摘要:
An improved apparatus and method for ultrasonic inspection of materials through barriers such as gaps in manufactured parts is disclosed. The improvement herein is directed to enabling such ultrasonic testing to bridge ambient gaps such as intentionally formed gaps in composite structures having a first structure for originally receiving and transmitting sound separated by the gap from another structure to be inspected. Preferably, the gap is flooded with a gas having a predictable and optimum speed of sound relative to the material of the first and second structures. Sound is propagated to the first structure in a wave packet that is transmitted through the couplant fluid. The sound is generated in a wave packet having a spatial width at least twice the dimension of the gap to be bridged. The wave packet has a contained frequency having a wavelength (relative to the speed of sound of the gas flooding the gap) to create a constructively interfering standing wave node within the gap. The sound propagated to the gas-filled gap has a wavelength which is a half-integer with respect to the gap dimension. Sound passes through the first structure, creates a standing wave node in the gas-filled gap, passes into and acoustically interrogates the second structure for flaws and reflects. Reflected ultrasoound from the interrogated second structure again bridges the gap as a constructively interfering standing wave, passing through the primary structure and then through the couplant fluid to a transducer for receipt and analysis of the received ultrasound.
摘要:
An ultrasonic method of inspecting repaired stub tubes in a boiling water reactor. The top and bottom ends of each stub tube are respectively welded to the corresponding control rod drive housing and to the bottom head of the reactor pressure vessel. Under certain conditions, a crack can form in the heat-affected zone of the stub tube adjacent to the upper weld, necessitating repair by installing a mechanical seal. A probe inserted in the control rod drive housing has transducers which transmit pulsed ultrasonic energy toward a machined surface-air gap interface disposed to reflect the pulse trains generally axially through the stub tube. The radial and azimuthal dimensions of a radial crack in the stub tube are determined in dependence on which pulsed trains are reflected back to the probe by the crack via the interface.
摘要:
Provided is a sliding support and a system using the sliding support unit. The sliding support unit may include a fulcrum capture configured to attach to a support flange, a fulcrum support configured to attach to the fulcrum capture, and a baseplate block configured to support the fulcrum support. The system using the sliding support unit may include a pressure vessel, a pedestal bracket, and a plurality of sliding support units.
摘要:
Apparatus for supporting the lower elbow assembly of a jet pump in a reactor pressure vessel (RPV) of a nuclear reactor are described. The clamp apparatus includes a lower clamp element and an upper clamp element. The upper and lower elements are configured to be positioned at the interface between the thermal sleeve and the jet pump riser elbow. The upper and lower elements include extended ridges that are configured to fit in circumferential grooves precisely machined into the sleeve-elbow assembly on opposing sides of the interface.
摘要:
A nozzle includes a barrel being integral with a vessel and includes a first bore. A safe end is joined at one end to the barrel by a first weld and at an opposite end to an inlet pipe at a second weld. A first thermal sleeve is disposed inside the first bore and has one end disposed in an interference fit with a second bore of the safe end. In order to repair the nozzle for reducing leakage at the interference fit between the first and second bores, a method includes removing a portion of the inlet pipe and the weld at the safe end and installing a replacement extension therefor. The extension includes a tubular body having a first fork at one end joined to the safe end by a replacement weld, and having a distal end joined to the inlet pipe at a third weld. A second fork is disposed concentrically inside the body and is integrally joined at one end with an intermediate portion of the body, and includes a distal end extending toward the safe end. A second thermal sleeve is disposed inside the first thermal sleeve and is joined at one end to the second fork and has an opposite end portion disposed in sealing cooperation with the first thermal sleeve for sealing flow therebetween to the interference fit between the first thermal sleeve and the safe end.
摘要:
In a boiling water nuclear reactor having its core, fuel support casting, and control rod guide tubes removed to expose the core plate, an apparatus and method for the submerged welding repair and replacement of the control rod drive housing at the bottom extremity of the reactor vessel is disclosed. The apparatus registers to a hole in the core plate and its corresponding guide pin. A mating fixture on the depending extremity of the shaft of the apparatus precisely fits and mates to the top of the control rod drive housing. The alignment device includes cross electronic levels sealed for submersion which levels remotely transfer through attached wiring the precise angularity between the top of the control rod drive housing on one hand and the corresponding and overlying hole in the core plate on the other hand. For the welding repair process herein, a welding cylinder apparatus fits over the depending end of the shaft of the alignment device. This welding cylinder protrudes downwardly and around the control rod drive housing mating to the stub tube through which the control rod drive housing is inserted. A rotating raceway is provided interior of the cylinder for permitting TIG welding unit to traverse around a path for weldment defined at the side of the control rod drive housing and at the top of the stub tube.
摘要:
A reactor pressure vessel assembly may include a housing surrounding a reactor core, steam separators, and a chimney. Inner surfaces of the chimney and reactor core define a conduit for transporting a two phase flow stream from the reactor core through the chimney to the steam separators. The housing defines an opening. An inner surface of the housing and outer surfaces of the chimney and reactor core define an annulus in fluid communication with the opening and conduit. A feedwater sparger in the housing is connected to the at least one opening and configured to deliver a sub-cooled feedwater into the annulus. A flow barrier structure between the chimney and the steam separators may force mixing between the sub-cooled feedwater and a downcomer fluid from the steam separators. An outer steam separator may be vertically over a portion of the flow barrier structure in a plan view.
摘要:
Apparatus for supporting the lower riser assembly of a jet pump in a reactor pressure vessel (RPV) of a nuclear reactor. In one embodiment of the apparatus, the clamp assembly provides structural rigidity to the lower rise assembly. The clamp assembly includes a lower thermal sleeve clamp and a riser clamp. The lower thermal sleeve clamp is positioned adjacent an interface between the elbow and the thermal sleeve of the jet pump riser pipe assembly. The riser clamp is secured to the riser pipe of the jet pump riser pipe assembly at a location adjacent an interface between the riser pipe and the elbow. The lower thermal sleeve clamp and the riser clamp also are coupled to each other so that as the respective clamps are secured to the lower riser assembly.
摘要:
Thermal sleeve assemblies for connecting a core spray line to a reactor safe end without welding. In one embodiment the thermal sleeve assembly includes a t-box junction, a thermal sleeve and a finger assembly. The t-box junction is attached core spray lines and the thermal sleeve. The finger assembly is coupled to the thermal sleeve and includes several fingers. The finger assembly includes a ring which is coupled to the thermal sleeve so that an opening in the ring is aligned with a bore extending through the thermal sleeve. The fingers are substantially L shaped and are attached to the ring so that when the ring is welded to the thermal sleeve second end the fingers extend from the thermal sleeve.
摘要:
A core differential pressure and liquid control line apparatus for a nuclear reactor is described. The apparatus includes a first portion configured to be positioned within and extend through an opening in the pressure vessel wall. At least the first tube portion has a diameter less than the diameter of the opening in the pressure vessel wall. An annulus is formed between the exterior surface of the first tube portion and the pressure vessel wall so that a neutron absorbent can be injected into the pressure vessel at the location of the annulus. The apparatus further includes a second L-shaped tube portion configured to be coupled to the first tube portion, and a third tube portion configured to be coupled to the second tube portion. The open end of the third tube portion extends to an elevation above the core plate.