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Life of Van Stone Corrective Measures

Description: This report is a document summarizing all information available on life aspects of various measures proposed to reduce or eliminate corrosion of Van Stone flanger.
Date: September 12, 1949
Creator: Botsford, C. W. & Eschbach, E. A.
Partner: UNT Libraries Government Documents Department
open access

X-ray Photometric Assay of Plutonium in Metal Castings

Description: This following report discusses certain topics pertinent to the x-ray photometric method, such as the optimum size of sample and of sample concentration, the technique of measurement for high precision, the use of easily prepared uranium standards for future calibrations and corrections for extraneous substances, and it compares results obtained by both x-ray and chemical assays.
Date: December 12, 1952
Creator: Lambert, M. C.
Partner: UNT Libraries Government Documents Department
open access

Review of the Xenon Problem

Description: Report discussing studies regarding the properties and nuclear constants of xenon, an element relevant to use of high power thermal neutron reactors.
Date: March 12, 1952
Creator: Gast, P. F.
Partner: UNT Libraries Government Documents Department
open access

Behavior of S.I.R. Fuels Irradiated in Sodium: Final Report, Production Test 105-180-P (Special Request KAPL-79: The "Beta Experiment")

Description: Report describing the effects of pile irradiation on fuel materials and coil springs for the Submarine Intermediate Reactor. The investigation was called for by Hanford Irradiation Request No. 79. Results of investigation are detailed in the report.
Date: August 12, 1952
Creator: Lambert, J. B., 1929-
Partner: UNT Libraries Government Documents Department
open access

Radioactive Particles in the Atmosphere : January 1951 - March 1951

Description: Report discussing studies regarding active atmospheric particles in several United States cities. Experimental data of particles collected in filters is given.
Date: April 12, 1951
Creator: Singlevich, W.
Partner: UNT Libraries Government Documents Department
open access

Westinghouse Creep Test of Zirconium-WAPD-M-106; Memorandum

Description: Basis: "It is desired to test the effect of neutron flux on the creep rate of zirconium. These data will greatly add to the metallurgical information needed for design specifications of reactor components utilizing this metal."
Date: February 12, 1951
Creator: Loeb, L. M.
Partner: UNT Libraries Government Documents Department
open access

Temperature distribution in an inhomogeneous cell

Description: Report describing "the effects of variable graphite conductivity and of the gas layers in the lattice" under the assumptions that "graphice conductivity varies as a power of the distance from the center of each cell" and "uniform distribution of heat sources" - from abstract.
Date: November 12, 1951
Creator: Triplett, John R.
Partner: UNT Libraries Government Documents Department
open access

Plutonium Oxide- Plastic Mixtures for Critical Mass Studies

Description: Critical mass experiments to be conducted at HAPO will require dilute and concentrated plutonium solutions. Since very high plutonium concentrations (~2,000 g/l) cannot be attained in pumpable solutions, solid plutonium compounds will be utilized for this phase of the work. Mixtures of plutonium oxide and polyethylene, methyl methacrylate or paraffin compacted in containers have been considers for use in highly-concentrated plutonium systems of known hydrogen to plutonium atomic ratio (H/Pu).
Date: May 12, 1960
Creator: Crocker, H. W.
Partner: UNT Libraries Government Documents Department
open access

Completion Report An Automatic Fuel Element Stamping Machine

Description: This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date: January 12, 1960
Creator: Allen, C. H.
Partner: UNT Libraries Government Documents Department
open access

Disposition of Contaminated Processing Equipment at Hanford Atomic Products Operation 1958-1959

Description: Operating plant experiences in restoring to useful service failed equipment contaminated through exposures to radioactive processes is of international interest to the nuclear industry. In accordance with a request from the Hanford Operations Office of the United States Atomic Energy Commission this report of the various measures taken in rehabilitating for re-use expensive engineered equipment has been compiled by the General Electric Company. This report is a review and summary of the dispos… more
Date: February 12, 1960
Creator: Kingsley, P. S.
Partner: UNT Libraries Government Documents Department
open access

Once Through Decontamination Studies- Interim Report No. 1.

