The present invention is directed to a method of providing a mid-wall repair, as well as a method of evaluating the mid-wall repair.
In pressurized water (PWR) and boiling water (BWR) nuclear reactors, multiple penetrations are provided in a pressure vessel or piping. The penetrations consist of sleeves and/or nozzles that extend from the exterior of the pressure vessel through openings in a low alloy or carbon steel vessel wall and a nickel-chromium-iron (Ni—Cr—Fe) or stainless steel clad disposed on the interior surface of the pressure vessel. During initial fabrication (i.e., before access to the interior of the pressure vessel is limited, and before the pressure vessel is subjected to radiation and pressurized high temperature water as a result of operation of the nuclear reactor), a J-shaped groove is formed in the vessel interior clad and in some cases the low alloy steel or carbon steel vessel interior wall as well, and a weld material is deposited in the groove to weld the nozzle to the clad and vessel wall, where applicable. Thus, the nozzle is welded from the interior of the pressure vessel to connect the nozzle to the pressure vessel.
As a result of operating and residual stresses in the J-groove weld and the primary water environment during operation, the welds, the sleeves or nozzles, and the Ni—Cr—Fe or stainless steel cladding are subject to stress corrosion cracking. Thus, it becomes necessary to repair the connection between the nozzle and the pressure vessel.
In a known repair technique, the technician does not have access to the highly radioactive interior of the closed pressure vessel. Thus, repair of the connection between the pressure vessel and the nozzle is conducted from the exterior of the pressure vessel.
In the known repair technique, the nozzle is severed at the mid-wall of the pressure vessel and a sacrificial plug installed to create a flush surface at the exterior of the pressure vessel. A welding pad of a material that is not susceptible to stress corrosion cracking, such as Alloy 52, is formed on the exterior of the pressure vessel. A hole is drilled in the welding pad, and a replacement nozzle formed of a material that is not susceptible to stress corrosion cracking, such as Alloy 690, is disposed in the hole. The replacement nozzle is then welded to the welding pad. Because it is not practical to provide postweld heat treatment stress relief of the weld and the adjacent areas, a temper bead welding technique is used to weld the welding pad to the pressure vessel or piping.
The known repair technique suffers from a number of disadvantages, however. These disadvantages include that it is often difficult to precisely align the replacement nozzle with the openings in the pressure vessel wall and the new welding pad on the pressure vessel. Further, a relatively large amount of material is used to provide the welding pad of sufficient size (e.g., 6 inch by 6 inch by 0.5 inch) to permit testing and evaluation of the weld pad to the pressure vessel. Further, because formation of the temper bead must be precisely controlled, the weld pad requires a relatively large amount of time to produce, which may increase down time of the nuclear reactor and the amount of radiation to which the technician is exposed during the repair process. The severity of these problems is compounded by the fact that a typical pressure vessel includes multiple nozzles.
Various illustrative embodiments provide a method of repairing and inspecting a first nozzle penetrating a closed vessel. In accordance with one aspect of an illustrative embodiment, the method may include removing a portion of the first nozzle, and forming a weld between a replacement nozzle and a surface of the mid-wall of the vessel. In accordance with another aspect of an illustrative embodiment, the method may further include evaluating the integrity of the weld at the mid-wall of the vessel.
Various illustrative embodiments of evaluating the integrity of the weld at the mid-wall of the vessel may include performing a liquid penetrant test of the weld; comparing a characteristic of the weld to a characteristic of at least one of a known defective weld and a known defect-free weld; and comparing a characteristic of the weld obtained through ultrasonic inspection
An appreciation of the present invention, and many of the attendant advantages of the invention, can be readily ascertained and/or obtained as the same becomes better understood by reference to the following detailed description when considered in connection with the accompanying drawings, wherein:
Examples of one or more embodiments of the present invention are described with reference to the drawings, wherein like reference numbers throughout the several views identify like or similar elements.
The method of providing and evaluating a mid-wall repair, as shown in the drawings and as described herein, can be provided between a pressure vessel or piping 100 (referred to as pressure vessel in the following discussion) of a PWR or BWR nuclear reactor and at least one nozzle 10. It is to be understood, however, that the method can be applied to various structures, including various nuclear reactor structures as well as structures that are not disposed in a nuclear reactor.
