GB2100496A - Standard integrated head package - Google Patents
Standard integrated head package Download PDFInfo
- Publication number
- GB2100496A GB2100496A GB8216189A GB8216189A GB2100496A GB 2100496 A GB2100496 A GB 2100496A GB 8216189 A GB8216189 A GB 8216189A GB 8216189 A GB8216189 A GB 8216189A GB 2100496 A GB2100496 A GB 2100496A
- Authority
- GB
- United Kingdom
- Prior art keywords
- reactor
- head package
- control rod
- head
- cooling
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
- 238000001816 cooling Methods 0.000 claims abstract description 33
- 230000007246 mechanism Effects 0.000 claims abstract description 24
- 230000000712 assembly Effects 0.000 claims abstract description 12
- 238000000429 assembly Methods 0.000 claims abstract description 12
- 238000009434 installation Methods 0.000 claims description 3
- 230000003247 decreasing effect Effects 0.000 claims description 2
- 238000012423 maintenance Methods 0.000 claims description 2
- 230000035515 penetration Effects 0.000 claims description 2
- 238000013461 design Methods 0.000 description 8
- 238000000034 method Methods 0.000 description 4
- 230000004075 alteration Effects 0.000 description 2
- 238000007596 consolidation process Methods 0.000 description 2
- 238000009413 insulation Methods 0.000 description 2
- 238000002360 preparation method Methods 0.000 description 2
- 238000012546 transfer Methods 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000000452 restraining effect Effects 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 239000002918 waste heat Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- 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
- G21C19/02—Details of handling arrangements
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/06—Sealing-plugs
- G21C13/073—Closures for reactor-vessels, e.g. rotatable
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
An integrated head package for a standard-type nuclear reactor consolidating many components and sub- assemblies of the upper reactor structure into a single unit which may be removed from the reactor vessel in a single lift. Included among the consolidated elements are a pressure vessel head (18), a cooling shroud (20), control rod drive mechanisms (22), a missile shield (14), a lifting rig, a hoist assembly (38), and a cable tray assembly (28, 30). <IMAGE>
Description
SPECIFICATION
Standard integrated head package
This invention pertains to the preparation of a nuclear reactorfor refueling, and in particular to a novel combination of features of a standard-type reactor that can help to reduce refueling times.
The term "standard-type reactor" is used herein as a reference to the type of nuclear reactor in commercial operation in the field today.
The time required for removing the upper structure from a standard-type nuclear reactor has made frequent refueling impractical. Because of the safety and structural functions performed by reactor internals, various components are assembled to each other in such a way as to insure their integrity during reactor operation. Therefore, in order to disassemble the reactor internals, each component or subassembly must be individually disconnected from another component or subassembly in sequential fashion.
This time-consuming preparation begins with disconnection of cabling which connects control rod drive mechanisms to reactor controls. After vessel head insulation has been removed, instrumentation thermocouple leads are individually disconnected.
Vessel stud nuts are detensioned with a special tool, then the studs and nuts are removed from the vessel flange. Guide studs are installed in several stud holes to provide proper head alignmenton reinstallation and the remainder of the stud holes are plugged. The reactor vessel head is unseated by a permanently-attached crane and slowly lifted while the reactor cavity is flooded with borated water.
Once the head has been removed, the control rod drive shafts are individually unlatched from rod cluster control assemblies, which remain in the core.
Finally, the upper internals and control rod drive shafts are lifted from the reactor vessel using a reactor internals lifting rig. This final lift exposes the reactor core.
The tedious disassembly procedure is reversed for reinstallation of the elements following refueling.
The entire refueling process requires some three to six weeks to complete.
Evaluation of the cost, in terms of reactor downtime, of refueling a standard-type nuclear reactor provided a large economic incentive to reduce the time necessary to refuel. The ensuing effort resulted in the design of a new reactor called the rapid refueling reactor. This design, disclosed generally in
U.S. Patent No. 4,158,599, involves the consolidation of all components and subassemblies of the upper structure of a nuclear reactor into a single integrated head package. The integrated head package may then be lifted with all cabling and cable supports still attached, as disclosed in U.S. Patent No. 3,836,430, to expose the core of the reactor.
