Transverse holding device for a steam generator of a pressurized water nuclear reactor, and for its adjustment
AssigneeFramatome
InventorSerge Brouttelande
Life of this patent
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Abstract
An adjusting and positioning assembly for a bearing element (55), constituted by a nut (52) carried by a base plate, (40) fixed on a wall of a concrete structure in which the component is arranged, and a screw-jack (54) engaged with and blockable with respect to the nut (52). The transverse holding of the lower part of a steam generator pressurized-water nuclear reactor is provided by an assembly of supports each constituted by an adjustable transverse holding device (24) according to the invention. The position of the bearing element is adjusted in such a manner as to maintain play allowing movement of the steam generator as a result of thermal effects or in the event of an earthquake.
Claims9
Transverse holding device for a component of a steam generator of a pressurized-water nuclear reactor, arranged in a stationary concrete structure having vertical walls surrounding the component, comprising at least one base plate fixed on one wall of the concrete structure and a bearing element carried by the base plate and adapted to be arranged in contact with or in the vicinity of a bearing surface of the component, wherein said transverse holding device comprises an assembly for adjusting and positioning the bearing element constituted by:
- (a ) a nut having an axis carried by the base plate traversed by a tapped orifice directed along the axis of the nut;
- (b) a screw-jack engaged with the nut and arranged in the axial direction of the nut;
- and (c) means for blocking the screw-jack with respect to the nut, in a specified position of the screw-jack in the axial direction,
- the bearing element being constituted by a pad carried by one end of the screw-jack directed towards the bearing surface of the component.
Method for adjusting an assembly comprising two pairs of lateral supports for transversely holding a steam generator of a pressurized-water nuclear reactor during hot testing of the nuclear reactor, the steam generator being at its service temperature, said method comprising the steps of:
- (a) bringing bearing pads of each one of the supports into contact with a corresponding bearing surface of the steam generator by unscrewing a corresponding screw;
- (b) blocking screw-jacks of one part of lateral supports arranged on one side of a vertical plane passing through the axis of a hot leg in position;
- and
- (c) for the other pair of lateral supports arranged on the other side of a vertical plane passing through the axis of the hot leg and for the front supports, moving the screw in the axial direction, by screwing, by a specified distance corresponding to a play between the bearing pad of the support and the corresponding part of the bearing surface of the steam generator, in order to allow guided movement of the steam generator between the supports as a result of thermal effects in service or through accidental causes.
Dependencies are inferred from the claim text.