Abstract: Male and female members for contact lenses where either member is able to hold the contact lens as it moves from station to station during the hydration process. The female member fits together with the male member forming a chamber. Each of the members contains a line centrally located so that both surfaces of the contact lens are flushed during the hydration process, and drainage takes place radially on the outside of the mated male and female chamber members. These members may be produced on a frame with a plurality of members, usually eight to a frame, to allow ease of processing. Full automation is possible, and complete and positive lens control during any step of the process through the packaging step is achieved.

Abstract: A process for releasing leachable substances from a polymeric contact lens blank. the contact lens is confined in a cavity within a carrier to permit the hydration of the lens without permitting it to invert or roll over. A fluid flow is introduced into the cavity about the lens to extract leachable material from the lens. The process significantly reduces the amount of leaching fluid that is used and the amount of time that is needed for hydration, washing and extraction.

Abstract: A nuclear reactor refueling system for a liquid metal-cooled fast breeder reactor includes a large rotatable plug (18) eccentrically mounted relative to the reactor core (12), and a small rotatable plug (24) mounted within the large plug (18). A fuel handling machine (28) is rotatably mounted upon the small plug (24), and the eccentric mounting of the large plug (18) permits the fuel handling machine (28) to access all areas of the reactor core (12) as well as a fuel transfer station or port (34) located externally of the reactor core barrel (16) yet internally of the reactor pressure vessel. A unique six-fingered star-shaped upper internals structure (36) is eccentrically mounted upon the large plug (18) so as to be concentrically disposed relative to the core (12) when the reactor is in operation yet permitting access to the central-most fuel assemblies (14) of the core (12) as the large rotatable plug (18) is rotated during refueling operations.

Abstract: Cask-like steel container for one-site storage, later-shipment and permanent disposal of low-level-radiation nuclear waste material. Container has configuration of a hollow cylinder with heavy walls. Bottom portion of container is affixed to cylindrical sides with a double weld. Steel top member has an annular recess as does the top portion of the cylindrical sides, with hermetic, radiation-resistant gasket material included therebetween, and the container top and sides are bolted together. The top member has spaced heavy eyelet-like members affixed thereto for handling the container.

Abstract: Disclosed is a system for handling, transporting, and disposing of low level radioactive waste materials which utilizes reusable, separate, and removable lifting means and tie-down means. Mechanical design of the lifting means and hold-down means prevent the inadvertent use of either for the improper purpose.

Abstract: Disclosed is a low temperature technique for annealing implantation damage and activating dopants. Conventional furnace annealing requires temperatures as high as 1000.degree. to 1100.degree. C. to completely anneal the dopant implantation damage; 75 KeV arsenic implantation followed by 550.degree. C. for 75 minutes and 900.degree. C. for 30 minutes in nitrogen for instance is not sufficient to anneal the implantation damage and results in a leakage current of the order of 1 mA per cm.sup.2. If, however, subsequent to the arsenic implantation, 0.4 KeV hydrogen ions are implanted using a Kaufman ion source with an accelerator current of 200 milliamp, then only 500.degree. to 600.degree. C. for one hour anneal in nitrogen is sufficient to eliminate the arsenic implantation damage. This results in a leakage current of the order of 5 to 25 nA per cm.sup.2 and a complete dopant activation is achieved.