US20150298266A1 - Two-Piece Replacement Nozzle - Google Patents
Two-Piece Replacement Nozzle Download PDFInfo
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- US20150298266A1 US20150298266A1 US14/257,134 US201414257134A US2015298266A1 US 20150298266 A1 US20150298266 A1 US 20150298266A1 US 201414257134 A US201414257134 A US 201414257134A US 2015298266 A1 US2015298266 A1 US 2015298266A1
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- Prior art keywords
- nozzle
- replacement nozzle
- replacement
- nozzle portion
- pressure vessel
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Classifications
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23P—METAL-WORKING NOT OTHERWISE PROVIDED FOR; COMBINED OPERATIONS; UNIVERSAL MACHINE TOOLS
- B23P6/00—Restoring or reconditioning objects
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
- B23K31/00—Processes relevant to this subclass, specially adapted for particular articles or purposes, but not covered by only one of the preceding main groups
- B23K31/02—Processes relevant to this subclass, specially adapted for particular articles or purposes, but not covered by only one of the preceding main groups relating to soldering or welding
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/207—Assembling, maintenance or repair of reactor components
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
- B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
- B23K2101/00—Articles made by soldering, welding or cutting
- B23K2101/04—Tubular or hollow articles
- B23K2101/12—Vessels
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/032—Joints between tubes and vessel walls, e.g. taking into account thermal stresses
- G21C13/036—Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates to a replacement nozzle for a pressurized vessel, and, more particularly, the present invention relates to a two-piece replacement nozzle and welding techniques associated therewith.
- a typical PWR plant includes (in part) a reactor vessel, steam generator, pressurizer, and a reactor coolant piping system, all of which operate under high pressure. Nozzles are attached to the vessels and/or piping for a number of purposes, such as for connecting piping and instrumentation, providing vents, and securing control element drive mechanisms and heater elements.
- a typical pressure vessel in the form of a pressurizer 10 is shown in FIG. 1 .
- the pressurizer 10 includes nozzles 12 for vents, nozzles 14 for sampling liquid level or pressure sensing, a nozzle 16 for temperature measuring, and a number of bottom nozzles 18 , 20 for heating elements. All of these nozzles are welded to the pressure vessel at the time of original manufacture.
- cladding 22 is welded to the interior of the pressurizer 10 , which is made of carbon steel.
- the nozzle 16 shown in cross section in FIG. 2 is exemplary of the mentioned welded nozzles, which all pass through a hole or bore 24 in the pressure vessel 10 and which are structurally welded at the interior end 26 to the vessel 10 with a J-groove weld 28 along the interior opening to the bore 24 .
- the diameter of nozzle 16 is slightly less than the diameter of bore 24 , so that there is a small annular space 30 between the nozzle exterior and the wall of bore 24 .
- the nozzles are fit tight to the bore, and in a control rod drive mechanism, they are installed with a shrink fit process.
- the nozzles may also be roll-expanded in the bore 24 .
- the J-groove weld 28 also functions as a seal weld to seal the annular space 30 .
- a reactor vessel similarly has nozzles represented by nozzle 16 in FIG. 2 welded thereto. Corresponding reactor vessel nozzles are located in the lower spherical head and allow instrumentation to be inserted into the reactor core.
- the piping of the reactor coolant system (not shown) also includes similar nozzles welded thereto. Further details of pressurizer vessels, reactor vessels, and coolant system piping, in particular, and nuclear power facilities, in general, are known to those of skill in the art.
- Nozzle failures and leakage in nuclear power facilities is mainly due to SCC (stress corrosion cracking), which occurs on components having a susceptible material, high tensile stresses, high temperature, and which are in a corrosive environment, conditions which primarily exist on nozzle penetration in the pressurizer vessel, reactor coolant piping, and the reactor pressure vessel.
- SCC stress corrosion cracking
- Such cracking occurs at the grain boundaries on the inside diameter of the nozzle material at or near the heat-affected zone of the weld and propagates radially outward through the thickness of the nozzle, which can eventually lead to small leakage of the reactor coolant supply. Failures have also occurred on stainless steel pressurizer nozzles.
