Tests were made to determine the effects of heat treatment and composition on the corrosion resistance of low-uranium, zirconium-base alloys to water at 600F. A total of 57 compositions were tested. The zirconium alloys contained up to 9% natural uranium plus small amounts of tin, antimony, lead, bismuth, yttrium, beryllium, germanium, niobium, nickel, and aluminum in various combinations. Data are presented in both tabular and graphical form. The effect of heat treatment on corrosion resistance of zirconium-uranium-tin alloys is partially masked by impurities in alloys made from sponge or bomb-reduced zirconium. In ternary alloys made from crystal bar zirconium, the effect of heat treatment on corrosion resistance is definite, and varies with the composition of the alloy. The range of ternary compositions from approximately % to 6 weight-per cent uranium and from 2 to4 per cent time, are the most attractive fuel element core alloys.

On October 7, 8, and 9, 1953, the Atomic Energy Commission Division of Reactor Development held a reactor information meeting at the Argonne National Laboratory. The objective of the meeting was exchange of information among people actively concerned with the design of reactors for power to the end that the power reactor program would move more speedily and more economically to another milestone of success. In this volume all the papers presented at the meeting are listed. Copies are given of those papers which are available, and references to published reports are indicated where know for those papers not included in this collections. In order to facilitate handling, this volume is being issued in six parts: Part I Power Reactors; Part II Reactor Physics. Critical and Exponential Experiments Measurements; Part III Reactor Components. Reactor Economics Considerations. Reactor Safeguard and Control; Part IV Fuel Element Design and Problems. Corrosion and Chemistry; Part V Heat Transfer; Part VI Processing. The Author Index is being bound and distributed with Part I of this volume.