deg C require more than 10 and two seconds, respectively before diffusion mechanlsms for beta yields alpha transformation commence. Once started, about 500 seconds are required to complete transformation by diffusion at these temperatures. Specimens quenched prior to tais hold time transform in part martensitically. Relationships are calculated for hardness as a function of grain size and cooling rate, and for grain size as a function of cooling rate. Metallographic examination confirms the hardness trends and reveals that widely varied grain structures can be produced by controlled cooling from the beta phase. Finally, a schematic time- temperature-transformation curve is sketched from the hardness data obtained. (auth)
Date: June 25, 1957
Creator: Bement, A. L. & Wallace, W. P.
Object Type: Report
System: The UNT Digital Library
THE PHYSICAL PROPERTIES OF TITANIUM AND TITANIUM ALLOYS (open access)

THE PHYSICAL PROPERTIES OF TITANIUM AND TITANIUM ALLOYS

None
Date: July 25, 1957
Creator: Lepkowski, W. J. & Holladay, J. W.
Object Type: Report
System: The UNT Digital Library
AN INVESTIGATION OF THERMAL TRANSIENTS AT A SOLID-FLUID INTERFACE (open access)

AN INVESTIGATION OF THERMAL TRANSIENTS AT A SOLID-FLUID INTERFACE

This report discusses analytical and experimental heattransfer studies of cyclic temperature oscillations rn a fluid medium and their effect on the temperature of an adjacent solid boundary. These studres are intended to aid in the analysis of thermal stress caused by cyclic temperature fluctuations. The results of experimental measurements of thermal amplitude attenuation for an effectively infinite wall are presented together with heat-transfer analyses for two cases with finite walls. (auth)
Date: October 25, 1957
Creator: Mott, J.E.
Object Type: Report
System: The UNT Digital Library
SURVEY OF PRESSURE AND DIFFERENTIAL PRESSURE INSTRUMENT TYPES FOR POSSIBLE APPLICATION TO HRE-3 SLURRY SYSTEM (open access)

SURVEY OF PRESSURE AND DIFFERENTIAL PRESSURE INSTRUMENT TYPES FOR POSSIBLE APPLICATION TO HRE-3 SLURRY SYSTEM

None
Date: October 25, 1957
Creator: Wills, H.D.
Object Type: Report
System: The UNT Digital Library
Relations Between the Hyperon Polarizations in Associated Production (open access)

Relations Between the Hyperon Polarizations in Associated Production

None
Date: November 25, 1957
Creator: Gatto, R.
Object Type: Report
System: The UNT Digital Library
STRESS ANALYSIS OF FLAT CIRCULAR PLATES (open access)

STRESS ANALYSIS OF FLAT CIRCULAR PLATES

The principal relations for the stress analysis of flat circular plates according to the classical theory are presented in a convenient form. Almost any flat circular plate of uniform thickness, with or without central holes, loaded with any combination of axisymmetrical loads may be analyzed by the procedures. (A.C.)
Date: November 25, 1957
Creator: Stanek, F.J.
Object Type: Report
System: The UNT Digital Library
Vinyl Coating of Graphite Plates for Ultrasonic Inspection (open access)

Vinyl Coating of Graphite Plates for Ultrasonic Inspection

A process has been developed for application of a thin, adherent vinyi plastic coating to graphite plates to prevent absorption of coupling fluids'' used in ultrasonic inspection. The plates are preheated and dipped mechanically in a fluid plastisol, and the resulting coating is fused in an infra-red heater. No significant attenuation of ultrasonic impulse results from presence of the coating. After inspection, the vinyl sheath may be easily stripped from the plate. (auth)
Date: March 25, 1958
Creator: Church, J. S.; Bell Jr., J. H.; Donahoe, J. K.; Faussone, R. A.; Rogers, G. B. & Rowen, J. T.
Object Type: Report
System: The UNT Digital Library
Biology and Medicine Semiannual Report for October 1957 Through March 1958 (open access)