- nozzles of these types have failed over time and have had to be replaced or repaired, as inspections on the nozzles and welds have revealed small indications or, in some cases, very minor leakage of primary coolant.
- One known repair method entails machining off the portion of the original nozzle protruding from the pressure vessel, attaching a weld pad to the vessel surrounding the nozzle location, and welding a one-piece replacement nozzle to the weld pad, the replacement nozzle having the same or similar dimensions as the original nozzle.
- the weld pad and pad-to-nozzle weld required by applicable code with this method are relatively large due to the size of the replacement nozzle.
- the problems inherent with the large structural weld joint geometries include a long schedule duration for welding during implementation, a potential for high personnel radiation exposure during implementation, and an increased risk of potential welding issues during implementation.
- This invention provides an improved replacement nozzle.
- the nozzle is provided in two pieces.
- a first nozzle piece is a thin-walled cylinder that is inserted into the counterbored opening of the pressure vessel after the protruding portion of the original nozzle has been removed.
- a weld pad is attached to the pressure vessel, to which the first replacement nozzle piece is welded.
- a second nozzle piece is positioned within the first nozzle piece and welded thereto.
- the existing instrumentation piping is connected to the free end of the second nozzle piece in known manner.
- This two-piece replacement nozzle can be implemented in approximately half the time required for the one-piece design, reducing outage critical path schedule and personnel radiation dose.
- a method of replacing a nozzle in a pressure vessel includes removing the portion of the nozzle extending outside the pressure vessel, preferably with a counterbore extending into the pressure vessel wall.
- a relatively small weld pad is provided on the outside of the pressure vessel, the weld pad having a machined hole aligned with and similarly dimensioned to the counterbore.
- a thin-walled first replacement nozzle piece is inserted into the weld pad hole and counterbore such that it is adjacent to the end of the remaining section of the original nozzle. A small gap may be left between the first replacement nozzle piece and the remaining nozzle section.
- the first replacement nozzle portion is then welded to the weld pad.
- the sizes of the weld pad and the pad-to-nozzle weld are significantly smaller than would normally be required due to the thin walls of the first replacement nozzle piece.
- a second thin-walled replacement nozzle piece is inserted within the first nozzle piece such that its end is aligned with the end of the first nozzle piece and adjacent the end of the remaining portion of the original nozzle.
- the replacement nozzle pieces are then welded together, and the plant instrumentation is reinstalled through the replacement nozzle.
- the combined pieces of the replacement nozzle have substantially the same outside diameter, inside diameter, and wall thickness as the original nozzle.
- FIG. 1 is a cross sectional view of a known pressure vessel.
- a pressurizer is shown for illustrative purposes, as the invention is applicable to small diameter nozzles located in other primary system components and piping as well.
- FIG. 2 is a cross sectional view of a nozzle taken along section 2 - 2 of FIG. 1 .
- FIG. 3 shows a cross sectional view of a two-piece replacement nozzle of the present invention installed in a pressure vessel.
- FIG. 4 shows a cross sectional view of the two-piece replacement nozzle of FIG. 3 and illustrates its resemblance to the original nozzle.
- This invention is drawn to a replacement nozzle for a nuclear pressure vessel, such as a bottom mounted instrument nozzle of a reactor.
- a nuclear pressure vessel such as a bottom mounted instrument nozzle of a reactor.
- Such nozzles allow instrumentation to pass through the pressure vessel to take measurements within the reactor.
- These nozzles are affixed to the pressure vessel by J-groove welds that attach the nozzles to the inner surface of the pressure vessel.
- FIG. 3 shows a cross sectional view of an original nozzle 18 and a replacement nozzle 40 of the present invention installed in a pressure vessel.
- a nozzle for bottom mounted instrumentation 18 is shown, but it will be recognized that the present invention can be used with any type of pressure vessel penetration.
