The process of age calculation for Hanford exponential lattices containing aluminum-matrix slugs, where the sums run over the materials of the lattice cell.

The results of electrical resistance measurements have been used as a means of following changes occurring in metals due to irradiation. The electrical conductivity is sensitive to changes in composition and to cold-work or structure damage. In an anisotropic metal, such as uranium, the director of measurement also influences to some extent the values obtained. For these reasons it is essential to use the same material, and if possible the same piece of material, in comparing the electrical properties before and after irradiation. This report is a description of the measurements made on pieces of the same uranium rod before and after an exposure of approximately 150 MWD/T. The results, while preliminary in nature and dealing only with one sample and exposure level, provide data for which a comparison may be made of the electrical resistivity of irradiated and non-irradiated uranium metal.

For some time, the need has been recognized for an X-ray diffraction unit applicable to studies concerning the crystallographic characteristics of pile irradiated materials. Except for studies involving specimens of low activity, it has been impossible in the past to investigate materials which emit intense beta and gamma radiations. The exact type and degree of irradiation damage to high activity materials has been largely a matter of theoretical conjecture. The object of this report is to describe an X-ray diffraction spectrometer that can be used to collect crystallographic data from irradiated materials.

When an aqueous solution containing dissolved irradiated uranium and nitric acid is equilibrated with 30% tributylphosphate solution in kerosene, the distribution co-efficients for sirconium and niobium are decreased by the addition of phosphoric acid to the system.

Three types of stainless steel (309 SCB, Carpenter 20, 304-L) were exposed to both the liquid and vapor phase of each of three types of solutions. The time of exposure totaled ten days during which the specimens were cleaned and weighed periodically. The three synthetic D-12 waste solutions contained respectively chrome-high chloride, chrome-low chloride and high chloride sans chromium. The solutions were renewed at each weighing.

This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).

The first of two general methods are discussed based on the removal of the thin layer of aluminum to which graphite adheres. Two electro-polishing techniques, an electrolytic etch, an anodization-deanodication cycle and two chemical etches are described.

An improved method for the determination of boron in plutonium is reported. Precipitation of plutonium (III) acid oxalate prior to color development with curcumin results in increased precision, greater speed, and lower costs. Results are presented of a statistical study involving all variables.

Impurities are separated from plutonium solutions by means of TTA (thenoyltrifluoracetone) extractions. Plutonium in hydrochloric acid solution is reduced to the trivalent state with hydroxylamine, and some impurities are extracted into hezone or a solution of TTA in hezone. The organic phase is removed, and the plutonium in the aqueous phase is oxidized to the tetravalent state with nitric acid. Investigations of several variables which affect the extraction are described..

The uranium recovery processes which are in operation or under construction at the present time--TBP, Redox and Purex--yield an aqueous uranyl nitrate solution as the recovered uranium product. For conversion of this recovered uranium to UF6 for feed to the gaseous diffusion plants, the uranyl nitrate in the solution is concentrated with or without prior organic stripping, calcined to UC3, reduced to UO2 with hydrogen, hydro-fluorinated to UF4 with RF, and finally fluorinated to UF6 with elemental fluorine.

Report discussing the manual and automatic welding techniques for fuel elements containing plutonium with Zircaloy-2 aluminum, and stainless steel cladding, 0.013 to 0.0889 cm (0.005 to 0.350 in.) thick" (p. 3).

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.

Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems.

Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.

This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.

Describes the current prototype model of a linear amplifier, two-channel pulse-height analyser, two-channel count-rate meter, and count-rate difference detector for a gamma-ray spectrometer monitor developed to approach the above design criteria.

To set forth limiting values of internal vapor pressure and effective liquid specific gravity which will permit the maximum utilization of the existing underground waste storage capacity. It is also intended to describe briefly the elements which could contribute to ultimate failure.

Series of isothermal transformation studies for improvement in fabrication and reactor performance of uranium fuel elements.

Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.

A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.

Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.

Report that describes graphite oxidation monitors and their proper storage and handling, as well as the losses encountered when moving the monitors between the laboratory and the reactor.

Report describing Hanford Laboratories' second report regarding thin wall tubing tests. This part covers "the production [of] test equipment developed, its operation, and test results" (p. 2).