U.S. Patent No. 3,836,429 discloses the consolidation of features of the upper structure of a nuclear reactor to embody the integrated head package of the rapid refueling reactor. During refueling, all components and subassemblies which were individually detached from the reactor vessel of the standard-type reactor remain fixedly attached to the vessel closure head of the rapid refueling reactor.
These components and subassemblies include all cabling, all components associated with the upper internals package, such as upper support plate, support columns and upper core plate, control rod drive mechanisms and the control rod drive shafts.
The control rod clusters are also removed as a part of the integrated head package of the rapid refueling design.
The rapid refueling reactor involves significant structural alterations to the design of the standardtype reactor in order to facilitate attachment of the upper internals package to the vessel closure head in a structurally sufficient manner. As a result, the rapid refueling reactor cannot be implemented as a retrofit of existing standard-type reactors. Hence, a significant problem associated with lengthy refueling times still exists as to standard-type reactors in operation and currently under construction.
Accordingly, it is the principal object of the present invention to provide a head package for a reactor structure which permits both rapid refueling and implementation with the standard-type reactor structure.
With this object in view, the present invention resides in an integrated reactor head package for decreasing the time required to disassemble and reassemble a standard-type reactor vessel during refueling operations, said head package consisting of an integrated arrangement of a pressure vessel closure head for sealingly closing a reactor vessel, control rod drive mechanisms for controlling position of control rod clusters within a reactor core, a cooling shroud for enclosing the control rod drive mechanisms and for retaining cooling environment therein, a missile shield for providing lateral support to said control rod drive mechanisms and for preventing ejection of said control rod drive mechanisms, means for attaching a lifting crane to said head package for lifting said head package onto and off of the reactor vessel, a plurality of vertical lifting rods linking said lifting crane attaching means with said closure head for providing structural support to said head package, a plurality of hoist assemblies for handling stud tensioner tools and stud removal tools, means for supporting said hoist assemblies, a plurality of cooling fans attached to said cooling shroud for directing flow of cooling air within said cooling shroud, a cable tray assembly for supporting cables routed between said head package and an operating floor, which cable tray assembly is rapidly detachable from said head package, said assembly including a connector plate for facilitating rapid detachment of said cable tray assembly from said head package, and a tray for supporting the cable between said connector plate and points of penetration into said cooling shroud.
With the arrangement according to the present invention, the time required to refuel a standard-type reactor is substantially reduced by the employment of an integrated head package which consolidates many of the components and subassemblies of the upper reactor structure and which may be removed from the reactor vessels in a single lift.
The invention will become more readily apparent from the following description of a preferred embodiment thereof shown, by way of example only, in the accompanying drawings, in which the single
Figure shows a perspective view of the invention with a cutaway in appropriate places to reveal detail.
The basic operational reactor components embraced by this invention are a pressure vessel head with control rod drive mechanisms, a lifting rig, a missile shield, lifting rods, a cooling shroud, cable tray and cabling, cooling fans, an operator stand, and hoist assemblies. Detailed description of the structure and function of these components exists in the prior art and will not be undertaken here. The discussion below is directed to a combination of these components resulting in an improved integrated head package for the standard-type reactor.It should be noted at the outset that this invention, embodied as a standard integrated head package, does not embrace an upper internals package or control rod assemblies as does the head package of the previously referenced rapid refueling reactor, because the addition of these subassemblies would necessitate major structural alterations to the standard-type reactor vessel.
The Figure depicts a standard integrated head package. Athree-legged head lifting rig 12 is pinconnected to a missile shield assembly 14. The missile shield assembly 14 is supported on three lift rods 16 that attach to a reactor vessel head 18. The missile shield assembly 14 is generally a heavy reinforced plate of steel for restraining and intercepting a control rod drive housing in the event of a major problem.
A cooling shroud 20 is mounted directly to a top of the head and surrounds control rod drive mechanisms 22 which control movement of the control rod clusters into and out of the core. The cooling shroud 20 provides a major support structure for the head package as well as defining an enclosure which provides a cooling environment for the control rod drive mechanisms 22. Cooling fans 24 mount directliy to the cooling shroud 20. Lift rods 16 are tied into the cooling shroud 20 to provide additional rigidity to the structure and to transfer a lifting load from the missile shield 14to the vessel head 18. Cabling 26 is routed from the top of the control rod drive mechanisms 22 around the top of the standard integrated head package 10 to a connector plate 28 on the side of the structure.From the connector plate 28, the cabling is routed along a cable tray 30 to the respective cable terminations.
The cable tray 30 is shorter than the cable tray of the rapid refueling reactor so as to conform to the particular geometry of the standard-type reactor plants. The cable tray is supported at the reactor end on the cooling shroud 20 and at the other end on supports on a steam generator wall (not shown). As part of the refueling operations, the cabling 26 is disconnected at the connector plate 28 and stored on the cable tray 30. The cable tray 30 can then be pivoted at the operating floor end to a storage position apart from the reactor vessel. This arrangement differs from the cable tray arrangement of the rapid refueling reactor, where the layout within containment permits the cable tray to remain attached to the head structure during refueling.
The cooling shroud 20 is made in four sections that bolt together as opposed to three sections on the rapid refueling design. A lower shroud 20a, or first section, bolts directly to the top of the vessel head 18. The lower shroud 20a comprises a plurality of doors 32 permitting maintenance access to the vessel head insulation and instrumentation thermocouple columns (not shown). The lower shroud 20a also supports baffling (not shown) which surrounds the control rod drive mechanisms 22 and is used to direct the flow of cooling air.
A middle shroud 20b bolts to the-top of the lower shroud 20a. This section supports baffling as well as hoist supports 34. The hoist supports 34 comprise two tracks circulating the perimeter of the middle shroud 20b. An outer track supports the main trolleys 36 on the hoist assemblies 38. An inner track is used as a counterbalance support for the hoist assemblies 38. The hoist assemblies 38 are used to maneuver stud tensioner tools and stud removal tools during refueling activities.
An upper shroud 20c bolts to the top of the middle shroud 20b and supports baffling (not shown) and a plurality of control rod drive mechanism cooling fans 24. The cooling fans 24 circulate air within the shroud 20 to transfer waste heat from the control rod drive mechanisms 22.
A messenger tray assembly 20d, which encircles the perimeter of the upper shroud 20c, is used to support control rod drive mechanism power and instrumentation cabling 26. Cabling from the control rod drive mechanisms 22 and from thermocouples (not shown), passes along wire supports (not shown) to the messenger tray assembly 20d. All cablings converges at a connector plate 28 which links the cable tray 30 to the messenger tray assembly 20d. The use of the messenger tray assembly 20d and connector plate 28 facilitates rapid disconnection and reconnection of the cable tray from the integrated head package, a procedure which is unnecessaryforthe rapid refueling reactor.
The three vertical lifting rods 16 pin-attach to the vessel head 18 and are attached to the cooling shroud 20 at two locations along their length. The lifting rods 16 serve to transiate a lifting force applied by a crane from the missile shield assembly 14 to the vessel head 18. The lifting rods 16 are permitted to move vertically, relative to the shroud 20, but are restrained from horizontal movement. A bullet nose is machined at a top end 42 of the lifting rods 16 to provide guidance when lowering the missile shield assembly 14 onto the lifting rods 16.
The missile shield assembly 14 comprises a circular flat plate 44 which is bolted to the lift lugs 46, which pin-attach to the lifting rig 12. The flat plate 44 is punctuated by a plurality of chamfered holes 48 to permit protrusion of the control rod drive mechanism housing extensions 50 therethrough. This arrangement provides lateral support to the control rod drive mechanisms 22 and prevents any part of the mechanism 22 from penetrating the containment housing (not shown) in the event of a major break.
The holes 48 in the missile shield assembly 14 of the invention are chamfered to facilitate the process of installation. The bolted flat-plate design of the missile shield assembly 14 of the integrated head package 10 differs from the welded egg-crate pattern of the missile shield in the prior art. The bolted flat-plate design improves the manufacturability of the assembly 14, provides a safer and more convenient operator working surface, and eliminates certain requirements applicable to weldments (American Society of Mechanical Engineers Boiler and
Pressure Vessel Code, Section Ill).
An operator stand 52, bolted directly to the missile shield plate 44, provides safe and convenient access to the eye of the lifting rig 12 for connection of the polar crane hook (not shown) thereto.
Thus, the standard integrated head package provides in a neat, compact design, a system that reduces reactor downtime and decreases manpower requirements by reducing the number of operations required to assemble and disassemble the standard reactor vessel during refueling.
Claims (6)
1. An integrated reactor head package for decreasing the time required to disassemble and reassemble a standard-type reactor vessel during refueling operations, said head package being characterized by an integrated arrangement of a pressure vessel closure head (18) for sealingly closing a reactor vessel, control rod drive mechanisms (22) for controlling position of control rod clusters within a reactor core, a cooling shroud (20) for enclosing the control rod drive mechanisms (22) and for retaining cooling environment therein, a missile shield (14) for providing lateral support to said control rod drive mechanisms (22) and for preventing ejection of said control rod drive mechanisms (22), means (12) for attaching a lifting crane to said head package for lifting said head package onto and off of the reactor vessel, a plurality of vertical lifting rods (16) linking said lifting crane attaching means with said closure head (18) for providing structural support to said head package, a plurality of hoist assemblies (38) for handling stud tensioner tools and stud removal tools, means (34, 36) for supporting said hoist assemblies (38), a plurality of cooling fans (24) attached to said cooling shroud for directing flow of cooling air within said cooling shroud (20), a cable tray assembly (28, 30) for supporting cables routed between said head package and an operating floor, which cable tray assembly (28, 30) is rapidly detachable from said head package, said assembly including a connector plate (28) for facilitating rapid detachment of said cable tray assembly (28, 30) from said head package, and a tray (30) for supporting the cable between said connector plate and points of penetration into said cooling shroud.
2. A reactor head package according to claim 1, wherein said cooling shroud (20) comprises a plurality of sections (20a, b, c) which stack one on top of the other and bolted together, and wherein a lower section (20a) of said cooling shroud (20) comprises a plurality of doors providing maintenance access to interior apparatus.
3. A reactor head package according to claim 1 or 2, characterized in that said missile shield (14) comprises a flat plate having a plurality of chamfered holes to facilitate installation of said missile shield over said control rod drive mechanisms, and wherein said missile shield is a top for an enclosure formed by said cooling shroud.
4. A reactor head package according to claim 1,2 or 3, characterized in that said means (12) for attaching a lifting crane to said head package comprises a tripod lifting rig attached to said missile shield (14), said lifting rig having an eye at a peak of said tripod for accepting a hook from the lifting crane.
5. A reactor head package according to any of claims 1 to 4, characterized in that said vertical lifting rods (16) have a bullet shaped nose (42) at an upper end facilitating installation of said missile shield (14) thereon.
6. A reactor head package according to any of claims 1 to 5, characterized in that said means (34, 36) for supporting said hoist assemblies (38) comprises two concentric tracks circulating the perimeter of said cooling shroud (20) and being attached thereto.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US27007381A | 1981-06-03 | 1981-06-03 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| GB2100496A true GB2100496A (en) | 1982-12-22 |
