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25 content of initial lots of Hanford UO{sub 3} (open access)

25 content of initial lots of Hanford UO{sub 3}

At the time the first UO{sub 3} from so-called ``full-level`` Redox runs was shipped from 224U, the % U{sub 235} as determined in 222-S appeared high when compared with theoretical values from the burn-out curve. Close agreement between the 222-S results and % U{sub 235} determined by K-25 on lots 007, 008, and 009, however, indicated that a considerable heel of cold uranium in Redox had been blended with the first ``full level`` material. This explanation has been verified by data collected over the past weeks and provided this report. It has also been verified by the % U{sub 235} found in lots later than 010* (after most of cold uranium flushed out of Redox) which ranged from 0.66% to 0.64%.
Date: May 28, 1952
Creator: Work, J. B.
Object Type: Report
System: The UNT Digital Library
25 Process Assistance. For Period of May 2, 1955 to May 13, 1955 (open access)

25 Process Assistance. For Period of May 2, 1955 to May 13, 1955

None
Date: May 23, 1955
Creator: Culler, F L
Object Type: Report
System: The UNT Digital Library
215 MWD/Ton batch size limits and control in the Bismuth Phosphate Plant (open access)

215 MWD/Ton batch size limits and control in the Bismuth Phosphate Plant

None
Date: May 24, 1954
Creator: Browne, W. G.
Object Type: Report
System: The UNT Digital Library
Absorption Spectrum of Ferric Sulfate Complex (open access)

Absorption Spectrum of Ferric Sulfate Complex

None
Date: May 22, 1950
Creator: Katzin, L.I. & Gebert, E.
Object Type: Report
System: The UNT Digital Library
Adsorption of Xenon in an Activated Charcoal Column (open access)

Adsorption of Xenon in an Activated Charcoal Column

Performance characteristics of two activated charcoal columns at room temperature in separating fission-product xenon from an air stream were investigated by installing each column in the exhaust from an enclosure in which irradiated slugs were dissolved. Breakthrough curves are presented and the variation in xenon concentration within the columns is examined. Theoretical treatments of adsorption columns in the literature are found to agree well with the experimental data. Performance of the colunms is evaluated in terms of concentration factor'' and number of effective theoretical plates. (auth)
Date: May 11, 1959
Creator: Cantelow, H. P.
Object Type: Report
System: The UNT Digital Library
AEC Hot Cells and Related Facilities (open access)

AEC Hot Cells and Related Facilities

Shielded enclosures equipped with viewing devices and remote-hauling equipment for use in experiments and processes involving radioactivity are referred to as hot cells. The hot cell includes the biological shield enclosing the working space, viewing devices, special ventilating equipment, and special equipment for use in the hot cells, such as manipulators, cranes, machine tools, and measuriag devices. A hot cave is the same as a hot cell. A junior hot cave is a small-sized hot cave. A summary is presented of pertinent data on hot cells in use at various AEC installations. (C.H.)
Date: May 1, 1958
Creator: Fosdick, Ellery R.
Object Type: Report
System: The UNT Digital Library
AEC Symposium on Particle-Fluid Mechanics (open access)

AEC Symposium on Particle-Fluid Mechanics

This report addresses the AEC symposium on particle-fluid mechanics
Date: May 13, 1959
Creator: Thomas, D. G.
Object Type: Report
System: The UNT Digital Library
Aluminum Canning of Nickel-Plated, Hanford Four-Inch Uranium Fuel Slugs by Hot-Pressing (open access)

Aluminum Canning of Nickel-Plated, Hanford Four-Inch Uranium Fuel Slugs by Hot-Pressing

Conditions of time, temperature, and pressure for hotpress bonding of aluminum-nickel and uranium-nickel disks were determined experimentally. A process for jacketing Hanford four-inch slugs, coated with nonporous nickel electroplates, in aluminum cans by cold-sizing and hot-pressing was developed and conditions of time, temperature, and pressure required for the actual canning process were determined. (auth)
Date: May 17, 1955
Creator: Sumsion, H. T.; Beck, C. J. & DeLuca, L. S.
Object Type: Report
System: The UNT Digital Library
Analyses required for the slag and crucible recovery program (open access)

Analyses required for the slag and crucible recovery program

This summary from the analytical research section, May 1, 1951, briefly describes the analytical method to be utilized in the recovery of plutonium from crucibles program.
Date: May 1, 1951
Creator: Groot, C. & Hill, O.F.
Object Type: Report
System: The UNT Digital Library
Analysis of 100-K emergency water requirements after CGI-844 pump failure (open access)

Analysis of 100-K emergency water requirements after CGI-844 pump failure

The demand plot has a 5-set, modified pump decay curve; it shows that 20,000 gpm emergency flow would be required within 80 seconds of complete pump power failure. Bases for the demand curve are constant bulk inlet temperature of 2 C, constant bulk outlet temperature of 95 C, K-3 I&E fuel elements, and initial reactor flow of 188,000 gpm.
Date: May 28, 1959
Creator: Corlett, R. F.
Object Type: Report
System: The UNT Digital Library
Analysis of Heat Transfer, Burnout, Pressure Drop and Density Date for High Pressure Water (open access)

Analysis of Heat Transfer, Burnout, Pressure Drop and Density Date for High Pressure Water

This report is the descriptive summary Analysis of Heat Transfer, Burnout, Pressure Drop and Density Date for High Pressure Water.
Date: May 1, 1951
Creator: Jens, W. H. & Lottes, P. A.
Object Type: Report
System: The UNT Digital Library
AN ANALYSIS OF THE MAGNESIUM-CO$sub 2$ REACTIONS IN TERMS OF A REACTOR ENVIRONMENT (open access)

