Safety Tests on Hand Stacking of U-235 Cubes (open access)

Safety Tests on Hand Stacking of U-235 Cubes

From abstract: "Critical assembly tests have been made on the Pajarito Universal Machine to determine the safety limits of handstacking cubes of 95% U-235 in spherical geometries preparatory to making critical assemblies of U-235 in an "infinite" tuballoy tamper. The U-235 cubes were stacked as pseudospheres in a cavity at the top of a tuballoy block 12" high and 8" on a side, and the assembly tamped by locating it inside a doughnut shaped water tank whose tamping effect is equivalent to the tamping caused by personnel necessary for hand stacking."
Date: October 11, 1948
Creator: Josephson, V.; Young, D. S. & Dike, R. S.
System: The UNT Digital Library
Plasma Containment Configuration (open access)

Plasma Containment Configuration

Report discussing a plasma containment configuration which appears to have no escape cone. From abstract: "Arguments are given to show how the containment process works, including experimental evidence deduced from published reports on "electromagnetic levitation."
Date: October 11, 1956
Creator: Linlor, William I., 1915-
System: The UNT Digital Library
The Slow Neutron Transmission of Be Metal as Measured by a Neutron Beam Spectrometer in the Energy Region 0.004 eV to 50 eV (open access)

The Slow Neutron Transmission of Be Metal as Measured by a Neutron Beam Spectrometer in the Energy Region 0.004 eV to 50 eV

Abstract. Slow neutron transmission measurements as a function of the time of flight of the incident neutron have been made for three different thicknesses of Beryllium. The energy region from 0.004 eV to 50 eV was investigated using the Columbia neutron beam spectrometer system. Particular emphasis was placed on the very low energy region (from 0.004 eV tp 0/2 eV or from 0.6 to 5 [length]) where pronounced crystal interference effects were observed. The effective slow neutron cross section (in the unity of X 10(-24)ce(2)atom) for several different energy values were: 6.1 at 0.2 [length], 3.5 at 1.5 [length], 2.3 at 2.5 [length] and 0.6 at 4.6 [length]. The positions of the discontinuities in the cross section agree fairly well with the values obtained from the X-ray measurements.
Date: October 11, 1944
Creator: Rainwater, Leo James, 1917- & Havens, W. W. (William Westerfield), Jr., 1920-2004
System: The UNT Digital Library
Results of Critical Mass Studies for Hanford at K-25 (open access)

Results of Critical Mass Studies for Hanford at K-25

Report presenting results of a study regarding the critical masses and nuclear properties of plutonium as well as the use and effects of various tampers.
Date: October 11, 1950
Creator: Gast, Paul F.
System: The UNT Digital Library
Neutron Yield in Uranium vs. Energy of Deuterons and Protons (open access)

Neutron Yield in Uranium vs. Energy of Deuterons and Protons

The purpose of this note is to recalculate the semi-empirical curve of neutron yield vs. deuteron energy originally obtained by H. York in order to predict, using it and the best available data, what yields may be expected for deuterons on uranium in the extrapolated energy region.
Date: October 11, 1950
Creator: Brown, H.
System: The UNT Digital Library
The Thermal Conductivity of Liquid UF6 (open access)

The Thermal Conductivity of Liquid UF6

From introduction: "The measurement of the thermal conductivity of liquid TF6 presented unusual difficulties because of two of its properties which necessitated working with a closed system. The properties were (1) the liquid can exist as such only above 64.05°C. at which temperature its saturated vapor pressure is 1140 mm. of mercury, and (2) the compound reacts rapidly with moist air. Also because of the liquid's extremely corrosive nature, it was necessary to design a cell of special corrosion resistant materials."
Date: October 11, 1944
Creator: Priest, Homer F.
System: The UNT Digital Library
Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program, Semiannual Report for Period January 1 - June 30, 1963 (open access)

Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program, Semiannual Report for Period January 1 - June 30, 1963

This technical report describes development work done on method of particle separation by the Biology Division of the Oak Ridge National Laboratory and the Oak Ridge Gaseous Diffusion Plant during the period January 1 to June 30, 1963, under the Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program. The central effort has been to develop zonal centrifuge systems for the separation of cells and sub-cellular particles, including viruses, and bio-colloids, including proteins and nucleic acids.
Date: October 11, 1963
Creator: Anderson, N. G.
System: The UNT Digital Library
Decoupling Concepts and Project Cowboy (open access)

