CN101839467B - Method for mounting main pipeline and main loop of pressurized water reactor nuclear power station steam generator - Google Patents
Method for mounting main pipeline and main loop of pressurized water reactor nuclear power station steam generator Download PDFInfo
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- CN101839467B CN101839467B CN2010101663526A CN201010166352A CN101839467B CN 101839467 B CN101839467 B CN 101839467B CN 2010101663526 A CN2010101663526 A CN 2010101663526A CN 201010166352 A CN201010166352 A CN 201010166352A CN 101839467 B CN101839467 B CN 101839467B
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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
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Abstract
The invention discloses a method for mounting a main return loop of a nuclear power station pressurized water reactor coolant system, which is characterized in that: a main pipeline heat section bend (16) and a main pipeline transition section bend (17) are welded at a loop nozzle of a lower seal end of the used steam generator (1); during mounting, a welding line (9) between a main pipeline heat section (13) and the main pipeline heat section bend (16) on the lower part of the steam generator (11) and a welding line (2) between the main pipeline heat section (13) and a reactor pressure container (10) can be assembled and welded simultaneously. In addition, the working amount for a welding line (5) is reduced during mounting. The mounting method can better control and guarantee the assembling and welding quality, improve the working efficiency, reduce the mounting time, and shorten the construction period.
Description
Technical field
The equipment of the invention belongs to-pipeline field is specifically related to the method for a kind of pressurized-water reactor nuclear power plant reactor coolant loop trunk line and major loop.
Background technology
The reactor coolant loop major loop is the core key equipment of pressurized-water reactor nuclear power plant.A loop of pressurized-water reactor nuclear power plant reactor coolant loop major loop is connected to form by reactor pressure vessel, steam generator, main pump, main pipe hot leg, cold section of trunk line, trunk line changeover portion etc. usually.Being installed in the pressurized-water reactor nuclear power plant construction of reactor coolant loop loop occupies critical path, and duly accomplishing Nuclear Power Station to guaranteeing the quality has material impact.When installing at the scene, a loop installation method of existing pressurized-water reactor nuclear power plant reactor coolant loop major loop normally:
-main pipe hot leg, cold section of trunk line and trunk line transition are transported into the trunk line room respectively; Wherein the position that links to each other with steam generator of main pipe hot leg one end is the main pipe hot leg elbow; The trunk line changeover portion is formed by three sections, and the position that wherein links to each other with steam generator is a trunk line changeover portion elbow;
-reactor pressure vessel, steam generator and main pump are in place respectively, and this moment, ozzle place, steam generator low head one loop wherein was not welded to connect main pipe hot leg elbow and trunk line changeover portion elbow;
-the weld seam between cold section of weld seam, reactor pressure vessel and the trunk line between welding steam generator and the main pipe hot leg elbow respectively;
-the weld seam between cold section of weld seam, main pump and the trunk line between welding reactor pressure vessel and the main pipe hot leg respectively;
Weld seam between the changeover portion elbow of-welding steam generator and trunk line changeover portion;
Weld seam between-welding trunk line changeover portion elbow and the trunk line changeover portion, the weld seam at trunk line changeover portion middle part and the weld seam between trunk line changeover portion and the main pump are accomplished the installation of a loop of pressurized-water reactor nuclear power plant reactor coolant loop major loop.
Because the space between the steam generator supporting leg is less; The weld seam between the changeover portion elbow of weld seam between steam generator and main pipe hot leg and steam generator and trunk line changeover portion; The space of welding is narrow and small; The installation condition is relatively poor, and workmen's technical ability is had relatively high expectations.Simultaneously, the weld seam group between steam generator and the main pipe hot leg is right, owing to reason difficulty such as angle of bend and manufacturing tolerance are bigger.For fear of welding stress and distortion the installation of reactor pressure vessel, steam generator is caused adverse effect; The welding simultaneously of weld seam between weld seam between steam generator and the main pipe hot leg and reactor pressure vessel and the main pipe hot leg; Generally need earlier to the weld seam welding between steam generator and the main pipe hot leg, again to the weld seam welding between reactor pressure vessel and the main pipe hot leg, so efficient is lower; The construction work amount is bigger, and the duration is longer.
Summary of the invention
The object of the present invention is to provide a kind of steam generator that is used for the pressurized-water reactor nuclear power plant reactor coolant loop.
Another object of the present invention is to provide a kind of trunk line that is used for the pressurized-water reactor nuclear power plant reactor coolant loop.