AN ANALYSIS OF THE MAGNESIUM-CO$sub 2$ REACTIONS IN TERMS OF A REACTOR ENVIRONMENT

The hazards associnted with the use of magnesium capsules in a CO/sub 2/- cooled reactor system have been analyzed, and consideration has been given to incidents which could lead to excessive temperature excursions and factors which could significantly reduce the ignition temperature of magnesium alloys. Methods of reducing the hazards associated with the Calder Hall type of reactor are discussed, and an experimental approach with which to define more aaccurately conditions that would lead to ignition is suggested. (auth)
Date: May 15, 1958
Creator: Scott, J.L.
Object Type: Report
System: The UNT Digital Library
Annealing of Irradiated Boron Containing Alloys and Dispersions (open access)

Annealing of Irradiated Boron Containing Alloys and Dispersions

The interpretation of the dimensional instability of U- Zr alloy containing small amounts of boron has raised the question of whether the observed low-temperature swelling can be related to the temperatureswelling characteristics of either the U-Zr alloy or Zr- B alloys by themselves. To obtain such information on the Zr--B system to compare with the more detailed study of thc alloy early results of which were reported in KAPL-1562, pieces of previously irradiated Zr- B alloys and dispersions were annealed in vacuum at temperatures between 350 and 750 C. (auth)
Date: May 12, 1958
Creator: Johnston, W. V. & Noonan, J. E.
Object Type: Report
System: The UNT Digital Library
Apparatus for Visual Study of Corrosion by Hot Water (open access)

Apparatus for Visual Study of Corrosion by Hot Water

None
Date: May 1, 1955
Creator: Grieser, Daniel R. & Simons, Eugene M.
Object Type: Report
System: The UNT Digital Library
APPR-1 HOT CHANNEL FACTORS. RE-EVALUATION ON THE BASIS OF MANUFACTURING EXPERIENCE AND ZERO POWER EXPERIMENTS (open access)

APPR-1 HOT CHANNEL FACTORS. RE-EVALUATION ON THE BASIS OF MANUFACTURING EXPERIENCE AND ZERO POWER EXPERIMENTS

None
Date: May 1, 1957
Creator: Brondel, J.O.
Object Type: Report
System: The UNT Digital Library
APPR Critical Experiment (open access)

APPR Critical Experiment

None
Date: May 18, 1955
Creator: Gallagher, J. G.; Bate, R. R.; Mann, J. E. & Callihan, A. D.
Object Type: Report
System: The UNT Digital Library
APPR critical experiment program meeting (open access)

APPR critical experiment program meeting

This report addresses the APPR critical experiment program meeting.
Date: May 19, 1955
Creator: Gallagher, J G
Object Type: Report
System: The UNT Digital Library
Aqueous Corrosion of Uranium and Alloys: Survey of Project Literature (open access)

Aqueous Corrosion of Uranium and Alloys: Survey of Project Literature

None
Date: May 14, 1952
Creator: McWhirter, J. W. & Draley, J. E.
Object Type: Report
System: The UNT Digital Library
AQUEOUS HOMOGENEOUS REACTOR FUEL PROCESSING--THE BEHAVIOR OF INSOLUBLE CORROSION AND FISSION PRODUCTS (open access)

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
Aqueous Homogeneous Research Reactor--Feasibility Study (open access)

Aqueous Homogeneous Research Reactor--Feasibility Study

None
Date: May 1, 1957
Creator: Kasten, P. R.; Lundin, M. I.; Segaser, C. L.; Aven, R. E.; Gilfillan, D. R.; Hughes, R. F. et al.
Object Type: Report
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program. Monthly Progress Report for April 1959 (open access)

Army Gas-Cooled Reactor Systems Program. Monthly Progress Report for April 1959

The Army Gas Cooled Reactor System Program includes water moderated heterogeneous reactor (Gas Cooled Reactor Experiment I), a graphite moderated homogeneous reactor (Gas Cooled Reactor Experiment II), a mobile gas cooled reactor (ML-1), and the co ordination of thc Gas Turbine Test Facility. The progress of each project, the associated tests and data evaluation, the applicabie design criteria, and the fabrication of reactor components are briefly summarized. (For preceding period see IDO-28538.) (W.D.M.)
Date: May 25, 1959
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Artificial cooling of the Columbia River by dam regulation: Part 1 (open access)

Artificial cooling of the Columbia River by dam regulation: Part 1

In early July 1958, it appeared that Columbia River temperatures at HAPO would be near 24--50{degree}C by the end of August. River temperatures were averaging 40 to 50{degree}C above 1957 figures and were 3{degree} to 4{degree} above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent. The large storage of cold water behind Grand Coulee Dam, normally untapped, was a source of possible relief. A plan for use was proposed for the peak high temperature period and agreed to by the Bureau of Reclamation.
Date: May 25, 1959
Creator: Kramer, H. A.
Object Type: Report
System: The UNT Digital Library
Artificial cooling of the Columbia River by dam regulation. Part 3 (open access)

Artificial cooling of the Columbia River by dam regulation. Part 3

The temperatures of the Columbia River was reduced 1 to 30 Centigrade with beneficial effects at HAPO. It is reasonable to expect that future benefits may be possible. It is desirable that the temperature of the river be controlled each year to the maximum extent possible. Instrumentation improvements requested to effect optimum savings. Records of river temperatures and flows should continue to be maintained by IPD as a necessary part of temperature optimization. Where possible, the coincident use of the river cooling technique should be made for the benefit of anadromous fish.
Date: May 25, 1959
Creator: Kramer, H. A.
Object Type: Report
System: The UNT Digital Library
The Average Fission Cross Section of U$sup 233$, U$sup 234$, and U$sub 236$ in the Fast Cross Section of U$sup 236$ in the Fast Reactor Neutron Spectrum (open access)