Abstract: A steering column support for a motor vehicle includes a steering column unit, a cross member supporting the steering column unit, at least one reinforcing strut connected with the cross member, and a receiving element for a knee restraint connected with the reinforcing strut(s) and the steering column unit. The steering column support controls and prevent undesirable vibration of the steering wheel.

Abstract: A suspension and steering linkage for a front wheel of a tricycle type vehicle includes an upper and lower control arms joined by a pivot arm. The control arms are parallel and of the same length and are pivoted at the vehicle so as to move together in vertical arcuate movement with the wheel. A steering linkage engages the pivot arm to rotate the wheel about a near vertical axis. The wheel is mounted to exhibit camber when turned for steering. A shock strut is positioned at a distal end of the upper control arm and moves in reaction to vertical displacement of the wheel. Its position is such as to enable the shock to move through a reduced excursion with respect to that of the wheel.

Abstract: A steering wheel position adjusting apparatus including a fixed tubular column, a movable tubular column movably mounted on the fixed tubular column, a lower rotational output steering shaft mounted within the fixed tubular column, and an upper rotational input steering shaft mounted within the movable tubular column and having upper and lower ends. The upper rotational steering shaft is connected at the upper end thereof to the manually operated steering wheel, and is connected at the lower end thereof to an upper end of the lower rotational steering shaft. The upper rotational steering shaft is movable with respect to the lower rotational steering shaft. An annular shaped ultrasonic motor is mounted on the outer periphery of the fixed column, the annular shaped ultrasonic motor being coaxial with the fixed tubular column and includes an output gear.

Abstract: In a boiling water reactor having a core shroud disposed within a reactor vessel and a plurality of tie rods installed between vertically spaced sites on the core shroud as part of a core shroud repair, a method of measuring tie rod preload after installation includes the steps of lowering a tool into the reactor vessel from a remote location positioned externally of the reactor vessel, attaching the tool to an upper portion of a tie rod, using the tool to apply a tensile load along a longitudinal axis of the tie rod, measuring the tensile load applied to the tie rod, measuring axial displacement of the tie rod in response to the applied tensile load, plotting the applied load versus the axial displacement measured, and identifying a change in slope on the load-displacement plot occurring at a load corresponding to the tie rod preload.

Abstract: A fuel bundle assembly for a nuclear reactor includes a modified channel and a handle unit that improves pressure drop performance. With the modified channel, one approach is to vary the outside dimension of the fuel channel along the length of the channel, but maintain a constant channel wall thickness. Another approach is to maintain the external dimensions of the fuel channel and vary the wall thickness along the length of the channel. The handle unit is formed including a handle member and a separate rod support member releasably engageable with the handle member. The handle member includes channels for receiving latch pin assemblies, coolant rods and a spacer assembly. The rod support member includes a plurality of fuel rod support chambers providing lateral support for the fuel rods of the fuel assembly. The rod support member also includes a main chamber that is sized to receive a portion of the handle member in a friction fit.

Abstract: An apparatus for inspection of a reactor pressure vessel uses a laser driven type underwater wall climbing robot guided by a laser pointer. The inspection apparatus uses a small and light underwater wall climbing robot for the quick and adequate inspection of weld lines of a reactor pressure vessel. Position control methods are provided for the stable guidance of the robot to desired three dimensional inspection positions on the reactor pressure vessel.

Abstract: A replacement jet pump diffuser apparatus and method are described. In one embodiment, the replacement diffuser apparatus includes a conical section, a first cylindrical section, and a second cylindrical section. The conical section is welded to the first cylindrical section, and the first cylindrical section is welded to the second cylindrical section. A V-flange is formed at one end of the second cylindrical section. The assembly further includes an adapter having a V-flange formed at one end. The adapter is secured to the second cylindrical section by a band clamp which compresses the V-flanges into contact. The adapter further includes an engagement flange having a plurality of bores extending therethrough. L-bolts extend through the respective bores in the engagement flange, and each L-bolt includes an L-section and a threaded section. Respective nuts threadedly engage the threaded sections of the L-bolts. The L-section of each bolt contacts a lower surface of the shroud support plate.

Abstract: A suspension for a ground vehicle which connects a rigid axle to the vehicle chassis and stabilizes the rigid axle in fore, aft, and rotational directions. The suspension comprises four links and a swivel. The four links extend within a predetermined number of degrees of parallel to a longitudinal axis of the vehicle, and connect the rigid axle to the vehicle chassis. Two of the links are normally attached above, and two of the links are normally attached below the rigid axle centerline. Therewith, the swivel comprises an arm having two opposite ends and a centrally positioned pivot shaft. Each end of the arm being interposed between an end each of two of the four links thus the pivot shaft is held steadfast to the surface residing between the locations where the pair of link ends would otherwise attach. Said surface being either of the vehicle framework or of the rigid axle, whichever location is preferred.

Abstract: A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000.degree. F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite.

Abstract: A method for operating the LOMI decontamination process in a regenerative manner. The method incorporates an initial injection of a dilute LOMI solution (vanadous formate, picolinic acid and sodium hydroxide) into a decontamination circuit followed by operation of a small cluster of cation exchange columns during the decontamination process. The cation exchange resin is used to remove metals in the same manner as in prior decontamination processes but operation of the cation exchange resin is continued to allow picolinic acid initially bound to the cation exchange resin to be released and recycled to the LOMI solution. Operation of the cation exchange columns ceases after the picolinic acid has been released but before the metals (e.g. sodium, iron and vanadium) are released back to the LOMI solution. The cluster of cation exchange columns are operated according to a sequence wherein one column is releasing picolinic acid while another is binding picolinic acid.

