Tests of subsize tensile and impact specimens of Type 547 stainless steel irradiated in three capsules to fastneutron exposures of up to 1.1 x 10/sup 22/ nvt were conducted. Ductile fractures at impact energies of 65 ft-lb, representing a 35% decrease in impact strength, were noted at room temperature. Impact energies of approximates 20 ft-lb and a fracture with both brittle and ductile characteristics were observed at -300 deg F. Irradiation-induced property changes included increases in yield strength from 35,000 to 105,000 psi and in ultimate strength from 90,000 to 112,000 psi and a decrease in total elongation from 63 to 31% at room temperature. A 600 deg F anneal produced no measurable recovery of preirradiation properties for periods up to 144 hr, but a large degree of recovery was obtained by annealing 1 hr at 1800 deg F. In material irradiated at 750 deg F, increases in yield strength from 55,000 to 149,000 psi and in ultimate strength from 92,000 to 149,000 psi, decreases in elongation from 55 to 10%, and reductions in area from 70 to 60% were observed. (H.G.G.)

Reactions with water of as-cast uranium-carbon alloys containing 2to 10 wt% carbon (UC/sub 0.4/ to UC/sub 2.2/) were investigated by using gas- chromatography for analysis of the gaseous products. Uranium metal-uranium monocarbide alloys yielded 2 moles of free hydrogen per mole of free metal, in addition to methane, small quantities of higher molecular weight gaseous hydrocarbons, and a solid, hydrous, tetravalent uranium oxide. The gaseous producte contained all the carbon originally present in the alloy. Uranium dicarbide (UC/sub 1.86/; this combined-C/U atom ratio was the maximum which could be obtained) yielded a mixture of 38 hydrocarbons (methane, 15 vol%; ethane, 28%: C/sub 3/- to C/sub 8/-alkanes, 7%; alkenes, 8%; alkynes, 0.6%; and widentified unsaturates, 1%), free hydrogen (40 vol%), a water-insoluble wax, and a solid, hydrous, tetravalent uranium oxide. Forty% of the combined carbon was found in the gas and 25% in the wax. The gaseous products from the hydrolysis of both UC and UC/sub 1.86/ were not affected by changes in the reaction temperature between 25 and 99 deg . The composition of the gases evolved at 80 deg from as-cast alioys with compositions between UC and UC/sub 1.86/ varied linearly with the combined-C/U atom ratio of the alloy; …

The nuclear star density produced by a 24-Bev proton beam in a material having approximately the properties of heavy concrete is calculated. A comparison is made with experimental measurements made at CERN; but, since the quantity that can be calculated is not the same as that measured, no firm conclusions can be drawn. Proton, neutron, pion, and muon intensities are plotted vs. distance as are star densities. (auth)

The purpose of this program is to determine the extent to which Zr-2.5Nb and Zr-2.5Nb --0.5Cu exhibit delayed failure (static fatigue) under various conditions of hydrogen content, heat treatment, and ambient temperature. Specimens are hydrogenated to 200 ppm or 500 ppm by means of a modified Sieverts apparatus, heat treated or cold reduced, and then evaluated in dynamic tensile and delayed failure tests under a certain set of conditions. At the present time, data are insufficient to form any conclusions regarding static fatigue behavior of these alloys. (auth)

This report, from the Chemical Processing Department at HAPO for December 1962, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations; and weapons manufacturing operation.

During the early part of CY-1961, water leak frequency on plant began to pose a mounting problem. At this time, DR reactor exhibited a leak mechanism which, although observed to some extent at other reactors, appeared to be primarily a DR problem. This mechanism can best be described as a trench running longitudinally along the top portion of the process tube. The dimensions vary considerably; however, the lengths attained were generally about two to there feet and the width was roughly one inch. The beginning of the trench appeared to be mainly in the position of 11 to 14 feet fro the rear Van Stone flange. The radial position of the trench in the tube runs from about the 10: 30 to the 2:30 o`clock position. For lack of a more definitive expression for this corrosion, it will be referred to as a form of ``accelerated local corrosion.`` This report deals entirely with one possible means of affecting accelerated local corrosion. A layer of gaseous air coming from the dissolved air in the process water could form a heat transfer resistant area. This area would probably exhibit an accelerated corrosion rate due to the higher tube wall temperatures resulting.

This production test authorized the irradiation of 1.6% enriched single tube elements in KER-1 and 2. This document provides the process tube loading, operating limits, and water shutoff times for the charge.

The metastability of alpha plutonium above the {alpha} {r_equilibrium} {beta} equilibrim transformation temperature (112 C) was studied by metallographic techniques. The purpose of this study was to extend the previous work on the {alpha} {yields} {beta} transformation which was accomplished using fluid displacement techniques{sup 1} and to obtain a basis for determining the length of time the alpha phase is stable at high temperatures. Approximate isothermal reaction curves were determined experimentally and an {alpha} {yields} {beta} time- temperature-transformation (T-T-T) curve was derived.

The transformation of retained phases of plutonium of different quality has been determined over a period of 10--12 months, by observing the density variation with time. A large density increase of each specimen was observed. The density increase of the low quality metal was the greatest and that of the highest quality metal was the least. The magnitudes of these increases are apparent from the graphs. One of the specimens fractured into two pieces after ten months. Also, surface cracks appeared in two of the other specimens. The fractured surfaces probably originated from the stresses associated with the transformation of retained phases or possibly from stress corrosion. The density increase with time was the same for the as-cast and cold treated specimens.

Sheline and Johnson made Mg28 through the reactions Si30(γ,2p)Mg28 and Mg26(α,2p)Mg28 in order to characterize and determine a decay scheme for the new nuclide. Lendner separated a magnesium fraction from the spallation products of the irradiation of chlorine, as sodium chloride, with 340-MeV protons. The 21-h activity that was present was deduced to be Mg28 from the 2.3-m half-life of the Al28 that was milked from it, as Sheline and Johnson had done.