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>The materials problems associated with the present sodium graphite reactor system have generally been approached by using existing knowledge and data to meet the proposed operating conditions. This discussion reviews the general reactor concept and the specific materials used for the major reactor components: (1) shielding materials; (2) core materials; and (3) sodium cooling system materials. In each case, the materials problems and the materials used to minimize or eliminate these problems are described. Economical nuclear power is currently dependent on the flow of improved materials for high temperature use in high radiation fields. Rapid progress is being made in this respect. (auth)

The purpose of this report is to present a semi-quantitative discussion of the effect of the heat capacity of the process tube assembly on the outlet water temperature following a mild inadequate cooling incident involving an entire reactor.

The purpose of the work documented herein was to correlate a new sensitive scintillator for the measurement of gamma dose rates from the reactor effluent isotopic spectrum in the Columbia River. Previous scintillation devices lacked the desired sensitivity for estimating these dose rates. A portable scintillation device was calibrated against ionization chambers over essentially full range of dose rates from the reactor effluent spectrum in the Columbia River. A river survey was then made, combining scintillator readings with pulse pencil and portable instrument readings from 1--1/2 miles above the reactors to about 57 miles downstream. 2 figs., 2 tabs.

Procedures for the dissolution of U-Mo alloy fuels to prepare feed solutions for low-acid (Redox) type solvent extraction processing are presented. U-Mo alloys can be dissolved in boiling ferric nitrate--ritric acid solutions to higher terminal urarium concentrations and lower terminal acidities without precipitation of uranyl molybdate than in nitric acid alone. Anion resin exchange studies indicate the presence of negatively charged iron-molybdenum complex ions in the solutions. The U-Mo alloys also dissolve more rapidly in ferric nitrate--nitnic acid solutions than in nitric acid alone; dissolution rate data are given. Curves delineating free acid, uranium, snd iron (III) concentrations within which solutions stable towards solids formation can be prepared from U-3 wt.% Mo and U-10 wt.% Mo alloys are presented. Stability during prolonged storage of uranium--molybdenum-ferric nitrate--nitric acid solutions is discussed. Data on the oxidation of plutonium in these solutions and on further neutralization of the solutions are presented. Fission product decontamination and product recovery obtained in solvent extraction studies simulating the Redox process are discussed. (auth)

A compilation of 290 references on gas bearings is presented. In most cases an English resume' of each reference is included a translation being made when required. The references are arranged alphabetically by first author. Indexes included are the year of origin corporate author, subject, patent number, and country of origin. (J.R.D.)

This is the monthly report for the Hanford Laboratories Operation, August, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities, visits, biology operation, physics and instrumentation research, employee relations, and operations research and synthesis operation are discussed.

Separate abstracts have been prepared on the papers presented at this conference. (C. H.)