Abstract: Apparatus for delivering energy and material, such as electricity, air and fluid, from a source (22) to a driven device (24). The apparatus (20) comprises at least one flexible elongated member (26) selected from the group of electrical conductors, air hoses, fluid hoses and the like. The elongated member has a feed portion (114) with a feed end (42) connectable to the source, a slack portion (118), a supply portion (120) with a supply end (43) connectable to the driven device, a first portion (128) between the feed portion and the slack portion, and a second portion (134) between the slack portion and the supply portion. The apparatus also includes a stationary hub (74) and a spool (78) connected to the hub. The spool is rotatable between stored and deployed conditions relative to said hub. A winding wall (82) on the spool is spaced away from the hub and has an internal surface (86), an oppositely disposed winding surface (88), and an aperture (90) extending therethrough.

Abstract: An enclosed cutting zone for use in a nuclear power plant. The cutting zone includes a cutting zone barrier and a transfer zone. The cutting zone includes a movable submergible upper rig, an upper inflatable ring supported by the submergible rig; a lower inflatable ring supported by the submergible rig; and a means for coupling the vertically extending edges of the submergible upper rig to form a cutting zone barrier having enclosed sidewalls. The transfer zone includes a movable, submergible upper rig; an upper inflatable ring supported by the submergible rig; and a lower inflatable ring supported by the submergible rig. The transfer zone is coupled to exterior surface of the cutting barrier so as to form a structure having enclosed sidewalls and an open top.

Abstract: In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

Abstract: An augmented cooling system for a CEDM in a nuclear reactor includes self actuated louvers or flap valve louvers which allow hot air from the head lift rig to vent and cooler ambient air to enter the rig in the event that pressure is lost for the forced cooled air which normally cools the CEDM.

Abstract: A surface scanner for conducting non-destructive inspection of complex surface structures and configurations. The scanner includes two flexible tracks, each fitted with a motor driven tractor assembly. A rigid beam track spans the two flexible tracks. The rigid beam track is coupled to each flexible track tractor assembly by articulating joints that permit movement at the joints along at least three independent axes. The rigid beam supports a third motorized tractor. This third tractor supports a compliant thruster assembly that deploys gimbaled mechanical impedance, ultrasonic and eddy current inspection probes. The movement of the scanner is controlled by a scan control system that includes both hardware and software for controlling the movement of the scanner over the surface to be inspected.

Abstract: A valve control apparatus for generating an anticipatory output response for controlling a fluid flow in a fluid flow line includes a valve provided inside the fluid flow line, at least one sensor for providing at least one input signal, said at least one input signal responsive to properties of said fluid flow in advance of said valve, and a letdown back-pressure controller receiving said at least one input signal and providing a tunable output signal for selectively opening and closing said valve to vary flow in the flow line responsive to said at least one input signal.

Abstract: An improved heated junction thermocouple cable arrangement for use with a nuclear reactor heated junction thermocouple having sensors with an unheated thermocouple, a heated thermocouple, and a heater coil, shares power conductors between multiple heater coils. The thermocouple conductors are separated from the power conductors to eliminate the possibility of interference with the thermocouple conductor signals. The heater coils are ganged in parallel and if one heater coil fails, power is still supplied to the remaining heater coils connected to a pair of power conductors.

Abstract: A flexi-rail assembly for supporting and positioning tools for inspecting a nuclear power plant steam generator. The flexi-rail assembly includes a housing; at least one lock assembly carried by the housing for coupling the housing to a support structure; and a carriage assembly movably supported by the housing for supporting and positioning inspection tools such as a robot manipulator arm and leg assembly. The housing includes a hollow rear portion for receiving at least one cylinder supporting a movable surface, wherein the cylinder is coupled to a source of pressurized fluid. The housing also supports at least one recessed surface for receiving the lock assembly. The lock assembly includes the cylinder and at least one tubular member. The tubular member includes an open center and at least two openings formed in the surface of the tubular structure.

Abstract: An automatic self-testing system includes a plurality of sensor processing channels or paths each having a sensor for providing, either directly or indirectly, a digital value to a comparator which compares the measured value with predetermined value that is, in turn, provided to coincidence logic that evaluates the output of its comparator with the output of the comparators of the other paths to provide an output indicative of a pass/fail condition. Each sensor processing path includes two sub-paths that can be associated with or switched into the processing path while the disassociated sub-path undergoes off-line testing by a test processor. Testing is effected by providing a digital value to the sub-path under test while sensing the output to determine the functional validity of the sub-path under test. The combinational logic state of the system is monitored and converted into a decimal value that is compared with the set of decimal values corresponding to the finite known-good logic states of the system.

Abstract: A nuclear reactor coolant system includes a primary coolant circuit connected to a secondary coolant circuit. A desired amount of coolant is bled from the primary circuit to the secondary circuit for purification and controlling chemical composition of the coolant. Variable speed charging pumps are provided in the secondary circuit to pump coolant back into the primary circuit at variable pressures and flow rates. A pressurizer level control system is also disclosed for controlling pump speeds.

Abstract: A magnetic filtration system for separating radioactive cut material from a fluid stream containing a mixture of the radioactive cut material and an abrasive cutting material. The system comprises a magnetic filter in fluid communication with the fluid stream. By selecting an abrasive cutting material having a different magnetic susceptibility than the radioactive material being cut, the abrasive cutting material can be separated from the radioactive cut material with the magnetic filter. The amount of high level radioactive material is thereby reduced for handling and disposal. The magnetic filter is part of a closed-loop system that extracts a fluid stream containing a mixture of abrasive cutting material and radioactive cut material from an enclosure in which an abrasive waterjet cutting tool is operated. Other filters are provided in the system for removing the radioactive cut particulate from the fluid stream in multiple stages according to a size of the particulate.

Abstract: A nozzle cap for sealing a nozzle which penetrates a nuclear reactor vessel, and a method of using such, is provided, and includes a closure portion suitable for closing an open end of the nozzle under pressure associated with the nuclear reactor vessel, a skirt portion that is cylindrically formed beneath the closure portion, a flexible element that is secured to the skirt portion and may include concave portions to accommodate vibration movements between the nozzle and the nozzle cap, and a weldment lip that is secured to the flexible element, and welded to the nozzle.

Abstract: To prevent damage to the electrical connections between PLC modules and a backplane during seismic and other vibrational disturbances, a bracket is used having two parallel side members attached to the backplane and a lower support bar connected between the side members to support the PLC modules in the vertical direction. An upper support bar may also be provided between the side plates to hold the PLC modules in the bracket and further prevent vertical movement. The upper and lower support bars may also provide vertical members or a rest in contact with the PLC modules and having a high coefficient of friction to prevent lateral movement of the PLC modules with respect to the backplane.

Abstract: A canopy seal clamp assembly (40) for stopping leaking in a canopy seal weld (42) located between a nuclear reactor vessel nozzle (30) and an elongated housing (24) includes an upper plate (44) having a central aperture (50) and an inner flange (52) spaced apart from a lower plate (60) having a central aperture (66) and an inner flange (68), a seal carrier (70) located adjacent the lower plate carriers a seal (72) for contacting an outer surface of a leaking weld (42) and connector (56) between the upper and lower plate maintain a compressive load to tightly seal the leaking weld and the compressive load tends to close and arrest further crack propagation in the weld. A method for repairing a weld is also described.