- the replacement nozzle 40 is a two-piece nozzle, including a first, outer nozzle section 42 and a second, inner nozzle section 44 .
- the first nozzle piece 42 is a thin-walled cylinder that is inserted into the counterbored opening 24 of the pressure vessel 10 after the protruding portion of original nozzle 16 has been removed.
- a weld pad 46 is attached to the pressure vessel, to which the first replacement nozzle piece 42 is welded via weld 48 .
- a second nozzle piece 44 is positioned within the first nozzle piece 42 and welded thereto via weld 50 .
- the existing instrumentation piping 32 is connected to the free end of the second nozzle piece 44 in known manner, such as via weld 34 .
- This two-piece replacement nozzle 40 can be implemented in approximately half the time required for the one-piece design, reducing outage critical path schedule and personnel radiation dose.
- FIG. 4 shows a cross sectional view of the original 18 and replacement 40 nozzles.
- the original nozzle 18 has an outside diameter 181 and an inside diameter 182 that define a wall thickness 183 .
- the outside diameter 181 corresponds very closely to the diameter of the opening 24 through the pressure vessel 10 .
- the inside diameter 182 allows for the introduction of instrumentation into the pressure vessel.
- the outer replacement nozzle portion 42 has an outside diameter 421 and an inside diameter 422 that define a wall thickness 423 .
- the outside diameter 421 is substantially the same as or slightly larger than the outside diameter 181 of the original nozzle 18 .
- the inner replacement nozzle portion 44 has a stepped profile with a first section having an axial length 446 that is less than the overall axial length 447 of the inner nozzle portion 44 .
- the first section of the inner nozzle portion 44 has an outside diameter 441 and an inside diameter 443 that define a first wall thickness 444 .
- the outside diameter 441 of the inner nozzle section 44 corresponds closely to the inside diameter 422 of the outer nozzle section 42 so that the inner section 44 can be inserted within the outer section 42 .
- the axial length 446 of the first inner nozzle section corresponds with the axial length of the outer nozzle section 42 so that when the inner nozzle section 44 is positioned within the outer nozzle section 42 , the two sections can be joined together, such as by a butt weld 50 .
- first outside diameter axial length 446 is a bit longer than the axial length 424 of the outer nozzle section 42 .
- the second section of the inner replacement nozzle portion 42 has the same inside diameter 443 as the first section, but has a second outside diameter 442 that is larger than the first outside diameter 441 .
- the second outside diameter 442 is substantially the same as the outside diameter 421 of the outer nozzle section 42 .
- the replacement nozzle sections 42 , 44 form a unit having an inside diameter 443 and outside diameter 421 , 442 that define a wall thickness 445 .
- These dimensions of the replacement nozzle 40 (that is, the combined unit of the outer replacement nozzle section 42 and the inner replacement nozzle section 44 ) are substantially the same as those of the original nozzle 18 .
- the wall thickness 445 of the replacement nozzle 40 is substantially the same as the wall thickness 183 of the original nozzle 18 .
- the wall thickness 423 of the outer replacement nozzle section 42 and the first wall thickness 444 of the inner replacement nozzle section 44 are substantially the same.
- the installation of the replacement nozzle 40 begins by removing the portion of the original nozzle 18 extending outside of the pressure vessel 10 . That is, the portion of the original nozzle 18 extending beyond the exterior surface of the pressure vessel 10 is removed in known manner, such as using a split lathe on the exterior of the interior of the original nozzle 18 .
- a counterbore is formed by removing a portion of the original nozzle 18 inside the outer surface of the pressure vessel 10 , creating an opening into which the replacement nozzle 40 can be positioned. (See FIG. 3 .)
- a weld pad 46 is welded to the exterior surface of the pressure vessel 10 .
- the weld pad 46 has a torus-like shape, and is centered about the pressure vessel bore 24 .
- a hole is created in the weld pad, the weld pad hole having substantially the same diameter as the bore 24 .
- This weld pad hole can be formed during the welding of the pad 46 itself, or can be created in a second machining step after the weld pad 46 has been created.