Abstract: A protective coating to reduce stress corrosion cracking of zirconium alloy sheathing in nuclear reactors. The coating is graphite based and includes ZrO.sub.2 and ethyl cellulose and acts as a sacrificial layer to immobilize fission products by formation of Zr.sub.x I.sub.y C type compounds which do not cause stress corrosion cracking.

Abstract: A tube for constituting all or part of a cladding or guide tube for a fuel assembly is made from an alloy containing, by weight, 0.4% to 0.6% of tin, 0.5% to 0.8% of iron, 0.35% to 0.50% of vanadium, and 0.10% to 0.18% of oxygen, 100 ppm to 180 ppm of carbon and 50 ppm to 120 ppm of silicon. The alloy contains nothing else apart from zirconium and unavoidable impurities and it is completely recrystallized.

Abstract: A remotely operated drilling tool is configured to produce holes in a core shroud support plate inside of a nuclear reactor vessel. The tool includes a support base that is securely mounted directly above the location where the hole will be formed. In a first operation, a drilling tool is secured to the support base and drills a hole through about 90% of the shroud support plate. The drilling tool includes chip capturing structure to prevent chip created by the machining process from contaminating the water in the reactor vessel. After about 90% of the hole is drilled with the drilling tool, an EDM tool is secured to the support base to machine the remainder of the hole using an EDM process. The EDM tool includes structure for machining the remainder of the hole, removing the slug from the hole, and performing a spotface on the underside of the shroud support plate.

Abstract: The recovery device includes a first tank containing a volume of water open in the inner space of the safety containment and a closed second tank isolated from the inner space of the safety containment. The second tank is smaller than the first tank, and is at least partly immersed in the water contained in the first tank. The inner volume of the immersed part of the second tank is placed in communication with the volume of water contained in the first tank by strainers. A discharge pipe is connected at one of its ends to a discharge point of the coolant circuit of the nuclear reactor and includes an end part opposite the discharge point opening into the interior of the second tank.

Abstract: Internal condenser system for discharging vapor from a circuit into a tank or pool to reduce pressure in said circuit.The internal condensation conduit (47) comprises a diaphragm (52) just upstream of a cold liquid feed orifice (55); the jet of vapor passing through orifice (53) of the diaphragm creates a zone of significantly negative pressure around this jet and downstream of the diaphragm causing cold liquid to be sucked up. This causes the vapor to condense in the mixing chamber (56).One possible application relates to primary circuits of a nuclear reactor.

Abstract: A method for sealing cracks adjacent stub tube attachment welds in a reactor pressure vessel of a nuclear reactor is described. The reactor pressure vessel includes at least one stub tube through which a control rod housing extends. The control rod housing is attached to one end of the stub tube with an upper stub tube attachment weld. A sidewall of a control rod drive housing is cut at a location below the upper stub tube attachment weld to separate an upper portion of the control rod housing from a lower portion of the control rod housing. The lower portion of the control rod drive housing is removed from the bottom head opening, and a replacement lower portion is positioned in the bottom head opening proximate to the remaining upper portion. The replacement lower portion then is secured to the reactor pressure vessel without securing the replacement lower portion to the remaining upper portion of the control rod drive housing.

Abstract: An apparatus for controlling dissolved oxygen concentration in primary and secondary cooling water in boiling water and pressurized water atomic reactors is disclosed. The apparatus contains an electrolytic cell having an anode chamber and a cathode chamber separated from one another by a diaphragm of a solid polymer electrolyte membrane. The diaphragm contains: (a) an ion exchange membrane and (b) a pair of multilayered electrodes chemically plated to both surfaces of the ion exchange membrane. The electrolytic cell is operatively connected to a circular route for cooling water in the reactor, and hydrogen gas generated through electrolysis of deionized water in the cathode side of the cell is introduced into the circular route for the cooling water to control the dissolved oxygen concentration of the cooling water.

Abstract: A protective sleeve includes an outer member and an inner member slidable within the outer member. The outer member has a tubular portion with a first end and a second end, and an attachment assembly is located at the first end of the tubular portion. The outer member further includes a plurality of spring plungers secured to an inner wall of the outer member. The attachment assembly includes a collar and a drip skirt secured to the collar. The attachment assembly is threadedly engaged to the first end of the outer member tubular portion. The inner member includes a first end positioned within the outer member and a second end. At least a portion of the inner member extends from the second end of the outer member. The inner member is movable relative to the outer member. A plurality of spring plungers are secured to an outer wall of the inner member. The spring plungers extend between the outer member and the inner member.

Abstract: A method and apparatus for improving the efficiency and performance of a steam driven power plant wherein addition of steam handling equipment to an existing plant results in a surprising increase in plant performance. For Example, a gas turbine electrical generation system with heat recovery boiler may be installed along with a micro-jet high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life.

Abstract: A control rod mechanism for transmitting the rotation of an electric motor via a drive shaft to an elevator apparatus for raising and lowering a hollow piston on an upper end thereof, which is provided a control rod that controls the output of a nuclear reactor. The control rod mechanism is used to insert the control rod into a reactor core or remove it therefrom, and also to rapidly insert the control rod into the reactor core by the injection of hot water to force the hollow piston upward. The control rod mechanism includes a magnetic coupling having an inner magnet, which is divided into a plurality of parts and is disposed at a lower portion of the drive shaft in order to transmit the rotational power of the electric motor to the drive shaft. The control rod mechanism also includes a drive-side outer magnet, which is divided into a plurality of parts and is provided on a rotary shaft of the electric motor in an arrangement on an outer side of the inner magnet.