Description: The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has also been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This report contains information on a series of tests performed in the 242-B single pass flow facility. Information concerning the following are presented: (1) Efficiency of decontaminating KER Loop 1 and 2 contaminated specimens. (2) Efficiency of… more
Date: January 12, 1960
Creator: Perrigo, L. D. & Hekenson, J. F.
Partner: UNT Libraries Government Documents Department
open access

Final Report of Piping Components for Organic Coolants

Description: Organic compounds with high boiling points and low corrosion qualities have been considered for use as reactor coolants and moderators. Those being considered, however, have a greater tendency to leak than does water. A program to evaluate mechanical closures to be used for a leak-tight system for organic fluids has been established. Report HW-59446 covered descriptions of the facility used in this study and the primary results of tests covering two liquids, fittings, and instrumentation. This … more
Date: January 12, 1960
Creator: Floyd, H. L.
Partner: UNT Libraries Government Documents Department
open access

Effect of Temperature on Uranium Recovery Columns Operation

Description: Some data on the temperature effect in pulse columns are reviewed. New data obtained with the "vibrational" stirrer are reported. The effects on both the dispersion and coalescence and the net rate of extraction suggest that improved operation of the RA column and lowered waste losses would be expected at elevated temperatures.
Date: August 12, 1953
Creator: Burger, L. L.
Partner: UNT Libraries Government Documents Department
open access

The Less Familiar Elements in the Atomic Energy Program

Description: Many factors are responsible for the rapid growth of analytical chemistry during the past ten to fifteen years. One of the most important of these factors is the greatly increased significance to present day chemistry of many elements that in the recent past were principally chemical curiosities. Since the Atomic Energy program is concerned with many such elements, it is of interest to discuss the cause for this concern and the resulting effect on the field of analytical chemistry. A number … more
Date: October 12, 1953
Creator: Bushey, A. H.
Partner: UNT Libraries Government Documents Department
open access

Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Description: Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Date: August 12, 1960
Creator: Wilburn, N. P.
Partner: UNT Libraries Government Documents Department
open access

Design Criteria of a Consumable Electrode Welder for Water Mixing Fuel Elements

Description: During the period when the writer mixing fuel element was being evaluated, a small Litton glass lathe and a General Electric Fillerarc welder were used to weld the mixing spool to the fuel element. Due to the condition of these units and to the numerous difficulties encountered with them, it was deemed necessary to design and procure a semi automatic welding unit which could weld in excess of three hundred fuel elements per day.
Date: May 12, 1959
Creator: Hanson. G. R.
Partner: UNT Libraries Government Documents Department
open access

Experimental Techniques for Determining Surface Energies of Solid Metals- A Literature Survey

Description: A knowledge of the surface tension of metals is a valuable tool in many aspects of physical metallurgy. Surface tension is a prime factor in such phenomena as swelling, nucleation and growth, and corrosion by liquid metals, and is also of importance in brazing. casting, and sintering. This survey was initiated to facilitate the selection of an experimental technique for determining the surface tension of uranium in support of current swelling studies of irradiated uranium. It is believed that s… more
Date: January 12, 1959
Creator: Laidler, J. J.
Partner: UNT Libraries Government Documents Department
open access

Dissolution of Stainless Steel Clad Power Reactor Fuels with Nitric Acid and Hydrofluoric Acid

Description: The processing of irradiated fuels from power and propulsion reactors is planned by Hanford Atomic Products Operation as part of the Atomic Energy Commission's interim reprocessing scheme. The several chemical processes proposed for the reprocessing of these fuels may be divided into two categories: first, total dissolution processes which dissolve both fuel element cladding and core material and, second, selective dissolution processes which dissolve either cladding or core material. The Nifle… more
Date: October 12, 1959
Creator: Cooley, C. R.
Partner: UNT Libraries Government Documents Department
open access

PRTR Calandria Fabrication Report

Description: The Plutonium Recycle Test Reactor is heavy water moderated with a heavy or light water reflector contained by a complex aluminum vessel called a Calandria. ( See Figure 1). Construction of this vessel started in August, 1958, at a large West Coast vendor's plant and was completed at Hanford in December, 1959. The fabrication problems associated with a high integrity welded aluminum vessel were generally unrealized prior to this period. This report covers the fabrication of the Calandria and li… more
Date: July 12, 1960
Creator: Pedersen, L. T. & Kreiter, M. R.
Partner: UNT Libraries Government Documents Department
open access

Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple

Description: Applications of sheathed (metal) thermocouples may require in many instances, the insertion of the thermocouple thermal junction into an area that must be hermetically sealed to the outside. This same area usually contains highly reactive heat transfer medium such as an eutectic alloy of sodium and potassium of sodium alone. When fissionable materials are being irradiated, fission products that are driven off would also be present and must be contained under varying temperatures and pressures.
Date: July 12, 1960
Creator: Kosut, Bert S.
Partner: UNT Libraries Government Documents Department
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