- the outer replacement nozzle portion 42 is then positioned within the weld pad hole and counterbore such that its interior end is adjacent to the end of the original nozzle 18 created during the removal step discussed above. Once in place, the outer nozzle portion 42 is welded to the weld pad 46 such as via a J-groove weld 48 .
- the inner nozzle portion 44 is inserted into the outer nozzle portion 42 and positioned such that its interior end is substantially coplanar with the inner nozzle interior end and is adjacent to the end of the original nozzle 18 .
- the inner nozzle portion 44 is then connected to the outer nozzle portion 42 such as via a butt weld 50 .
- the plant instrumentation piping 32 can then be connected to the exterior end of the replacement nozzle 40 .
- both the weld pad 46 and the J-groove weld 48 are much smaller than would be required for a one-piece replacement nozzle.
- installation of the two-piece replacement nozzle 40 of the present invention is a one-week process. This results in a significant reduction of the radiation dose incurred by personnel installing the replacement nozzle and of the outage critical path schedule by approximately 5-7 days, which may reduce the overall duration that the reactor is off-line.
- the placement of the replacement nozzle 40 on the exterior surface of the pressure vessel 10 provides benefits over placement on the interior surface of the pressure vessel 10 .
- the radiation dose incurred by personnel performing the replacement is reduced by not having to operate within the pressure vessel 10 .
- the machining steps discussed above take place outside the pressure vessel, significantly reducing or eliminating the possibility that any foreign objects are introduced to the reactor system.
- any repair performed on the interior of the vessel would have to be performed underwater. (A cofferdam is used to prevent water from escaping the vessel during the repair disclosed herein.)
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Mechanical Engineering (AREA)
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- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Butt Welding And Welding Of Specific Article (AREA)
Abstract
Description
- 1. Field of the Invention
- The present invention relates to a replacement nozzle for a pressurized vessel, and, more particularly, the present invention relates to a two-piece replacement nozzle and welding techniques associated therewith.
- 2. Description of the Related Art
- While the present invention may be used in a variety of industries, the environment of a pressurized water reactor (PWR) nuclear power plant will be discussed herein for illustrative purposes. A typical PWR plant includes (in part) a reactor vessel, steam generator, pressurizer, and a reactor coolant piping system, all of which operate under high pressure. Nozzles are attached to the vessels and/or piping for a number of purposes, such as for connecting piping and instrumentation, providing vents, and securing control element drive mechanisms and heater elements. A typical pressure vessel in the form of a
pressurizer 10 is shown inFIG. 1 . Thepressurizer 10 includesnozzles 12 for vents,nozzles 14 for sampling liquid level or pressure sensing, anozzle 16 for temperature measuring, and a number ofbottom nozzles - As shown in
FIG. 2 ,cladding 22, typically made of stainless steel, is welded to the interior of thepressurizer 10, which is made of carbon steel. Thenozzle 16 shown in cross section inFIG. 2 is exemplary of the mentioned welded nozzles, which all pass through a hole or bore 24 in thepressure vessel 10 and which are structurally welded at theinterior end 26 to thevessel 10 with a J-groove weld 28 along the interior opening to thebore 24. The diameter ofnozzle 16 is slightly less than the diameter ofbore 24, so that there is a smallannular space 30 between the nozzle exterior and the wall ofbore 24. In some applications the nozzles are fit tight to the bore, and in a control rod drive mechanism, they are installed with a shrink fit process. The nozzles may also be roll-expanded in thebore 24. The J-groove weld 28 also functions as a seal weld to seal theannular space 30. A reactor vessel similarly has nozzles represented bynozzle 16 inFIG. 2 welded thereto. Corresponding reactor vessel nozzles are located in the lower spherical head and allow instrumentation to be inserted into the reactor core. The piping of the reactor coolant system (not shown) also includes similar nozzles welded thereto. Further details of pressurizer vessels, reactor vessels, and coolant system piping, in particular, and nuclear power facilities, in general, are known to those of skill in the art. - Nozzle failures and leakage in nuclear power facilities is mainly due to SCC (stress corrosion cracking), which occurs on components having a susceptible material, high tensile stresses, high temperature, and which are in a corrosive environment, conditions which primarily exist on nozzle penetration in the pressurizer vessel, reactor coolant piping, and the reactor pressure vessel. Such failures are manifested by cracking. Such cracking occurs at the grain boundaries on the inside diameter of the nozzle material at or near the heat-affected zone of the weld and propagates radially outward through the thickness of the nozzle, which can eventually lead to small leakage of the reactor coolant supply. Failures have also occurred on stainless steel pressurizer nozzles.