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As discussed above, the pressure vessel 100 can include at least one nozzle 10. In a preferred embodiment, the pressure vessel 100 can include a plurality of nozzles 10. It is to be understood, however, that the pressure vessel 100 can include any number of nozzles 10.
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A weld 109 can be used to connect the pressure vessel 100 and the nozzle 10. In a preferred embodiment, a groove can be formed in the clad 107 or a combination of the clad and vessel wall with weld butter. More preferably, the clad 107 or combination of clad and vessel wall can include a J-shaped groove. The weld 109 can be formed in the groove to weld the pressure vessel 100 to the nozzle 10. It is to be understood, however, that various welds can be used to weld the pressure vessel 100 to the nozzle 10.
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After cleaning the upper nozzle portion 17 and the mid-wall void 113, the surface of the mid-wall void 113 can be evaluated after dye penetrant testing, to confirm that the surface of the mid-wall void 113, such as a portion of the surface adjacent the upper nozzle portion 17, is acceptable for subsequent installation of the replacement nozzle, as described below.
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In an embodiment of the invention, the alignment tool 40 can include a sealing portion that seals against an interior surface of the upper nozzle portion 17. Such an alignment tool 40 can permit reactor fuel off-load or refueling while the mid-wall repair is occurring, by permitting the pressure vessel 100 to be filled with water during the repair process of up to the removal of the alignment tool 40 and reinsertion of the heater or instrument.
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The alignment tool 40 and alignment shaft 42 can be removed from the upper nozzle 17 and the replacement nozzle 30, such that the clamping device maintains the position of the replacement nozzle 30 relative to the pressure vessel 100.
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A welding tool 60 can be used to provide the weld 115 between the replacement nozzle 30 and the mid-wall 105. The welding tool 60 can include a video camera such that a technician can monitor formation of the weld 115, a wire feed through which the technician can deliver a material for the weld 115, an inert gas delivery system to aid in formation of the weld 115, and a water cooling system for cooling the welding tool 60.
A surface of the weld 115 can be prepared for subsequent testing and evaluation. After formation of the weld 115, the weld surface can be prepared for subsequent testing and evaluation. An abrasive grinding operation can be used to remove an excess portion of the weld 115 (e.g., a portion of the weld extending beyond the inner diameter of the replacement nozzle 30).
The weld 115 can be inspected to determine the sufficiency of the weld 115. In a preferred embodiment, the weld 115 can be liquid penetrant inspected.
In a preferred embodiment, the weld 115 can be ultrasonically inspected. More preferably, an ultrasonic map indicating properties of the weld 115 can be provided, the map including characteristics of portions of the weld 115 such as echodynamic signature including response amplitude and time of flight of the ultrasonic signal. By comparing the ultrasonic map of the weld 115 with a plurality of ultrasonic maps of known defect-free and defective welds, a technician can determine whether the weld 115 is substantially free of defects. The ultrasonic maps of known defect-free and defective welds can be determined by producing ultrasonic maps of various weld samples, and then by destructively evaluating the weld samples to determine the absence or existence of defects. It is understood that the term “defect-free” can include welds that meet or exceed the UT examination standards set forth in ASME Code, Section III, and specifically Paragraph NB-5330, which is hereby incorporated by reference. This is in contrast to the more forgiving UT examination requirements of ASME Code, Section XI, which is invoked for this repair by ASME Code Case N-638, which are also both hereby incorporated by reference. It is also to be understood that the above-described process can be performed to provide a weld that exceeds ASME Code, Section XI requirements.
Numerous additional modifications and variations of the present invention are possible in light of the above teachings. It is therefore to be understood that within the scope of the appended claims, the present invention may be practiced otherwise than as specifically described herein.
This patent application is a divisional of U.S. patent application Ser. No. 11/091,767, filed Mar. 29, 2005, the contents of which are incorporated by reference herein in their entirety.
Number | Date | Country | |
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Parent | 11091767 | Mar 2005 | US |
Child | 15058899 | US |