Biology and Medicine Semiannual Report for October 1957 Through March 1958

Data are presented from the following studies: the radiation chemistry of pepsin, gelatin, methanol, benzene, and hexanes; the effects of irradiation of the pituitary in advanced cancer using high-energy particles from the 184-inch cyclotron; applications of ion beams in biological studies; the metabolism of strontium-90 and its relation to calcium metabolism in rats; hematological effects of low-level radiation doses in man; the influence of diet on serum lipoproteins; development of simplified methods for the analysis of blood serum for lipid content; tracer studies employing iron59 of red blood cell production and destruction and iron metabolism in a wide variety of blood disorders; tracer studies on heart function and blood circulation employing I/sup 131/; applications of C/sup 14/ in studies of leukocyte formation from which it was concluded that peripheral neutrophils have a 2-day life span, large lyphocytes a life span of 2 to 3 days, and small lyphocytes a life span of between 8 and 14 days; tracer studies employing P/sup 32/ in studies of the phagocytic action of cells of the reticuloendothelial system; factors regulating the volume of the body fluids; and development of a method for determining estrogen concentration in urine. Radiation protection activities are summarized. Lists are …
Date: April 25, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Arc Calcination of Thorium Oxide (open access)

Arc Calcination of Thorium Oxide

An over-all description of the background material on the use of electrical arcs for heating of powders is presented as well as a summary of experimental studies on the arc calcination of thoria. Favorable results have been indicated both with heating thoria powder in an arc heated gas and with thoria formed into a consumable electrode. Use of a consumable electrode produces thoria particles 0.1 to 0.01 mu in diameter. It is recommended that additional electrodes be fabricated and further arc calcination tests be run to produce a quantity of product sufficient for evaluation. (auth)
Date: June 25, 1958
Creator: Johnsson, K.O.
Object Type: Report
System: The UNT Digital Library
In-reactor corrosion of X-8001 and 1245 aluminum: Analysis of data from PT IP-42A (open access)

In-reactor corrosion of X-8001 and 1245 aluminum: Analysis of data from PT IP-42A

Failures of standard fuel element jackets (1245 aluminum alloy) after relatively short Hanford reactor exposures are occurring at high reactor power levels. Metallographic examination of fuel element jackets from short exposure ruptures shows the cause of failure to be rapid intergranular corrosion. This type of attack has been reproduced in laboratory tests by exposure to water at temperatures above 200 C, or to steam at temperatures higher than 300 C. Flow disruptions due to misalignment of the fuel elements within the reactor process tube, worn tube ribs, etc., are believed to cause the high local jacket temperatures necessary for the occurrence of intergranular corrosion.
Date: June 25, 1958
Creator: Dillon, R. L. & Richman, R. B.
Object Type: Report
System: The UNT Digital Library
Volatility Studies of Some Fission Product Fluorides (open access)

Volatility Studies of Some Fission Product Fluorides

A preliminary study of the volatility behavior of molybdenum indicated that MoF/sub 5/ was converted to MoF/sub 6/ by F/sub 2/; MoF/sub 6/ and Tc fluoride are absorbed on NaF at 100; technetium fluoride is more strongly held than molybdenum fluoride on NaF; MoF/sub 6/ may not be completely trapped by a dry ice trap. The behavior of volatile fission product fluorides was such that (a) Ru and Nb fluorides were volatile from fused salts during fluorination, (b) Mo and technetium were not volatile during hydrofluorination but were in excess F/ sub 2/> 100 deg C(auth).
Date: June 25, 1958
Creator: Brooksbank, W. A., Jr.; Carter, R. J. & Osborne, M. F.
Object Type: Report
System: The UNT Digital Library
THE EFFECT OF PLANT THERMAL EFFICIENCY ON THE COST OF NUCLEAR POWER (open access)