- As indicated, nozzles of these types have failed over time and have had to be replaced or repaired, as inspections on the nozzles and welds have revealed small indications or, in some cases, very minor leakage of primary coolant. One known repair method entails machining off the portion of the original nozzle protruding from the pressure vessel, attaching a weld pad to the vessel surrounding the nozzle location, and welding a one-piece replacement nozzle to the weld pad, the replacement nozzle having the same or similar dimensions as the original nozzle. The weld pad and pad-to-nozzle weld required by applicable code with this method are relatively large due to the size of the replacement nozzle. The problems inherent with the large structural weld joint geometries include a long schedule duration for welding during implementation, a potential for high personnel radiation exposure during implementation, and an increased risk of potential welding issues during implementation.
- This invention provides an improved replacement nozzle. The nozzle is provided in two pieces. A first nozzle piece is a thin-walled cylinder that is inserted into the counterbored opening of the pressure vessel after the protruding portion of the original nozzle has been removed. A weld pad is attached to the pressure vessel, to which the first replacement nozzle piece is welded. However, due to the reduced dimensions of the thin-walled first nozzle portion, a much smaller weld pad and pad-to-nozzle weld can be used. A second nozzle piece is positioned within the first nozzle piece and welded thereto. The existing instrumentation piping is connected to the free end of the second nozzle piece in known manner. This two-piece replacement nozzle can be implemented in approximately half the time required for the one-piece design, reducing outage critical path schedule and personnel radiation dose.
- A method of replacing a nozzle in a pressure vessel includes removing the portion of the nozzle extending outside the pressure vessel, preferably with a counterbore extending into the pressure vessel wall. A relatively small weld pad is provided on the outside of the pressure vessel, the weld pad having a machined hole aligned with and similarly dimensioned to the counterbore. A thin-walled first replacement nozzle piece is inserted into the weld pad hole and counterbore such that it is adjacent to the end of the remaining section of the original nozzle. A small gap may be left between the first replacement nozzle piece and the remaining nozzle section. The first replacement nozzle portion is then welded to the weld pad. The sizes of the weld pad and the pad-to-nozzle weld are significantly smaller than would normally be required due to the thin walls of the first replacement nozzle piece.
- A second thin-walled replacement nozzle piece is inserted within the first nozzle piece such that its end is aligned with the end of the first nozzle piece and adjacent the end of the remaining portion of the original nozzle. The replacement nozzle pieces are then welded together, and the plant instrumentation is reinstalled through the replacement nozzle. The combined pieces of the replacement nozzle have substantially the same outside diameter, inside diameter, and wall thickness as the original nozzle.
- The present invention is described with reference to the accompanying drawings, which illustrate exemplary embodiments and in which like reference characters reference like elements. It is intended that the embodiments and figures disclosed herein are to be considered illustrative rather than restrictive.
-
FIG. 1 is a cross sectional view of a known pressure vessel. A pressurizer is shown for illustrative purposes, as the invention is applicable to small diameter nozzles located in other primary system components and piping as well. -
FIG. 2 is a cross sectional view of a nozzle taken along section 2-2 ofFIG. 1 . -
FIG. 3 shows a cross sectional view of a two-piece replacement nozzle of the present invention installed in a pressure vessel. -
FIG. 4 shows a cross sectional view of the two-piece replacement nozzle ofFIG. 3 and illustrates its resemblance to the original nozzle. - This invention is drawn to a replacement nozzle for a nuclear pressure vessel, such as a bottom mounted instrument nozzle of a reactor. Such nozzles allow instrumentation to pass through the pressure vessel to take measurements within the reactor. These nozzles are affixed to the pressure vessel by J-groove welds that attach the nozzles to the inner surface of the pressure vessel.
