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.

The following report provides data collected during an investigation in the Columbia River. The purpose of this investigation was to research the radioactivity present in the bottom-living organisms of the river.

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.

Report discussing studies regarding the properties and nuclear constants of xenon, an element relevant to use of high power thermal neutron reactors.

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.

Report discussing studies regarding active atmospheric particles in several United States cities. Experimental data of particles collected in filters is given.

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."

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.

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).

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.

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 disposition of contaminated major processing equipment at Hanford Atomic Products Operation during 1958-1959 and a listing of 1) equipment buried, 2) equipment stored, to be buried or decontaminated, and 3) equipment decontaminated and returned to service.

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 decontaminating present reactor pigtails by different methods. (3) Areas that need further study.

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 report will cover final results and other pertinent information.

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.

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 of pertinent analytical research problems at Hanford will be cited as examples.

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.

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.

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 swelling in uranium in support of current swelling; studies of small bubbles of fission gases (krypton and xenon), and the forces resisting the expansion of these bubbles are the elastic and plastic flow energies and surface tension of the metal. Experimental techniques for the determination of surface tension of solids are still in the development stage, but three techniques appear to be most feasible. These methods are: (1) the mechanical method, in which a tensile lead is used to counterbalance the contractile force of surface tension; (2) the thermal etching method, involving measurement of the dihedral angle at the root of etched grain boundaries; and (3) the electron diffraction method, which analyzes surface tension by the amount of lattice distortion it …

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 Niflex process uses a nitric and hydrofluoric acid solution for the total dissolution of stainless steel clad uranium fuel elements.

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 lists recommendations for improving the design and reducing the cost.

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.