A further object of the invention provides a kind ofly can simplify installation, improve execution conditions, guarantee the installation method of welding quality and the pressurized-water reactor nuclear power plant reactor coolant loop main circuit circulates of reduction of erection time.
The present invention is achieved in that
A kind of steam generator that is used for the pressurized-water reactor nuclear power plant reactor coolant loop, its ozzle place, low head one loop has been welded to connect main pipe hot leg elbow and trunk line changeover portion elbow respectively.
A kind of trunk line that is used for the pressurized-water reactor nuclear power plant reactor coolant loop is characterized in that main pipe hot leg wherein is a straight tube, and the trunk line changeover portion is made up of two segment pipes.
A kind of installation method that adopts the pressurized-water reactor nuclear power plant reactor coolant loop main circuit circulates of above-mentioned steam generator and trunk line may further comprise the steps:
Step 4; Weld seam between welding steam generator bottom trunk line changeover portion elbow and the trunk line changeover portion, the weld seam at trunk line changeover portion middle part and the weld seam between trunk line changeover portion and the main pump are accomplished the installation of a loop of pressurized-water reactor nuclear power plant reactor coolant loop major loop respectively;
Further; The installation method of above-mentioned pressurized-water reactor nuclear power plant reactor coolant loop main circuit circulates; Wherein, weld seam between main pipe hot leg in the step 3 and the steam generator bottom main pipe hot leg elbow and the weld seam between main pipe hot leg and reactor pressure vessel welding simultaneously.
Beneficial effect of the present invention is:
Low head one loop ozzle has been welded to connect main pipe hot leg elbow and trunk line changeover portion elbow respectively when (1) dispatching from the factory owing to steam generator; Making two weld seams between original steam generator and main pipe hot leg, the trunk line changeover portion by the scene welding is installed changes in steam generator manufactory and welding; Avoided the narrow inconvenience that brings with angle of bend of on-the-spot installing space, help controlling better and the group that guarantees these two weld seams to and welding quality;
(2), make the scene of a loop of nuclear power station presurized water reactor coolant system major loop reduce the weld seam between original steam generator and the trunk line changeover portion elbow in installing because the change of steam generator structure; The installation of a plurality of loops can reduce the scene of a plurality of weld seams the welding workload is installed, and helps reducing the set-up time compression duration;
(3) after the main pipe hot leg of original tape elbow makes the main pipe hot leg of straight tube in on-the-spot the installation; Weld seam surrounding space between main pipe hot leg and the steam generator is comparatively open, with change before be between the steam generator supporting leg space-constrained situation and compare, it is better that the welding operation condition is installed; In addition; Weld seam to changing the straight tube group into to simpler and easy, therefore helps improving welding quality by the bend pipe group, reduces the set-up time;
(4) after the main pipe hot leg of original tape elbow makes the main pipe hot leg of straight tube in on-the-spot the installation; Weld seam between main pipe hot leg and the steam generator bottom main pipe hot leg elbow and the weld seam between main pipe hot leg and the reactor pressure vessel can be realized welding simultaneously, the adverse effect that when increasing work efficiency, also can avoid welding stress and distortion that major loop equipment is installed.
Description of drawings
Fig. 1 is loop structure sketch map of pressurized-water reactor nuclear power plant reactor coolant loop major loop.
Fig. 2 is the schematic top plan view of a loop of pressurized-water reactor nuclear power plant reactor coolant loop major loop.
Fig. 3 is the structural representation of a loop changeover portion of pressurized-water reactor nuclear power plant reactor coolant loop major loop.
Fig. 4 is the original steam generator of a pressurized-water reactor nuclear power plant reactor bottom sketch map.
Fig. 5 is a pressurized-water reactor nuclear power plant reactor steam generator of the present invention bottom sketch map.
Fig. 6 is the original main pipe hot leg sketch map of loop of pressurized-water reactor nuclear power plant reactor coolant loop major loop.
Fig. 7 is an original trunk line changeover portion of loop of a pressurized-water reactor nuclear power plant reactor coolant loop major loop sketch map.
Fig. 8 is a loop main pipe hot leg of a pressurized-water reactor nuclear power plant reactor coolant loop major loop of the present invention sketch map.
Fig. 9 is a loop trunk line of a pressurized-water reactor nuclear power plant reactor coolant loop major loop of the present invention changeover portion sketch map.