-
FIG. 3 shows a cross sectional view of anoriginal nozzle 18 and areplacement nozzle 40 of the present invention installed in a pressure vessel. A nozzle for bottom mountedinstrumentation 18 is shown, but it will be recognized that the present invention can be used with any type of pressure vessel penetration. Thereplacement nozzle 40 is a two-piece nozzle, including a first,outer nozzle section 42 and a second,inner nozzle section 44. Thefirst nozzle piece 42 is a thin-walled cylinder that is inserted into thecounterbored opening 24 of thepressure vessel 10 after the protruding portion oforiginal nozzle 16 has been removed. Aweld pad 46 is attached to the pressure vessel, to which the firstreplacement nozzle piece 42 is welded viaweld 48. However, due to the reduced dimensions of the thin-walledfirst nozzle portion 42, a muchsmaller weld pad 46 and pad-to-nozzle weld 48 can be used. Asecond nozzle piece 44 is positioned within thefirst nozzle piece 42 and welded thereto viaweld 50. The existing instrumentation piping 32 is connected to the free end of thesecond nozzle piece 44 in known manner, such as viaweld 34. This two-piece replacement nozzle 40 can be implemented in approximately half the time required for the one-piece design, reducing outage critical path schedule and personnel radiation dose. -
FIG. 4 shows a cross sectional view of the original 18 andreplacement 40 nozzles. Theoriginal nozzle 18 has anoutside diameter 181 and aninside diameter 182 that define awall thickness 183. As discussed above, theoutside diameter 181 corresponds very closely to the diameter of theopening 24 through thepressure vessel 10. Theinside diameter 182 allows for the introduction of instrumentation into the pressure vessel. - The outer
replacement nozzle portion 42 has an outside diameter 421 and an inside diameter 422 that define awall thickness 423. The outside diameter 421 is substantially the same as or slightly larger than theoutside diameter 181 of theoriginal nozzle 18. - The inner
replacement nozzle portion 44 has a stepped profile with a first section having anaxial length 446 that is less than the overallaxial length 447 of theinner nozzle portion 44. The first section of theinner nozzle portion 44 has an outside diameter 441 and aninside diameter 443 that define afirst wall thickness 444. The outside diameter 441 of theinner nozzle section 44 corresponds closely to the inside diameter 422 of theouter nozzle section 42 so that theinner section 44 can be inserted within theouter section 42. Theaxial length 446 of the first inner nozzle section corresponds with the axial length of theouter nozzle section 42 so that when theinner nozzle section 44 is positioned within theouter nozzle section 42, the two sections can be joined together, such as by abutt weld 50. Thus, first outside diameteraxial length 446 is a bit longer than theaxial length 424 of theouter nozzle section 42. - The second section of the inner
replacement nozzle portion 42 has the sameinside diameter 443 as the first section, but has a second outside diameter 442 that is larger than the first outside diameter 441. The second outside diameter 442 is substantially the same as the outside diameter 421 of theouter nozzle section 42. Thus, when joined together, thereplacement nozzle sections inside diameter 443 and outside diameter 421, 442 that define awall thickness 445. These dimensions of the replacement nozzle 40 (that is, the combined unit of the outerreplacement nozzle section 42 and the inner replacement nozzle section 44) are substantially the same as those of theoriginal nozzle 18. Thewall thickness 445 of thereplacement nozzle 40 is substantially the same as thewall thickness 183 of theoriginal nozzle 18. Preferably, thewall thickness 423 of the outerreplacement nozzle section 42 and thefirst wall thickness 444 of the innerreplacement nozzle section 44 are substantially the same. - The installation of the
replacement nozzle 40 begins by removing the portion of theoriginal nozzle 18 extending outside of thepressure vessel 10. That is, the portion of theoriginal nozzle 18 extending beyond the exterior surface of thepressure vessel 10 is removed in known manner, such as using a split lathe on the exterior of the interior of theoriginal nozzle 18. Preferably, a counterbore is formed by removing a portion of theoriginal nozzle 18 inside the outer surface of thepressure vessel 10, creating an opening into which thereplacement nozzle 40 can be positioned. (SeeFIG. 3 .) - After the exterior portion of the
original nozzle 18 has been removed, aweld pad 46 is welded to the exterior surface of thepressure vessel 10. Theweld pad 46 has a torus-like shape, and is centered about the pressure vessel bore 24. A hole is created in the weld pad, the weld pad hole having substantially the same diameter as thebore 24. This weld pad hole can be formed during the welding of thepad 46 itself, or can be created in a second machining step after theweld pad 46 has been created. The outerreplacement nozzle portion 42 is then positioned within the weld pad hole and counterbore such that its interior end is adjacent to the end of theoriginal nozzle 18 created during the removal step discussed above. Once in place, theouter nozzle portion 42 is welded to theweld pad 46 such as via a J-groove weld 48. - Next, the
inner nozzle portion 44 is inserted into theouter nozzle portion 42 and positioned such that its interior end is substantially coplanar with the inner nozzle interior end and is adjacent to the end of theoriginal nozzle 18. Theinner nozzle portion 44 is then connected to theouter nozzle portion 42 such as via abutt weld 50. With thereplacement nozzle 40 in place, the plant instrumentation piping 32 can then be connected to the exterior end of thereplacement nozzle 40. - It should be noted that because the
wall thickness 423 of theouter nozzle portion 42 is substantially thinner than thewall thickness 183 of theoriginal nozzle 18, both theweld pad 46 and the J-groove weld 48 are much smaller than would be required for a one-piece replacement nozzle. Where the process of installing a one-piece replacement nozzle would be a two-week project, installation of the two-piece replacement nozzle 40 of the present invention is a one-week process. This results in a significant reduction of the radiation dose incurred by personnel installing the replacement nozzle and of the outage critical path schedule by approximately 5-7 days, which may reduce the overall duration that the reactor is off-line. - The placement of the
replacement nozzle 40 on the exterior surface of thepressure vessel 10 provides benefits over placement on the interior surface of thepressure vessel 10. The radiation dose incurred by personnel performing the replacement is reduced by not having to operate within thepressure vessel 10. Additionally, the machining steps discussed above take place outside the pressure vessel, significantly reducing or eliminating the possibility that any foreign objects are introduced to the reactor system. Furthermore, as the reactor is flooded during the refueling outage, any repair performed on the interior of the vessel would have to be performed underwater. (A cofferdam is used to prevent water from escaping the vessel during the repair disclosed herein.) - While the preferred embodiments of the present invention have been described above, it should be understood that they have been presented by way of example only, and not of limitation. It will be apparent to persons skilled in the relevant art that various changes in form and detail can be made therein without departing from the spirit and scope of the invention. For example, while the environment of a PWR nuclear power plant has been discussed herein for illustrative purposes, the present invention can also be used in a variety of other environments such as a boiling water reactor nuclear power plants or other industrial plants. Thus the present invention should not be limited by the above-described exemplary embodiments, but should be defined only in accordance with the following claims and their equivalents. Furthermore, while certain advantages of the invention have been described herein, it is to be understood that not necessarily all such advantages may be achieved in accordance with any particular embodiment of the invention. Thus, for example, those skilled in the art will recognize that the invention may be embodied or carried out in a manner that achieves or optimizes one advantage or group of advantages as taught herein without necessarily achieving other advantages as may be taught or suggested herein.
Claims (10)
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CN106448755A (en) * | 2016-11-24 | 2017-02-22 | 中广核工程有限公司 | Nuclear reactor pressure vessel cap and mounting method thereof |
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