THE EFFECT OF PLANT THERMAL EFFICIENCY ON THE COST OF NUCLEAR POWER

Nuclear power cost is plotted versus thermal efficiency. The relationship is not limited to any particular reactor type and is applicable for any reactor system where steam is the working fiuid for the turbogenerator. (T- R.H-)
Date: July 25, 1958
Creator: Albrecht, W.L.
Object Type: Report
System: The UNT Digital Library
Remote Maintenance Experimental Work on a Reactor System Pump (open access)

Remote Maintenance Experimental Work on a Reactor System Pump

An experimentally determined evaluation of standardremote-handling equipment applied to the problems associated with remote maintenance of a typical reactor system component is presented It is comcluded that commercially available equipment can be used and that a good techmician can rapidly learn the use of manipulators required in remote maintenance. The use of closed circuit television in maintenance is possible; however, further development of radiation- resistant equipment is required. (j.R.D.)
Date: July 25, 1958
Creator: McDonald, W.B.; McGlothlan, C.K. & Storto, E.
Object Type: Report
System: The UNT Digital Library
Reactor Components Study (open access)

Reactor Components Study

Reactor operating conditions are formally established to conserve pile life. A major part of the 2000 Research and Development effort is oriented to develop fundamental information required to properly establish these limiting operating conditions. This report reviews the current condition of reactor components believed important to continued productive life of the reactors and discusses the current status of technologies important in estimating the future productive life of the reactor complex. These evaluations are conducted continuously and this report is one of a series of status reports.
Date: August 25, 1958
Creator: Curtiss, D. H.; Fullmer, G. C. & Gilbert, W. D.
Object Type: Report
System: The UNT Digital Library
Simulation of Various Accident Considerations for a Merchant-Ship Pressurized-Water Reactor (open access)

Simulation of Various Accident Considerations for a Merchant-Ship Pressurized-Water Reactor

A study was conducted on the safety aspects of foreseeable accident types in connection with the Nuclear Merchant Ship Reactor program. Four accidents have been selected for analysis by analog simulation techniques: continuous rod withdrawal, startup, loss of coolant flow, and cold-water insertion. The simulation of the reactor only was required for these situations because the effects of the accidents would be completed in less than one primary- coolant loop time. The external control system was ignored, and only the effects of the negative reactivity cocfficients were considered in the natural shutdown of the plant. Three phases of operation were considered in these analyses: operation with no safety system, high-flux scram, and period scram. The programs involved the variations of the scram parameters and the reactor temperature coefficients over the range of possible values for this reactor power plant. Results indicate that the inherent stabliity of the reactor system is sufficient to attenuate the power excursions resulting from the first three accidents. In the coldwater accident, if the difference in loop temperatures is on the order of 300 deg F, scram is necessary to limit the power excursion. (auth)
Date: August 25, 1958
Creator: Boyd, Roger S.; Gordon, Benjamin B.; Byers, Richard H.; Winslow, Leon E. & Stone, J. James, Jr.
Object Type: Report
System: The UNT Digital Library
Nuclear Gas Engine (open access)

Nuclear Gas Engine

A preliminary design study of the nuclear gas engine, consisting of a gas-cooled reactor directly coupled to a reciprocating engine, is presented. The principles of operation of the proposed gas engine are outlined and typical variations anre discussed. The nuclear gas engine is compared with other reciprocating engines and air compressors. A comparison between the ideal and actual cycles is made, with particular attention given to pumping, heat, and other losses to be expected. The applications and development of the nuclear gas engine are discussed. (W.D.M.)
Date: September 25, 1958
Creator: Fraas, A. P.
Object Type: Report
System: The UNT Digital Library
Summer Quarter, 1958, Co-Op Report (open access)

Summer Quarter, 1958, Co-Op Report

process and fluidized bed reactor is reported. Work done on cleanup of mercury from the Metallex process is also described. (J.R.D.)
Date: September 25, 1958
Creator: Smith, M. O.
Object Type: Report
System: The UNT Digital Library