Among the figure, the weld seam between 1-main pipe hot leg elbow and the steam generator, the weld seam between 2-main pipe hot leg and the reactor pressure vessel; Weld seam between cold section of 3-trunk line and the reactor pressure vessel, the weld seam between cold section of 4-trunk line and the main pump, the weld seam between 5-steam generator and the trunk line changeover portion elbow; Weld seam between 6-steam generator bottom trunk line changeover portion elbow and the trunk line changeover portion, the weld seam at 7-trunk line changeover portion middle part, the weld seam between 8-trunk line changeover portion and the main pump; Weld seam between 9-main pipe hot leg and the steam generator bottom main pipe hot leg elbow, 10-reactor pressure vessel, 11-steam generator; The 12-main pump, 13-main pipe hot leg, cold section of 14-trunk line; 15-trunk line changeover portion, 16-main pipe hot leg elbow, 17-trunk line changeover portion elbow.
The specific embodiment
Below in conjunction with accompanying drawing the present invention is further introduced:
Pressurized-water reactor nuclear power plant reactor coolant loop steam generator 11 as shown in Figure 5, as to dispatch from the factory, its ozzle place, low head one loop has been welded to connect main pipe hot leg elbow 16 and trunk line changeover portion elbow 17 respectively.
As shown in Figure 8, the main pipe hot leg 13 of pressurized-water reactor nuclear power plant reactor coolant loop is a straight tube, does not comprise former main pipe hot leg elbow 16 parts.As shown in Figure 9, the trunk line changeover portion 15 of pressurized-water reactor nuclear power plant reactor coolant loop is made up of two segment pipes, does not comprise former trunk line changeover portion elbow 16.
Like Fig. 1, Fig. 2, shown in Figure 3, use the installation method of the pressurized-water reactor nuclear power plant reactor coolant loop main circuit circulates of steam generator 11, the main pipe hot leg 13 among Fig. 8 and the trunk line changeover portion 15 among Fig. 9 among Fig. 5, may further comprise the steps:
Step 4: weld seam 6, the weld seam 7 at trunk line changeover portion 15 middle parts and the weld seam 8 between trunk line changeover portion 15 and the main pump 12 between difference welding steam generator 11 bottom trunk line changeover portion elbows 17 and the trunk line changeover portion 15, accomplish the installation of a loop of pressurized-water reactor nuclear power plant reactor coolant loop major loop.
For the weld seam 4 between the weld seam 3 between cold section 14 of trunk line and the reactor pressure vessel 10 and cold section 14 of trunk line and the main pump 12, also can carry out the while welding under the situation that execution conditions are permitted and the workmen is enough at the scene.
Under the situation that execution conditions are permitted and the workmen is enough at the scene, the installation of other loops of pressurized-water reactor nuclear power plant reactor coolant loop major loop can be carried out according to above-mentioned steps simultaneously.
Combine accompanying drawing that embodiments of the invention have been done detailed description above, but the present invention is not limited to the foregoing description, in the ken that those of ordinary skills possessed, can also under the prerequisite that does not break away from aim of the present invention, makes various variations.
Claims (2)
1. the installation method of a pressurized-water reactor nuclear power plant reactor coolant loop main circuit circulates may further comprise the steps:
Step 1, main pipe hot leg (13), trunk line cold section (14) and trunk line changeover portion (15) are in place respectively; Said main pipe hot leg (13) is a straight tube, and trunk line changeover portion (15) is made up of two segment pipes;
Step 2, reactor pressure vessel (10), steam generator (11) and main pump (12) are in place respectively; Described steam generator (11) has been welded to connect main pipe hot leg elbow (16) and trunk line changeover portion elbow (17) respectively at its ozzle place, low head one loop;
Step 3, the respectively weld seam (3) between weld seam (4) between weld seam (2), trunk line between weld seam (9), main pipe hot leg (13) and the reactor pressure vessel (10) between welding main pipe hot leg (13) and steam generator (11) the bottom main pipe hot leg elbow (16) cold section (14) and the main pump (12) and trunk line cold section (14) and the reactor pressure vessel (10);
Step 4; Weld seam (6) between welding steam generator (11) bottom trunk line changeover portion elbow (17) and the trunk line changeover portion (15), the weld seam (7) at trunk line changeover portion (15) middle part and the weld seam (8) between trunk line changeover portion and the main pump are accomplished the installation of a loop of pressurized-water reactor nuclear power plant reactor coolant loop major loop respectively.
