Abstract: A method and system for providing secure communication between a server and a remote client utilizing a polymorphic software platform. In various embodiments, the system provides mixed mode data entry, meaningless field entries and randomly generated false entries interpolated into the real entries for providing a secure system of communication such that a third party has no repeatable method of decoding the information transmitted.

Abstract: A harness used for restraining a horse or other animal during training and grooming is disclosed. The harness consists of an upper strap connected to a lower strap. The strap is placed around the front legs of the horse by a buckle. The upper strap is placed over the front shoulder of the horse.

Abstract: A method and system for providing secure communication between a server and a remote client utilizing a polymorphic software platform. In various embodiments, the system provides mixed mode data entry, meaningless field entries and randomly generated false entries interpolated into the real entries for providing a secure system of communication such that a third party has no repeatable method of decoding the information transmitted.

Abstract: A clinical information reporting system for use with an electronic database for a health care facility, the electronic database being a rotational and modular database for the provision of a scalable and extensible configuration preferably consisting of a workstation as the base configuration and being configurable for use in small and medium network situations and being particularly adapted for the receipt, manipulation, modification and generation of cardiology reports such as resting ECG records and stress ECG records.

Abstract: An electrolytic process and apparatus for reducing calcium oxide in a molten electrolyte of CaCl.sub.2 -CaF.sub.2 with a graphite anode in which particles or other contamination from the anode is restricted by the use of a porous barrier in the form of a basket surrounding the anode which may be removed from the electrolyte to burn the graphite particles, and wherein the calcium oxide feed is introduced to the anode compartment to increase the oxygen ion concentration at the anode.

Abstract: A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a Cu--Mg alloy containing not less than about 25% by weight Mg at a temperature in the range of from about 750.degree. C. to about 850.degree. C. to precipitate uranium metal and some of the noble metal fission products leaving the Cu--Mg alloy having transuranium actinide metals and rare earth fission product metals and some of the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel.

Abstract: A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800.degree. C. to about 850.degree. C. to produce additional uranium metal which dissolves in the U-Fe alloy raising the uranium concentration and having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel.

Abstract: A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800.degree. C. to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein.