CN114220566B - Method for plugging narrow gap in reactor pressure vessel of nuclear power station - Google Patents
Method for plugging narrow gap in reactor pressure vessel of nuclear power station Download PDFInfo
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- CN114220566B CN114220566B CN202111274707.8A CN202111274707A CN114220566B CN 114220566 B CN114220566 B CN 114220566B CN 202111274707 A CN202111274707 A CN 202111274707A CN 114220566 B CN114220566 B CN 114220566B
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- plugging
- graphite packing
- threaded sleeve
- sleeve
- filled
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- 238000000034 method Methods 0.000 title claims abstract description 24
- 230000007246 mechanism Effects 0.000 claims abstract description 29
- 238000012856 packing Methods 0.000 claims description 28
- 229910002804 graphite Inorganic materials 0.000 claims description 27
- 239000010439 graphite Substances 0.000 claims description 27
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 26
- 239000002657 fibrous material Substances 0.000 claims description 13
- YKTSYUJCYHOUJP-UHFFFAOYSA-N [O--].[Al+3].[Al+3].[O-][Si]([O-])([O-])[O-] Chemical compound [O--].[Al+3].[Al+3].[O-][Si]([O-])([O-])[O-] YKTSYUJCYHOUJP-UHFFFAOYSA-N 0.000 claims description 12
- 238000010521 absorption reaction Methods 0.000 claims description 12
- 238000005056 compaction Methods 0.000 claims description 6
- 239000000463 material Substances 0.000 claims description 4
- 238000009434 installation Methods 0.000 claims description 3
- 239000000126 substance Substances 0.000 claims description 3
- 239000001307 helium Substances 0.000 abstract description 9
- 229910052734 helium Inorganic materials 0.000 abstract description 9
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 abstract description 9
- 239000007789 gas Substances 0.000 abstract description 6
- 238000013461 design Methods 0.000 abstract description 4
- 229910001220 stainless steel Inorganic materials 0.000 description 6
- 239000010935 stainless steel Substances 0.000 description 5
- 238000012360 testing method Methods 0.000 description 4
- 239000000428 dust Substances 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000007789 sealing Methods 0.000 description 2
- BPQQTUXANYXVAA-UHFFFAOYSA-N Orthosilicate Chemical compound [O-][Si]([O-])([O-])[O-] BPQQTUXANYXVAA-UHFFFAOYSA-N 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000004075 alteration Effects 0.000 description 1
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 230000008520 organization Effects 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/028—Seals, e.g. for pressure vessels or containment vessels
- G21C13/0285—Seals, e.g. for pressure vessels or containment vessels for container apertures
-
- 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
Abstract
The invention provides a method for plugging a narrow gap in a reactor pressure vessel of a nuclear power station. The hot helium gas can be effectively prevented from flowing into the driving mechanism, the generation of heat convection is prevented, the temperature of the inner cavity of the driving mechanism and the temperature of the flange of the driving shell tube nozzle are further reduced, and the running temperature of the driving mechanism is guaranteed not to exceed the design temperature.
Description
Technical Field
The invention relates to the technical field of plugging, relates to a high-temperature-resistant and irradiation-resistant narrow-slit plugging technology, and particularly relates to a method for plugging a narrow slit in a reactor pressure vessel of a nuclear power station.
Background
The absorption ball shutdown system is used as a standby shutdown system of the high-temperature gas cooled reactor and can enable the reactor to reach a lower cold shutdown state when being used together with the control rod system. Each reactor of the high-temperature gas cooled reactor comprises 6 sets of absorption ball shutdown falling ball devices, each absorption ball shutdown falling ball device mainly comprises a driving mechanism and a ball storage tank, the working temperature of the driving mechanism is 150 ℃ under the normal operation condition, and the working environment medium is helium.
When a high-temperature gas cooled reactor is subjected to a thermal test, the temperature of a driving mechanism of an absorption ball shutdown system is found to exceed the design temperature, and the analysis reason is that a penetrating annular cavity (namely a narrow slit 14) exists between an upper end enclosure 10 of a pressure vessel and the absorption ball driving mechanism, the structure is shown in fig. 1, under the drive of helium pressure difference, hot helium continuously flows into and flows out of an inner cavity 13 of the absorption ball driving mechanism, so that the temperature rise of the absorption ball driving mechanism is abnormal, the helium flows upwards from the narrow slit 14 between a vertical pipe 1 and a driving shell and tube nozzle 9, flows into the inner cavity 13 of the driving mechanism, then flows downwards from the cavity between a ball dropping pipe 16 and the vertical pipe 1, and flows into the pressure vessel.
After the high-temperature gas-cooled reactor finishes a thermal test, the reactor is cooled to normal temperature and normal pressure, a company organization in Shishimawan opens a manhole of a top cover of a reactor pressure vessel, enters an upper end enclosure 10 of the reactor pressure vessel, and seals a gap (namely a narrow gap 14) between the lower part of a driving shell pipe nozzle 9 and the lower part of a vertical pipe 1. After plugging, hot helium can be effectively prevented from flowing into the driving mechanism, so that heat convection is prevented from being generated, the temperature of the inner cavity 13 of the driving mechanism and the temperature of the flange of the driving shell tube nozzle are further reduced, and the running temperature of the driving mechanism is guaranteed not to exceed the design temperature.
Disclosure of Invention
The present invention is directed to solving, at least to some extent, one of the technical problems in the related art.
The invention aims to provide a method for plugging a narrow gap in a reactor pressure vessel of a nuclear power station, which can effectively prevent hot helium from flowing into a driving mechanism, prevent thermal convection from being generated, further reduce the temperature of an inner cavity of the driving mechanism and a flange of a nozzle of a driving shell and tube and ensure that the operating temperature of the driving mechanism does not exceed the designed temperature.
The embodiment of the application provides a method for plugging a narrow gap in a pressure vessel of a nuclear power plant reactor, wherein plugging materials are filled into the narrow gap from bottom to top from a notch below a driving shell tube nozzle and a vertical tube below an upper end socket of the pressure vessel, and are compacted through a compaction mechanism.
In some embodiments, the plug comprises an alumina silicate fiber material and a graphite packing.
In some embodiments, the filling method of the plugging substance is as follows: the upper gap is filled and compacted by adopting an aluminum silicate fiber material, and the lower gap is filled and compacted by adopting a graphite packing.
In some embodiments, 1-2 check rings are arranged in the middle of the aluminum silicate fiber material, one check ring is arranged after the aluminum silicate fiber material is filled, and one check ring is arranged after the graphite packing is filled.
In some embodiments, the retainer ring is formed by mutually inserting two semi-ring structures.
In some embodiments, the compaction method is: when the graphite packing is plugged to be close to the lower opening, a threaded sleeve is arranged below the opening, a jacking nut is arranged at the thread at the upper part of the threaded sleeve, a locking sleeve is arranged above the jacking nut, and the upper part of the locking sleeve is clamped into the narrow slit and tightly props against the lowest check ring; and (4) upwards rotating the jacking nut, and upwards extruding the locking sleeve to compact the graphite packing.
In some embodiments, the threaded sleeve comprises a first threaded sleeve and a second threaded sleeve which are mutually spliced, the jacking nut comprises a first nut portion and a second nut portion which are mutually spliced, and the locking sleeve comprises a first locking sleeve and a second locking sleeve which are mutually spliced.
In some embodiments, the first threaded sleeve and the second threaded sleeve are both provided with locking portions, the locking portion of the first threaded sleeve and the locking portion of the second threaded sleeve are detachably connected through a screw, the first nut portion and the second nut portion are detachably connected through a fixing plate and a screw, and the first locking sleeve and the second locking sleeve are detachably connected through a fixing plate and a screw.
In some embodiments, after the graphite packing is compacted by the locking sleeve, the jacking nut is rotated downwards, the graphite packing is continuously filled into the narrow gap, and then the jacking nut is rotated upwards, and the graphite packing is compacted repeatedly.
In some embodiments, the plug is compacted with a sheet tool prior to installation of the compaction mechanism.
The invention has the beneficial effects that: after plugging, hot helium can be effectively prevented from flowing into the driving mechanism, thermal convection is prevented from being generated, the temperature of the inner cavity of the driving mechanism and the temperature of the flange of the driving shell tube nozzle are further reduced, the running temperature of the driving mechanism is not higher than the design temperature, and the narrow slit plugging device is suitable for narrow slit plugging in high-temperature and irradiation environments.
Additional aspects and advantages of the invention will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the invention.
Drawings
The above and/or additional aspects and advantages of the present invention will become apparent from and readily appreciated by reference to the following description of the embodiments taken in conjunction with the accompanying drawings,
wherein:
FIG. 1 is a schematic illustration of the location of a slot within a reactor pressure vessel of a nuclear power plant;
FIG. 2 is a schematic illustration of helium gas flow into and out of the interior cavity of the drive mechanism of FIG. 1;
FIG. 3 is a schematic diagram of a method for plugging a narrow gap inside a reactor pressure vessel of a nuclear power plant according to an embodiment of the invention;
FIG. 4 is a schematic view of a retainer ring;
FIG. 5 is a schematic view of a threaded sleeve;
FIG. 6 is a schematic structural view of a jacking nut;
FIG. 7 is a schematic view of the locking sleeve;
reference numerals are as follows:
1-a riser; 2-an aluminum silicate fiber material; 3-a retainer ring; 4-graphite packing; 5-locking sleeve; 6-jacking nuts; 7-a thread bushing; 8-a dust collector assembly; 9-drive case nozzle; 10-sealing an upper end of the pressure container; 11-a fixing sheet; 12-a locking part; 13-driving mechanism inner cavity; 14-narrow slit; 15-at the gap; 16-bulb falling tube.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings. The embodiments described below with reference to the accompanying drawings are illustrative and intended to explain the present invention and should not be construed as limiting the present invention.
The method for plugging a narrow gap inside a reactor pressure vessel of a nuclear power plant according to an embodiment of the invention is described below with reference to the accompanying drawings.
As shown in fig. 3, the embodiment of the present application proposes a method for plugging a narrow gap inside a reactor pressure vessel of a nuclear power plant, wherein plugging substances are filled into the narrow gap 14 from the lower opening 15 between a driving shell nozzle 9 and a riser 1 from bottom to top under an upper sealing head 10 of the pressure vessel and are compacted by a compacting mechanism.
The specific operation steps are as follows:
(1) The upper gap of the narrow gap 14 is plugged by adopting a linear aluminum silicate fiber material 2, a stainless steel wire or a steel plate with a proper diameter can be used for pushing during plugging, the aluminum silicate fiber material 2 is compacted as much as possible, the total length of the plug is about 300mm, and 1 stainless steel retainer ring 3 is respectively arranged at the middle section and the tail end of the aluminum silicate fiber material 2 according to the record of the gap so as to improve the plugging strength. As shown in FIG. 4, the retainer ring 3 is formed by mutually inserting two half-ring structures through mutually matched slots and protrusions, the thickness of the retainer ring 3 is 3-4mm, and the height of the retainer ring is 10-30mm.
(2) After the tail end of the aluminum silicate fiber material 2 is installed into the check ring 3, a lower gap is plugged by the graphite packing 4, the graphite packing 4 with a proper section is used for plugging according to the record of the gap between the vertical pipe 1 of the absorption ball falling device and the driving shell pipe nozzle 9, a thin sheet tool is used for compacting during plugging, and 1 stainless steel check ring 3 is installed at the tail end of the graphite packing 4 to improve the plugging strength. Meanwhile, the gap in the optical cable groove in the narrow gap 14 is also filled and compacted by a small section of graphite packing.
(3) When the graphite packing 4 shutoff was to being close the lower part opening, installation stainless steel thread bush 7 on dust arrester subassembly 8, thread bush 7 was located the opening below, as shown in fig. 5, thread bush 7 is two semicircular structure, divide into first thread bush and second thread bush, all is equipped with locking portion 12 on the higher authority relevant position, can dismantle the connection through the screw between the locking portion of first thread bush and the locking portion 12 of second thread bush, makes thread bush 7 hold riser 1 tightly through locking screw.
(4) 2 semicircular stainless steel jacking nuts 6 are arranged at the thread part at the upper part of the thread sleeve 7, and after the two jacking nuts 6 are placed, the two jacking nuts 6 are connected by adopting a fixing piece 11 and a screw, as shown in figure 6. The spliced jacking nut 6 is matched with the thread of the thread bush 7.
(5) The upper part of the jacking nut 6 is provided with a stainless steel locking sleeve 5 with a two-half-circle structure, and the two locking sleeves 5 are connected by adopting a fixing piece 11 and a screw after being placed, as shown in figure 7. The locking sleeve 5 is contacted with the jacking nut 6 but not fixedly connected with the jacking nut. The thickness of the sleeve at the upper end of the spliced locking sleeve 5 can be just inserted into the narrow slit 14 and tightly propped against the lowermost retainer ring 3.
(6) Through rotating jacking nut 6, constantly jacking lock sleeve 5 makes graphite packing 4 compression play the shutoff effect with compaction graphite packing 4, and if necessary the jacking nut 6 of screwing down is again to the certain amount of graphite packing 4 of packing into in the narrow slit 14 and is screwed up jacking nut 6 once more, guarantees graphite packing 4 compaction many times repeatedly. And (5) completing plugging.
The effect is as follows: after plugging is completed, scientific researchers develop a supplementary thermal state function test on the high-temperature gas cooled reactor, during the supplementary thermal test, the temperature of the inner cavity of the absorption ball driving mechanism is continuously monitored, the temperature of the inner cavity of 12 sets of absorption ball driving mechanisms is lower than 150 ℃, the technical requirement is met, and the feasibility of the plugging method is verified.
In the description of the present invention, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the invention and to simplify the description, and are not intended to indicate or imply that the referenced devices or elements must have a particular orientation, be constructed and operated in a particular orientation, and are therefore not to be considered limiting of the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of the feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; may be mechanically coupled, may be electrically coupled or may be in communication with each other; they may be directly connected or indirectly connected through intervening media, or they may be connected internally or in any other suitable relationship, unless expressly stated otherwise. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the present invention, unless otherwise expressly stated or limited, the first feature "on" or "under" the second feature may be directly contacting the first and second features or indirectly contacting the first and second features through an intermediate. Also, a first feature "on," "over," and "above" a second feature may be directly or diagonally above the second feature, or may simply indicate that the first feature is at a higher level than the second feature. A first feature "under," "beneath," and "under" a second feature may be directly under or obliquely under the second feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
In the present disclosure, the terms "one embodiment," "some embodiments," "an example," "a specific example," or "some examples" and the like mean that a specific feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Moreover, various embodiments or examples and features of various embodiments or examples described in this specification can be combined and combined by one skilled in the art without being mutually inconsistent.
Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations can be made to the above embodiments by those of ordinary skill in the art within the scope of the present invention.
Claims (10)
1. A method for plugging a narrow gap in a reactor pressure vessel of a nuclear power station is characterized in that plugging materials are filled into the narrow gap formed by the upper end cover of the pressure vessel and an absorption ball driving mechanism in an absorption ball shutdown system from bottom to top from a notch below a driving shell pipe nozzle and a vertical pipe below the upper end cover of the pressure vessel, and are compacted by a compacting mechanism.
2. The plugging method of claim 1, wherein the plug comprises an aluminum silicate fiber material and a graphite packing.
3. The plugging method according to claim 2, wherein the plugging substance is filled by a method comprising: the upper gap is filled and compacted by adopting an aluminum silicate fiber material, and the lower gap is filled and compacted by adopting a graphite packing.
4. The plugging method according to claim 3, wherein 1-2 retainer rings are arranged in the middle of the aluminum silicate fiber material, one retainer ring is arranged after the aluminum silicate fiber material is filled, and one retainer ring is arranged after the graphite packing is filled.
5. The occlusion method of claim 4, wherein the retainer ring is formed by inserting two semi-ring structures into each other.
6. The plugging method according to claim 3, wherein the graphite packing is compacted by the method comprising the following steps: when the graphite packing is plugged to be close to the lower opening, a threaded sleeve is arranged below the opening, a jacking nut is arranged at the thread at the upper part of the threaded sleeve, a locking sleeve is arranged above the jacking nut, and the upper part of the locking sleeve is clamped into the narrow slit and tightly props against the lowest check ring; and (4) upwards rotating the jacking nut, and upwards extruding the locking sleeve to compact the graphite packing.
7. The plugging method of claim 6, wherein the threaded sleeve comprises a first threaded sleeve and a second threaded sleeve that are mated to each other, the jacking nut comprises a first nut portion and a second nut portion that are mated to each other, and the locking sleeve comprises a first locking sleeve and a second locking sleeve that are mated to each other.
8. The occlusion method of claim 7, wherein the first threaded sleeve and the second threaded sleeve are each provided with a locking portion, the locking portion of the first threaded sleeve and the locking portion of the second threaded sleeve are detachably connected by a screw, the first nut portion and the second nut portion are detachably connected by a fixing plate and a screw, and the first locking sleeve and the second locking sleeve are detachably connected by a fixing plate and a screw.
9. The plugging method of claim 6, wherein after the locking sleeve compacts the graphite packing, the jacking nut is rotated downwards, the graphite packing is continuously filled into the narrow gap, and then the jacking nut is rotated upwards, and the graphite packing is compacted repeatedly.
10. The method of plugging of claim 1 wherein the plug is compacted with a wafer tool prior to installation of the compaction mechanism.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111274707.8A CN114220566B (en) | 2021-10-29 | 2021-10-29 | Method for plugging narrow gap in reactor pressure vessel of nuclear power station |
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| CN202111274707.8A CN114220566B (en) | 2021-10-29 | 2021-10-29 | Method for plugging narrow gap in reactor pressure vessel of nuclear power station |
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| CN114220566A CN114220566A (en) | 2022-03-22 |
| CN114220566B true CN114220566B (en) | 2022-11-15 |
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| CN117174347A (en) * | 2023-07-26 | 2023-12-05 | 华能核能技术研究院有限公司 | High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof |
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| DE3104481A1 (en) * | 1981-02-09 | 1982-08-19 | GHT Gesellschaft für Hochtemperaturreaktor-Technik mbH, 5060 Bergisch Gladbach | DEVICE FOR SWITCHING OFF A HIGH TEMPERATURE CORE REACTOR |
| US10032529B2 (en) * | 2010-12-09 | 2018-07-24 | Westinghouse Electric Company Llc | Nuclear reactor internal electric control rod drive mechanism assembly |
| CN103456374B (en) * | 2013-09-03 | 2015-09-30 | 清华大学 | The reactive control method of pebble bed high temperature reactor and telescopiform control rod |
| CN108507549B (en) * | 2018-05-28 | 2020-07-28 | 中国核工业二三建设有限公司 | Method for installing and measuring graphite bricks and carbon bricks in high-temperature gas cooled reactor |
| CN111473107A (en) * | 2020-04-27 | 2020-07-31 | 中核能源科技有限公司 | High-temperature gas cooled reactor helium compressor isolation pressure maintaining maintenance method and device |
| CN113192658A (en) * | 2021-05-28 | 2021-07-30 | 中核能源科技有限公司 | Absorption ball shutdown device |
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Application publication date: 20220322 Assignee: Huaneng Hainan Changjiang Nuclear Power Co.,Ltd. Assignor: Huaneng Nuclear Energy Technology Research Institute Co.,Ltd. Contract record no.: X2023110000136 Denomination of invention: A sealing method for narrow gaps inside the pressure vessel of a nuclear power plant reactor Granted publication date: 20221115 License type: Common License Record date: 20231201 |
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