Abstract: An improved method for compression molding typically brittle, particulate ceramic materials comprising uranium dioxide in the manufacture of nuclear fuel products.

Abstract: Sound waves are generated in a sonic cell and propagated through a gas to a sensor which is coupled to a microcomputer. A gas mixture is first directed into a chamber and the attenuation and transit time of sound waves are calculated. Then, a calibrated gas is directed into the chamber, and the attenuation and transit time are again calculated. With these measurements, the microcomputer calculates the concentrations of at least two gaseous constituents such as hydrogen and water vapor, in the gas mixture. The microcomputer acts also as a control for operating valves and heater coils in response to pressure and temperature sensors coupled with the chamber.

Abstract: A rotary cylinder calcining system for treating tacky materials with a propensity to adhere to the surfaces of handling apparatus. The system comprises a reciprocating means for freeing the cylinder calciner outlet from any blockages caused by adhering material.

Abstract: A liquid level detector, or detector array, for insertion into the pressure vessel of a nuclear reactor, or into any liquid-containing vessel, for that matter. A coaxial cable supports the detector, which includes a sensing element having a positive temperature-coefficient of electrical resistivity. The detector is driven by a constant current source of electricity and the presence of liquid is determined by making a resistance measurement.

Abstract: Elongated members such as nuclear fuel end plugs are provided to a robot by a vibratory feeder. The robot singly inserts the members into a character stamper or marker and then removes them and drops them down a chute to an inspection site. The member is inserted into a character reader and inspected. Unacceptably stamped members are rejected and for each accepted member the stamper is advanced to a next character. Thus, a next member is stamped with the next character, or permutation of characters, the robot already having provided a new member to the stamper.

Abstract: In a coupling system for a nuclear reactor control rod and control rod drive, said coupling system being selectively uncouplable by an uncoupling rod, a system of passages for exercising a countervailing force on the uncoupling rod to prevent inadvertent uncoupling during scram.

Abstract: A fine-motion control rod drive for a nuclear reactor, which can be disassembled in sections. The drive includes a spindle defining a sealing surface to prevent spillage after the drive motor is removed. A spline connection with a sliding key arrangement permits the shaft of the drive motor to be separated from the spindle during disassembly. The drive motor is effective for uncoupling the control rod drive piston from the control rod prior to disassembly.

Abstract: A testable time delay apparatus includes means for testing component operation during any stage of system function and means for continuously monitoring and testing component functions. The device is particularly useful in critical process control applications such as in a nuclear reactor control system.

Abstract: A method and apparatus for determining the subcriticality of masses of uranium by directing epithermal neutrons toward said mass, isolating said material from external thermal neutrons, and measuring the ratio of thermal and epithermal neutrons to epithermal neutrons which enables the establishment of a subcriticality value representative of the mass of uranium.

Abstract: A microprocessor controls pressure transducer testing, calibration, and adjustment. A transducer or unit under test (UUT) receives a fluid pressure signal from a test line, and outputs a corresponding electrical signal. A test pressure is output from a fluid pressure module which is connected to the UUT. A human operator is interrogated by the microprocessor based control unit as to (1) identifying details about the desired pressure UUT to be tested, and (2) the anticipated electrical range to be encountered in reply to an applied test pressure. The microprocessor then sequentially generates electrical output signals which are sent to the test lines to generate the test pressure pulses from a fluid pressure supply. The pressure test pulses are delivered to the UUT. As the UUT receives the sequence of pressure test pulses, the microprocessor records the output electrical signals generated by the UUT, and compares them to an internal reference pressure transducer output.

Abstract: A self-contained modular nuclear reactor which can be prefabricated at a factory location, nuclear-certified at the factory, transported to a field location for final assembly and connection to a large-scale electric-power generating facility. The modular reactor includes a prefabricated nuclear heat supply module and a plurality of shell segments which can be assembled about the heat supply module and which provide a form for the pouring and curing of a cementatious biological shield about the heat supply module. The modular reactor includes passive shutdown heat removal systems sufficient to render the reactor safe in an emergency. A large-scale power plant arrangement is disclosed which incorporates a plurality of the modular reactors.