| GB2100496B GB2100496B (en) | 1985-06-05 |
Family
ID=23029789
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB8216189A Expired GB2100496B (en) | 1981-06-03 | 1982-06-03 | Standard integrated head package |
Country Status (12)
| Country | Link |
|---|---|
| JP (2) | JPS57211588A (en) |
| KR (1) | KR890002381B1 (en) |
| BE (1) | BE893405A (en) |
| DE (1) | DE3217166A1 (en) |
| EG (1) | EG16266A (en) |
| ES (1) | ES8406130A1 (en) |
| FR (1) | FR2511540A1 (en) |
| GB (1) | GB2100496B (en) |
| IL (1) | IL65686A (en) |
| IT (1) | IT1152171B (en) |
| SE (1) | SE446569B (en) |
| YU (1) | YU106282A (en) |
Cited By (20)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0131168A1 (en) * | 1983-07-05 | 1985-01-16 | Westinghouse Electric Corporation | Thermal insulation of nuclear reactor |
| EP0142383A2 (en) * | 1983-11-16 | 1985-05-22 | Westinghouse Electric Corporation | Refueling of nuclear reactors |
| EP0154113A2 (en) * | 1984-02-03 | 1985-09-11 | Westinghouse Electric Corporation | Modular head assembly for a pressure vessel of a nuclear reactor |
| US4699752A (en) * | 1985-09-13 | 1987-10-13 | Brahm Leroy D | Shielding device |
| EP0297881A2 (en) * | 1987-06-29 | 1989-01-04 | Westinghouse Electric Corporation | Integrated head package for a nuclear reactor |
| US4857265A (en) * | 1986-12-24 | 1989-08-15 | Framatome | Wiring installation for connection of electric devices of a nuclear reactor |
| US4961899A (en) * | 1984-08-23 | 1990-10-09 | Westinghouse Electric Corp. | Multiple-cable connecting device for a nuclear reactor |
| FR2704679A1 (en) * | 1993-04-27 | 1994-11-04 | Framatome Sa | Pressurised water nuclear reactor comprising an anti-ejection retention device for vessel head penetration adapters |
| FR2704680A1 (en) * | 1993-04-27 | 1994-11-04 | Framatome Sa | Device for retaining the upper end part of the vessel head penetration adapters of a nuclear reactor cooled by pressurised water |
| WO1997042635A1 (en) * | 1996-05-09 | 1997-11-13 | Combustion Engineering, Inc. | Integral head rig, head area cable tray and missile shield for pressurized water reactor |
| EP0820068A1 (en) * | 1996-07-16 | 1998-01-21 | Westinghouse Electric Corporation | Head assembly |
| US5930321A (en) * | 1996-07-16 | 1999-07-27 | Cbs Corporation | Head assembly |
| FR2883096A1 (en) * | 2005-03-14 | 2006-09-15 | Framatome Anp Sas | Nuclear reactor thermocouple column replacement procedure uses underwater intervention stand and alignment pins for intermediate supporting structure |
| US7158605B2 (en) * | 2003-09-24 | 2007-01-02 | Westinghouse Electric Co Llc | Head assembly |
| US7567645B2 (en) * | 2005-07-19 | 2009-07-28 | Advent Engineering Services, Inc. | Modular integrated head assembly |
| CN103474112A (en) * | 2012-06-08 | 2013-12-25 | 中国核动力研究设计院 | Reactor internal hoisting tool |
| CN103871499A (en) * | 2012-12-13 | 2014-06-18 | 中国核动力研究设计院 | CRDM cooling enclosing plate and wind pipe assembly for integrated reactor roof |
| WO2014143270A2 (en) | 2013-01-15 | 2014-09-18 | Westinghouse Electric Company Llc | Apparatus and method for removing the upper internals from a nuclear reactor pressurized vessel |
| US9659674B2 (en) | 2012-04-27 | 2017-05-23 | Westinghouse Electric Company Llc | Instrumentation and control penetration flange for pressurized water reactor |
| WO2022117318A1 (en) * | 2020-12-03 | 2022-06-09 | Rolls-Royce Smr Limited | Nuclear power plant system |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100844439B1 (en) * | 2007-01-02 | 2008-07-07 | 한국전력기술 주식회사 | Modular reactor head area assembly |
| CN103871496B (en) * | 2012-12-13 | 2017-07-18 | 中国核动力研究设计院 | A kind of integrated heap roof construction suitable for presurized water reactor |