2. the installation method of pressurized-water reactor nuclear power plant reactor coolant loop main circuit circulates as claimed in claim 1 is characterized in that main pipe hot leg (13) and the welding simultaneously of the weld seam (2) between the weld seam (9) between steam generator (11) the bottom main pipe hot leg elbow (16) and main pipe hot leg (13) and the reactor pressure vessel (10) in the step 3.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010101663526A CN101839467B (en) | 2010-05-10 | 2010-05-10 | Method for mounting main pipeline and main loop of pressurized water reactor nuclear power station steam generator |
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| Application Number | Priority Date | Filing Date | Title |
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| CN2010101663526A CN101839467B (en) | 2010-05-10 | 2010-05-10 | Method for mounting main pipeline and main loop of pressurized water reactor nuclear power station steam generator |
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| Publication Number | Publication Date |
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| CN101839467A CN101839467A (en) | 2010-09-22 |
| CN101839467B true CN101839467B (en) | 2012-05-16 |
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| CN2010101663526A Active CN101839467B (en) | 2010-05-10 | 2010-05-10 | Method for mounting main pipeline and main loop of pressurized water reactor nuclear power station steam generator |
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Families Citing this family (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102169736B (en) * | 2011-01-19 | 2013-01-23 | 中国核工业第五建设有限公司 | Installing method for main pipeline of coolant system of nuclear power station |
| CN104464848B (en) * | 2012-01-06 | 2017-01-11 | 中国核工业二三建设有限公司 | Method for installing steam generator in nuclear island of nuclear power station |
| CN102592692B (en) * | 2012-01-06 | 2014-12-03 | 中国核工业二三建设有限公司 | Method for installing steam generator in nuclear island of nuclear power plant |
| CN102637463B (en) * | 2012-04-11 | 2016-02-24 | 中国核工业二三建设有限公司 | The method of main loop system in nuclear island of nuclear power plant is installed |
| CN104252884A (en) * | 2013-06-27 | 2014-12-31 | 中广核工程有限公司 | Installation method of primary loop main pipeline of nuclear power plant |
| CN104992738A (en) * | 2014-07-29 | 2015-10-21 | 台山核电合营有限公司 | Nuclear island main equipment installation process based on three-dimensional high-precision measurement |
| WO2017028201A1 (en) * | 2015-08-18 | 2017-02-23 | 中广核工程有限公司 | Nuclear reactor coolant system main circuit arrangement structure |
| CN105679382A (en) * | 2016-03-25 | 2016-06-15 | 上海核工程研究设计院 | Nuclear power station primary loop main equipment direct connecting manner |
| CN105957566A (en) * | 2016-07-05 | 2016-09-21 | 上海核工程研究设计院 | Reactor loop main equipment |
| CN106098118A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN106098119A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN106098117A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN106098114A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN106098120A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN106098116A (en) * | 2016-08-11 | 2016-11-09 | 上海核工程研究设计院 | A kind of passive PWR nuclear power plant reactor coolant loop is arranged |
| CN108597623B (en) * | 2018-06-22 | 2024-05-14 | 中核核电运行管理有限公司 | Stress corrosion cracking relieving main pipeline branch pipe joint connecting structure of heavy water reactor |
| CN111599496B (en) * | 2020-04-14 | 2022-11-18 | 中国核电工程有限公司 | Main pipeline and reactor coolant loop |
| CN112185594A (en) * | 2020-09-30 | 2021-01-05 | 中国核动力研究设计院 | Coolant loop arrangement structure suitable for advanced pressurized water reactor nuclear power station reactor |
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| US4769209A (en) * | 1986-01-10 | 1988-09-06 | Westinghouse Electric Corp. | Compact small pressurized water nuclear power plant |
| FR2614462B1 (en) * | 1987-04-27 | 1989-07-28 | Framatome Sa | METHOD FOR COMPLETELY REPLACING A STEAM GENERATOR OF A PRESSURE WATER NUCLEAR REACTOR |
| US4957693A (en) * | 1989-01-03 | 1990-09-18 | Westinghouse Electric Corp. | Pressurized water nuclear reactor system with hot leg vortex mitigator |
| JPH046497A (en) * | 1990-04-24 | 1992-01-10 | Toshiba Corp | Pressurized water reactor |
| JP2999053B2 (en) * | 1992-02-27 | 2000-01-17 | 三菱重工業株式会社 | Pressurized water reactor plant |
| US5790619A (en) * | 1997-01-15 | 1998-08-04 | Combustion Engineering, Inc. | Drain system for a nuclear power plant |
| CN101620892B (en) * | 2009-07-30 | 2012-02-08 | 华北电力大学 | Structural design of loop system of high-power pressurized water reactor nuclear power station |
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