Beryllium is a metal sensitive to machining damage, causing a loss in mechanical properties. Since some mechanical abrading is often used in surface preparation for mounting strain gages, it is desirable to know whether the abrading produces flaws. Metallographic study of beryllium subjected to four different surface preparation methods was carried out. It was determined that the gentle abrading necessary for affixing strain gages produced a negligible density and depth of flaws and did not lower the mechanical properties. 5 figures, 2 tables.

During the fifteen months that the Argus laser facility has been operating we have had two primary goals. These are: (1) to provide focusable, well characterized, high power beams for laser fusion experiments and (2) to further understand the propagation of high power and energy pulses. The propagation experiments have already led to increases in the laser output power and system reliability. Pulses appropriate for advanced targets are shaped to optimize the compression and heating of the target. In general they stress the laser in both limits of energy and power. In this work several results significant to the laser fusion program were realized. The neutron output of fusion targets increased by almost two orders of magnitude to more than 10/sup 9/ neutron/shot. An improved beam propagation technique (image relaying) was developed and partially implemented. It increased the focusable output power for short pulses (30-100 ps) to more than 4.0 TW. More than one kilojoule/beam was extracted from the laser in a high quality beam in a one nanosecond Gaussian pulse. A complex two step optical pulse was generated and successfully amplified to peak powers of more than 3.0 TW. The most recent of the system upgrades are complete image …

A variety of x-ray imaging techniques have been used to study the absorption, transport and implosion characteristics of exploding pusher microsphere targets irradiated with 1.06 ..mu..m light. Multichannel grazing incidence reflection microscopy, zone plate coded imaging and spatially resolved x-ray spectroscopy have observed the thermal and suprathermal x-ray emission associated with these phenomena. A second generation of x-ray imaging devices, designed for forthcoming high density implosion experiments, including axisymmetric x-ray microscopes and 1- and 2-D crystal line imaging devices, will also be briefly discussed.

Lists of documents exchanged during the first half of 1977 under agreements between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the governments of France, Federal Republic of Germany, and Japan are presented. During this period, the NRC received 41 reports from France, 29 from F. R. Germany, and 24 from Japan, and in return sent 107 U.S. reports to each of these three countries.

The analysis encompassed identification and analysis of potential threats to canister integrity arising in the course of waste solidification, interim storage at the fuels reprocessing plant, wet and dry shipment, and geologic storage. Fabrication techniques and quality assurance requirements necessary to insure optimum canister reliability were considered taking into account such factors as welding procedure, surface preparation, stress relief, remote weld closure, and inspection methods. Alternative canister materials and canister systems were also considered in terms of optimum reliability in the face of threats to the canister's integrity, ease of fabrication, inspection, handling and cost. If interim storage in air is admissible, the sequence suggested comprises producing a glass-type waste product in a continuous ceramic melter, pouring into a carbon steel or low-alloy steel canister of moderately heavy wall thickness, storing in air upright on a pad and surrounded by a concrete radiation shield, and thereafter placing in geologic storage without overpacking. Should the decision be to store in water during the interim period, then use of either a 304 L stainless steel canister overpacked with a solution-annealed and fast-cooled 304 L container, or a single high-alloy canister, is suggested. The high alloy may be Inconel 600, Incoloy Alloy 800, …