| CN103331597B (en) * | 2013-06-21 | 2015-05-06 | 山东核电设备制造有限公司 | Novel screw thread assembling device |
| KR101551852B1 (en) | 2014-08-08 | 2015-09-08 | 한국전력기술 주식회사 | Anti-Seismic Appratus for Control Element Drive Mechanism |
Family Cites Families (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1337090A (en) * | 1970-07-08 | 1973-11-14 | Westinghouse Electric Corp | Method of refluelling reactor |
| US3752737A (en) * | 1970-07-08 | 1973-08-14 | Westinghouse Electric Corp | Combination of nuclear reactor and missile shield |
| US3836429A (en) * | 1970-07-08 | 1974-09-17 | Westinghouse Electric Corp | Means for rapidly exposing the core of a nuclear reactor for refueling |
| US4158599A (en) * | 1970-07-08 | 1979-06-19 | Westinghouse Electric Corp. | Method of refueling reactor |
| US3836430A (en) * | 1970-07-08 | 1974-09-17 | Westinghouse Electric Corp | Cable support structure for enabling a nuclear reactor to be refueled rapidly |
| JPS50127091A (en) * | 1974-03-18 | 1975-10-06 | ||
| FR2317394A1 (en) * | 1975-07-10 | 1977-02-04 | Roannais Const Textiles Atel | DEVICE FOR THERMAL TREATMENT OF WIRES |
| JPS5911864B2 (en) * | 1975-07-14 | 1984-03-19 | 武田薬品工業株式会社 | Blood leak detection device |
| US4086132A (en) * | 1976-05-13 | 1978-04-25 | Westinghouse Electric Corporation | Combined fuel assembly and thimble plug gripper for a nuclear reactor |
-
1982
- 1982-05-04 IL IL65686A patent/IL65686A/en unknown
- 1982-05-07 DE DE19823217166 patent/DE3217166A1/en active Granted
- 1982-05-14 IT IT21267/82A patent/IT1152171B/en active
- 1982-05-18 YU YU01062/82A patent/YU106282A/en unknown
- 1982-06-02 FR FR8209613A patent/FR2511540A1/en active Granted
- 1982-06-02 SE SE8203412A patent/SE446569B/en not_active IP Right Cessation
- 1982-06-02 ES ES512799A patent/ES8406130A1/en not_active Expired
- 1982-06-03 KR KR8202484A patent/KR890002381B1/en active
- 1982-06-03 JP JP57094142A patent/JPS57211588A/en active Pending
- 1982-06-03 BE BE0/208262A patent/BE893405A/en not_active IP Right Cessation
- 1982-06-03 GB GB8216189A patent/GB2100496B/en not_active Expired
- 1982-06-04 EG EG314/82A patent/EG16266A/en active
-
1990
- 1990-09-10 JP JP1990094104U patent/JPH0351398U/ja active Pending
Cited By (32)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0131168A1 (en) * | 1983-07-05 | 1985-01-16 | Westinghouse Electric Corporation | Thermal insulation of nuclear reactor |
| EP0142383A2 (en) * | 1983-11-16 | 1985-05-22 | Westinghouse Electric Corporation | Refueling of nuclear reactors |
| EP0142383A3 (en) * | 1983-11-16 | 1985-11-21 | Westinghouse Electric Corporation | Refueling of nuclear reactors |
| EP0154113A2 (en) * | 1984-02-03 | 1985-09-11 | Westinghouse Electric Corporation | Modular head assembly for a pressure vessel of a nuclear reactor |
| EP0154113A3 (en) * | 1984-02-03 | 1986-08-27 | Westinghouse Electric Corporation | Modular head assmebly for a pressure vessel of a nuclear reactor |
| US4678623A (en) * | 1984-02-03 | 1987-07-07 | Westinghouse Electric Corp. | Modular head assembly and method of retrofitting existing nuclear reactor facilities |
| US4961899A (en) * | 1984-08-23 | 1990-10-09 | Westinghouse Electric Corp. | Multiple-cable connecting device for a nuclear reactor |
| US4865801A (en) * | 1985-09-13 | 1989-09-12 | Brahm, Brown, Et Al. | Shielding device |
| US4699752A (en) * | 1985-09-13 | 1987-10-13 | Brahm Leroy D | Shielding device |
| US4857265A (en) * | 1986-12-24 | 1989-08-15 | Framatome | Wiring installation for connection of electric devices of a nuclear reactor |
| EP0297881A2 (en) * | 1987-06-29 | 1989-01-04 | Westinghouse Electric Corporation | Integrated head package for a nuclear reactor |