Decoupling Concepts and Project Cowboy

This paper for the Project Vela Technical Symposium is intended to be a brief resume of the principle results of the Cowboy program. The material is taken from a report entitled "Use of Large Cavities to Reduce Seismic Waves from Underground Explosions" by Herbat, Werth, and Spring (1960). As a result, no effect is made to justify each step in the analysis; reference should be made to the complete report.
Date: October 11, 1960
Creator: Werth, Glenn C.
System: The UNT Digital Library
In-link Alpha Monitor Prototype Performance (open access)

In-link Alpha Monitor Prototype Performance

This report summarizes the operational experience and the data obtained on the 2AW Purex type process stream. The performance of an in-line alpha monitor for continuously monitoring Plutonium in Purex Process waste streams is described. The instrument has a lower limit of measurement of 1 x 10⁻⁶ grams of Plutonium per liter and can measure concentrations as high as 7.9 x 10⁻² grams/liter.
Date: October 11, 1955
Creator: Hildreth, N. T.
System: The UNT Digital Library
Investigation of the Causes of Weld Rejects (open access)

Investigation of the Causes of Weld Rejects

Weld rejects have accounted for a large percent of the total rejects in the production of fuel elements, and consequently, the investigation of the causes of these rejects was a desirable undertaking. Although previous investigations had made possible a satisfactory standardization of the welding process, it was felt of value to more sharply define the causes of weld rejects and to facilitate the control of these causes.
Date: October 11, 1955
Creator: Otterbein, G. L.
System: The UNT Digital Library
Dry Maintenance Facility for the HRT (open access)

Dry Maintenance Facility for the HRT

A portable shield has been designed, developed, fabricated and shop tested to provide the HRT with a facility for direct dry maintenance operations. It provides temporary replacement for any one of the lower roof plugs and should permit many operations to be performed without flooding the reactor cell with water.
Date: October 11, 1960
Creator: Holz, P. P.
System: The UNT Digital Library
Local Reactivity "Worth" in the HRT (open access)

Local Reactivity "Worth" in the HRT

The effect of adding small quantities of fuel or poison to the HRT has been estimated using perturbation theory. The results have been reduced to a single relation and a set of graphs which make the estimation of added reactivity relatively simple. The perturbation theory results are compared with multigroup results and reasonable agreement is demonstrated; however, there is some question concerning the prompt neutron lifetime.
Date: October 11, 1960
Creator: Jaye, S. & Vondy, D. R.
System: The UNT Digital Library
A Preliminary Study of Pre-Solvent Extraction Treatment of Stainless Steel-Uranium Fuels with Dilute Aqua Regia (open access)

A Preliminary Study of Pre-Solvent Extraction Treatment of Stainless Steel-Uranium Fuels with Dilute Aqua Regia

The continuous dissolution of 304 stainless steel and stainless steel-UO2 alloy in dilute aqua regia was studied with subsequent stripping of the dissolver product to remove chloride ion. The process has the advantage of producing, by means of a simple head end treatment, a solvent extract feed in a conventional nitric acid medium so that existing solvent extraction processes, materials of construction and waste disposal methods can be used. The purposes of this study were to investigate the variables affecting the dissolution process and to obtain dissolver scale-up data, and to investigate the removal of chloride from the dissolver product and the variables affecting the stripping operation. A continuous flooded pot dissolver was used. It has the advantages of stability of operation and ease of control in comparison with column dissolvers and requires a minimum of mechanical processing prior to dissolution. Stripping of the dissolver product to remove chloride ion was studied in a 4-in. diameter Pyrex bubble-cap column containing 12 single bubble cap plates. Continuous dissolution rates and dissolver product stainless steel loading were correlated with aqua regia feed composition, acid feed rate and surface area exposed to reaction. Profiles of chloride concentration down the stripping column were obtained …
Date: October 11, 1957
Creator: Kitts, F. G. & Perona, J. J.
System: The UNT Digital Library