Abstract: In a fuel assembly for a nuclear reactor a fuel element spacer formed of an array of laterally positioned cojoined tubular ferrules each providing a passage for one of the fuel elements, the elements being laterally supported in the ferrules between slender spring members and laterally oriented rigid stops.

Abstract: A method is disclosed for the compaction of control rod blades and fuel channels of a boiling water reactor. Upper and lower portions of a control rod blade are removed from a cruciform shaped main blade structure. Each elongate tubular fuel channel of substantially square cross section is sectioned into four substantially congruent panels. A plurality of panels are stacked into each quadrant of the main blade structure substantially parallel to the long axis thereof.

Abstract: An apparatus for underwater separation of a jet pump beam from the inlet mixer of a jet pump in a nuclear reactor system. The apparatus underwater cuts a retaining piece coupling the beam with the inlet mixer.

Abstract: A testable physically isolated control circuit includes a first unit 10, a second unit 40, and an optical coupler 30 to couple units 10 and 40 together. The functional portion 10a of the first unit includes an input terminal 11 and an oscillator 12 for controlling a first transmitter 17. Signals from the first transmitter are received by a receiver 44 in unit 40 to control the relay 48. Each unit 10 and 40 also includes a testing portion 10b and 40b for monitoring the condition of the functional portions. The testing portion 40b detects the state of the receiver 44 and the relay 48 and transmits this information via transmitter 65 to a receiver 22 in first unit 10. This receiver 22 controls input terminals 29 and 15 to provide control information concerning the proper functioning of the circuit.

Abstract: A pressure sensitive, toroidal magnetostrictive core wound with primary and secondary coils providing inputs to self-checking circuitry for analyzing operability status and providing redundant pressure measurement options is described. Pressure sensing assemblies are presented which are useful for measuring hydrostatic pressure or concentrated loads.

Abstract: A testable physically isolated control circuit includes a first unit 10, a second unit 40, and an optical coupler 30 to couple units 10 and 40 together. The functional portion 10a of the first unit includes an input terminal 11 and an oscillator 12 for controlling a first transmitter 17. Signals from the first transmitter are received by a receiver 44 in unit 40 to control the relay 48. Each unit 10 and 40 also includes a testing portion 10b and 40b for monitoring the condition of the functional portions. The testing portion 40b detects the state of the receiver 44 and the relay 48 and transmits this information via transmitter 65 to a receiver 22 in first unit 10. This receiver 22 controls input terminals 29 and 15 to provide control information concerning the proper functioning of the circuit.

Abstract: An apparatus is disclosed which measures forces resisting the movement of pistons in a control rod drive mechanism in a nuclear reactor and which includes pressure sensing means and further includes hydraulic circuitry to divert pressurized fluid from a normal operating conduit to a selected shunt conduit containing a valve having a particular fluid control characteristic, said shunt conduit directing the fluid to a selected piston to move said piston and said pressure sensing means measuring the pressure of the fluid during the motion of said piston to give an indication of the force needed to achieve such motion.

Abstract: A testable load driving circuit apparatus includes a solid-state load driver for controlling AC current loads coupled in series with a winding of a saturable core reactor used for sensing the presence or absence of load current through a load current monitor which is coupled to another winding in the reactor. The load driving circuitry may be tested during circuit operation by injecting a signal of insufficient duration to substantially affect the load circuit.

Abstract: A jet pump plug for a multi-nozzle jet pump is disclosed wherein the nozzles are accessible through a relatively small opening in the pump structure. The plug comprises a plurality of sections, each including a closure plate and a lever coupled thereto. Each plug section is constructed so as to allow that section to be separately introduced into the opening to the vicinity of the nozzles from a location which may be remote from the pump. The closure plates are manipulated through their attached levers from a remote location to the end of sealing the nozzles with them. The first plug section introduced through the opening includes means for alignment relative to the jet pump structure so as to orient its closure plate with respect to the nozzles. The remaining plug section is supported by the first plug section upon being introduced into the opening.