| US4830814A (en) * | 1987-06-29 | 1989-05-16 | Westinghouse Electric Corp. | Integrated head package for a nuclear reactor |
| EP0297881A3 (en) * | 1987-06-29 | 1989-11-29 | Westinghouse Electric Corporation | Integrated head package for a nuclear reactor |
| FR2704679A1 (en) * | 1993-04-27 | 1994-11-04 | Framatome Sa | Pressurised water nuclear reactor comprising an anti-ejection retention device for vessel head penetration adapters |
| FR2704680A1 (en) * | 1993-04-27 | 1994-11-04 | Framatome Sa | Device for retaining the upper end part of the vessel head penetration adapters of a nuclear reactor cooled by pressurised water |
| WO1997042635A1 (en) * | 1996-05-09 | 1997-11-13 | Combustion Engineering, Inc. | Integral head rig, head area cable tray and missile shield for pressurized water reactor |
| EP0820068A1 (en) * | 1996-07-16 | 1998-01-21 | Westinghouse Electric Corporation | Head assembly |
| US5930321A (en) * | 1996-07-16 | 1999-07-27 | Cbs Corporation | Head assembly |
| US5742652A (en) * | 1996-07-16 | 1998-04-21 | Westinghouse Electric Corporation | Head assembly |
| US6061415A (en) * | 1998-04-07 | 2000-05-09 | Westinghouse Electric Company Llc | Missile shield for a nuclear reactor pressure vessel |
| US7158605B2 (en) * | 2003-09-24 | 2007-01-02 | Westinghouse Electric Co Llc | Head assembly |
| CN1841569B (en) * | 2005-03-14 | 2011-02-09 | 法玛通Anp公司 | Method and device for changing nuclear reactor upper component at least a thermoelectric couple column |
| FR2883096A1 (en) * | 2005-03-14 | 2006-09-15 | Framatome Anp Sas | Nuclear reactor thermocouple column replacement procedure uses underwater intervention stand and alignment pins for intermediate supporting structure |
| US7567645B2 (en) * | 2005-07-19 | 2009-07-28 | Advent Engineering Services, Inc. | Modular integrated head assembly |
| US9659674B2 (en) | 2012-04-27 | 2017-05-23 | Westinghouse Electric Company Llc | Instrumentation and control penetration flange for pressurized water reactor |
| CN103474112A (en) * | 2012-06-08 | 2013-12-25 | 中国核动力研究设计院 | Reactor internal hoisting tool |
| CN103474112B (en) * | 2012-06-08 | 2016-05-18 | 中国核动力研究设计院 | Reactor core internals lifting device |
| CN103871499A (en) * | 2012-12-13 | 2014-06-18 | 中国核动力研究设计院 | CRDM cooling enclosing plate and wind pipe assembly for integrated reactor roof |
| WO2014143270A2 (en) | 2013-01-15 | 2014-09-18 | Westinghouse Electric Company Llc | Apparatus and method for removing the upper internals from a nuclear reactor pressurized vessel |
| EP2946390A4 (en) * | 2013-01-15 | 2016-08-24 | Westinghouse Electric Corp | Apparatus and method for removing the upper internals from a nuclear reactor pressurized vessel |
| US10102935B2 (en) | 2013-01-15 | 2018-10-16 | Westinghouse Electric Company Llc | Method of removing upper internals from a nuclear reactor pressurized vessel |
| WO2022117318A1 (en) * | 2020-12-03 | 2022-06-09 | Rolls-Royce Smr Limited | Nuclear power plant system |
Also Published As
| Publication number | Publication date |
|---|---|
| GB2100496B (en) | 1985-06-05 |
| FR2511540B1 (en) | 1985-05-17 |
| ES512799A0 (en) | 1984-07-01 |
| JPH0351398U (en) | 1991-05-20 |
| DE3217166A1 (en) | 1982-12-23 |
| YU106282A (en) | 1990-12-31 |
| KR890002381B1 (en) | 1989-07-02 |
| EG16266A (en) | 1991-12-30 |
| DE3217166C2 (en) | 1991-03-14 |
| KR840000942A (en) | 1984-03-26 |
| FR2511540A1 (en) | 1983-02-18 |
| SE8203412L (en) | 1982-12-04 |
| ES8406130A1 (en) | 1984-07-01 |
| IT8221267A0 (en) | 1982-05-14 |
| BE893405A (en) | 1982-12-03 |
| SE446569B (en) | 1986-09-22 |
| IT1152171B (en) | 1986-12-31 |
| IL65686A (en) | 1985-07-31 |
| JPS57211588A (en) | 1982-12-25 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PCNP | Patent ceased through non-payment of renewal fee |
Effective date: 19920603 |