摘要:
A tube support plate is disclosed for supporting a plurality of tubes with reduced vibration in a nuclear steam generator. The support plate has a plurality of holes disposed therethrough in a regular array. Each hole has an axis, an interior surface and a plurality of lands supported on the interior surface and extending towards the axis. The support plate has a given thickness as taken along the hole axis, and each of the lands has a tapered surface for facilitating tube insertion. The method of forming the tube support plate comprises a first step of forming each of the holes through the support plate with a first cylindrical portion of a first diameter and a second cylindrical portion of a second diameter less than the first diameter. Next, portions of the second cylindrical portion are removed in a second step to form a plurality of lands having exposed ends supporting a tube within the hole.
摘要:
A method of forming and installing anti-vibration bars into a tube bundle of a steam generator is disclosed. The tube bundle comprises rows of tubes, each tube carrying a high temperature coolant. Each of the resultant anti-vibration bars has a tubular configuration and is disposed between adjacent rows of the tube bundle for stabilizing the tubes against vibration caused by fluids recirculating at high velocities through the steam generator. The method of this invention comprises the steps of inserting at least one anti-vibration bar between adjacent rows of the tube bundle and applying a pressurized fluid in the anti-vibration, thus expanding the anti-vibration bar to contact the tubes of the adjacent rows and to make a series of indentations therein. Typically, the pressure of the fluid is increased incrementally up to a maximum level set such that the configuration of the steam genrator tubes is not deformed. The resultant anti-vibration bar is a hollow member and has first and second series of indentations disposed on opposing sides thereof and spaced from each other a uniform distance corresponding to the spacing between adjacent tubes of a row. The indentations are configured similarly to the shape of the tubes to provide intimate contact there between and to support the tubes against vibration.
摘要:
Vessel structural support system for laterally and vertically supporting a vessel, such as a nuclear steam generator having an exterior bottom surface and a side surface thereon. The system includes a bracket connected to the bottom surface. A support column is pivotally connected to the bracket for vertically supporting the steam generator. The system also includes a base pad assembly connected pivotally to the support column for supporting the support column and the steam generator. The base pad assembly, which is capable of being brought to a level position by turning leveling nuts, is anchored to a floor. The system further includes a male key member attached to the side surface of the steam generator and a female stop member attached to an adjacent wall. The male key member and the female stop member coact to laterally support the steam generator. Moreover, the system includes a snubber assembly connected to the side surface of the steam generator and also attached to the adjacent wall for dampening lateral movement of the steam generator. In addition, the system includes a restraining member of "flat" attached to the side surface of the steam generator and a bumper attached to the adjacent wall. The flat and the bumper coact to further laterally support the steam generator.
摘要:
A system for removing sludge from a sludge-bearing fluid flowing in a vertically oriented nuclear steam generator so that the sludge is not present therein in sufficient quantities to corrode components (e.g., heat transfer tubes) located in the steam generator. The system comprises a tube sheet having a plurality of apertures therethrough for receiving the ends of the heat transfer tubes so that the tubes are supported by the tube sheet. The tube sheet has a top surface thereon and also a recess formed in the top surface for separating and for collecting the sludge from the sludge-bearing fluid. The recess has a substantially frusto-conical wall generally converging at the bottom end of the recess for providing a settling basin for the sludge after the sludge is separated from the sludge-bearing fluid. A pipe extends from adjacent the bottom end of the recess to the exterior of the heat exchanger for transporting the sludge from the recess to the exterior of the heat exchanger. A valve, which is connected to the pipe, is capable of opening to remove the sludge via blowdown through the pipe and into a holding tank for suitable disposal.
摘要:
A method and apparatus are disclosed for substantially eliminating flow induced vibrations of the flow tubes of a steam generator in the U-bend region. Antivibration bars are provided between columns of flow tubes in the U-bend region which are contoured on one side to correspond with the exact as-built and as-bent diameter of the tubes as located within the tube bundle. Measurements of the actual flow tube diameters are made and recorded and stored either on tape or in a computer which is then used to control a numerically operated machine which configures or machines cutouts in the antivibration bars to precisely correspond with the respective measured diameters of the flow tubes. Only one side of the antivibration bars need to be machined because of the flexibility of the flow tubes which allow the positioning of the other side of the flow tubes along a flat plane.
摘要:
A thermal sleeve is mechanically attached to the bore of a surge nozzle of a pressurizer for the primary circuit of a pressurized water reactor steam generating system. The thermal sleeve is attached with a series of keys and slots which maintain the thermal sleeve centered in the nozzle while permitting thermal growth and restricting flow between the sleeve and the interior wall of the nozzle.
摘要:
A tube and shell steam generator having an anti-clogging heat exchange tube bundle wherein the tube support plates within the tube bundle are designed with varying degrees of porosity thereby regulating local secondary side fluid conditions (velocity, quality, superheat, void fraction, etc.) in a manner to reduce the potential for clogging of the tube support plate lobes that are more prone to clogging.
摘要:
A thermal sleeve is mechanically attached to the bore of a surge nozzle of a pressurizer for the primary circuit of a pressurized water reactor steam generating system. The thermal sleeve is attached with a series of keys and slots which maintain the thermal sleeve centered in the nozzle while permitting thermal growth and restricting flow between the sleeve and the interior wall of the nozzle.
摘要:
A stayrod configuration for permitting complete sludge lancing of the tubesheet, including a plurality of first stayrods, each having the same diameter as the steam generator tubing and being threaded into the tubesheet at spaced positions which match the tube pattern. This plurality of first stayrods is attached to a connector, which is threaded to provide a receptacle for a second, full-length stayrod within a shortened spacer.
摘要:
A means of offsetting semi-circular tube support plates typically present in heat exchangers with cross flow baffles, such as axial flow economizers, utilizing the motive force of steam generator pressurization. The offset slightly flexes the tubes, thereby providing a preload which minimizes the potential for tube vibration and wear.