Abstract: A glass melter for vitrifying material including radioactive and hazardous materials. In one embodiment, the melter comprises an inner vessel or container having a solidified glass skull, at least one pair of vertically-oriented, retractable electrodes, a first wall spaced apart from said inner vessel to define a dry annulus therebetween for radiatively cooling the inner vessel, and a second wall spaced apart from said first wall to define a second annulus that serves as a water jacket when filled with water. Each electrode has a protective sleeve therearound with means formed therebetween for passing a purging gas therethrough. A central access nozzle allows waste material and glass formers to be fed into the inner vessel while simultaneously venting the off-gas generated in the inner vessel. Also, the dry annulus can have fluid circulating therethrough for regulated cooling or leak detection.

Abstract: A pipe restraint (20) permits thermal expansion of a piping system (10), while inhibiting movement of the piping system during dynamic events and providing vibration isolation. The pipe restraint includes first and second displacement members (22) and (24), which are interconnected by a restraining mechanism (32) for restraining displacement of the first and second displacement members relative to one another. The restraining mechanism includes first and second portions, which generally oppose one another relative to the central axis of the restraining mechanism. The restraining mechanism further includes third and fourth portions, which also generally oppose one another relative to the central axis of the restraining mechanism. The third and fourth members are offset circumferentially about the central axis from the first and second members. The first and second portions are connected to one of the displacement members, while the third and fourth portions are connected to the other displacement member.

Abstract: Disclosed is a transportation and storage assembly for transporting and storing nuclear fuel rod assemblies. The transportation and storage assembly includes a basket assembly (24) designed for failed nuclear fuel rod assemblies, or a basket assembly (122) designed for undamaged nuclear fuel rod assemblies. The basket assemblies (24, 122) are inserted into a canister (22). The canister (22) includes a shell (26) that receives and surrounds the basket assemblies (24, 122), and lids (28, 96) that enclose the shell (26). The basket assemblies (24, 122) include a plurality of apertured plates (36, 124) interconnected by structural members (42, 88) that maintain the plates (36, 124) in a spaced apart relationship, axially aligning the apertures (38, 126) in the plates (36, 124). In the basket assembly (24) for failed nuclear fuel rod assemblies, a container (44) is inserted into a row of axially aligned apertures (122), having a drain passage (104).

Abstract: A pipe restraint having a helical isolator (I.sup.1) coupled to a housing (16) and including a central cylinder (4) coupled to a central rod (2). Connecting rods (34, 36) are located at opposite ends of the restraint to attach the restraint between a pipe and an adjacent structure. Wire energy absorbing rope bights (32) are used to form the isolator I.sup.1. The bights (32) are placed in a state of precompression and have bi-linear spring properties which may be adjusted by adjusting the diameter of the housing (16) and spacer bar ( 30).

Abstract: A wire cable isolator and an associated energy absorbing restraint is provided for connecting between a device subject to movement due to dynamic loads and possibly thermal deflection, and an adjacent structure, such as a building or a support member. The isolator has predetermined, symmetrical force-deflection properties. The isolator includes first and second pairs of entrapment members, and a wire cable formed in a spiral. The first pair of entrapment members clamp the wire cable spiral at opposite side of the spiral and the second pair of entrapment members clamp the wire cable spiral at opposite sides of the spiral. The first and second pair of entrapment members are disposed at predetermined positions about an exterior periphery of the spiral.

Abstract: Disclosed is a transportation and storage assembly for transporting and storing nuclear fuel rod assemblies. The transportation and storage assembly includes a basket assembly (24) designed for failed nuclear fuel rod assemblies, or a basket assembly (122) designed for undamaged nuclear fuel rod assemblies. The basket assemblies (24, 122) are inserted into a canister (22). The canister (22) includes a shell (26) that receives and surrounds the basket assemblies (24, 122), and lids (28, 96) that enclose the shell (26). The basket assemblies (24, 122) include a plurality of apertured plates (36, 124) interconnected by structural members (42, 88) that maintain the plates (36, 124) in a spaced apart relationship, axially aligning the apertures (38, 126) in the plates (36, 124). In the basket assembly (24) for failed nuclear fuel rod assemblies, a container (44) is inserted into a row of axially aligned apertures (122), having a drain passage (104).

Abstract: A pipe restraint having a helical isolator (I.sup.1) coupled to a housing (16) and including a central cylinder (4) coupled to a central rod (2). Connecting rods (34, 36) are located at opposite ends of the restraint to attach the restraint between a pipe and an adjacent structure. Wire energy absorbing rope bights (32) are used to form the isolator I.sup.1. The bights (32) are placed in a state of precompression and have bi-linear spring properties which may be adjusted by adjusting the diameter of the housing (16) and spacer bar (30).

Abstract: A system and method (100,200) which uses a spreadsheet computer program having linked files in which the network architecture and the network element properties are entered and stored by the user. The overall network configuration information is input into a first, (INPUT) file type (102), which includes general parameters such as the battery terminal voltage, cable temperatures, bus (or node) names and bus interconnection information such as cable sizes and number of conductors per node. Cable impedance tables are available in a second, auxiliary (RESIST) file (112). Detailed loading information is entered in a third, (PANEL) file (128), which includes load description, load type (constant power or constant impedance), and load rating data and load status (on or off), which can be sequenced over time. These spreadsheets, or files, cooperate to automatically set up the appropriate YBUS admittance matrix file (120,124) and interactively compute voltages and currents using fourth type (CALC) files (122,126).