CN103778978A - Integrated reactor main pump overhaul water draining and waste heat discharging method - Google Patents
Integrated reactor main pump overhaul water draining and waste heat discharging method Download PDFInfo
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- CN103778978A CN103778978A CN201210410523.4A CN201210410523A CN103778978A CN 103778978 A CN103778978 A CN 103778978A CN 201210410523 A CN201210410523 A CN 201210410523A CN 103778978 A CN103778978 A CN 103778978A
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- main pump
- waste heat
- pressure vessel
- pressure inlet
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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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- Structures Of Non-Positive Displacement Pumps (AREA)
Abstract
The invention relates to a nuclear reactor main pump overhaul technology, and concretely discloses an integrated reactor main pump overhaul water draining and waste heat discharging method. An opening hole is processed in a pressing cylinder inside a pressure vessel, and the horizontal position of the opening hole is lower than a horizontal position of a main pump pipe connecting flange. An installing hole is processed in the pressure vessel and to be opposite to the opening hole in the pressing cylinder. A normal waste heat discharging system is connected with the pressure vessel. A waste heat discharging inlet nozzle is arranged in the installing hole and a waste heat discharging outlet nozzle is arranged on the pressure vessel. The waste heat discharging outlet nozzle is under the waste heat discharging inlet nozzle. Through the method, the water level of the pressure vessel of the reactor is lowered to the position where the main pump can be dismounted. Effective discharging of the waste heat of the reactor during overhaul of the main pump can be guaranteed, and the problems of waste heat discharging and water draining of a pressure vessel of a reactor during overhaul of an integrated reactor main pump are solved.
Description
Technical field
The invention belongs to nuclear reactor main pump service technique field, be specifically related to main pump drainage for overhaul and waste heat discharge method.
Background technology
Between integrated reacting stack device main pump turn(a)round, reactor pressure vessel draining and residual heat of nuclear core need timely and effective derivation.
The compressed water reactor nuclear power that distributing is arranged stands in during maintenance cold shut generally by normal residual heat removal system and boron recovery system reactor pressure vessel draining, and derive residual heat of nuclear core by normal residual heat removal system, and integral reactor is because once through steam generator is arranged in reactor pressure vessel, main pump is directly connected and has cancelled main pipeline with reactor pressure vessel main pump pipe connecting flange, reactor pressure vessel cannot be directly by coupled pipe drainage to main pump pipe connecting flange, below pressure vessel water level is down to main pump pipe connecting flange time because normal residual heat removal system intake and water return outlet are isolated cause effectively deriving residual heat of nuclear core completely.
Summary of the invention
The object of the present invention is to provide a kind of integral reactor main pump drainage for overhaul and waste heat discharge method that is directed to integral reactor, it can be by normal residual heat removal system to reactor pressure vessel draining and take away residual heat of nuclear core.
Realize technical scheme of the present invention as follows:
A kind of integral reactor main pump drainage for overhaul and waste heat discharge method, it comprises the steps:
1) on the clamping cylinder of pressure vessel inside, process perforate, the horizontal level of perforate is lower than the horizontal level of main pump pipe connecting flange;
2) on pressure vessel corresponding to the position processing mounting holes of perforate on clamping cylinder;
3) normal residual heat removal system is connected in pressure vessel, will more than enter a mouthful pressure inlet and be arranged in above-mentioned mounting hole, remaining escape hole pressure inlet is arranged on pressure vessel, remaining escape hole pressure inlet is positioned at more than above-mentioned and enters a mouthful pressure inlet below;
4) be arranged on the export pipeline of normal remaining heat-extraction system changing appearance system.
In above-mentioned integral reactor main pump drainage for overhaul and waste heat discharge method: enter mouthful pressure inlet and remaining escape hole pressure inlet more than described normal remaining heat-extraction system comprises, also be included in and remaining the first isolation valve arranging on the pipeline that mouthful pressure inlet is connected that enters, with the second isolation valve arranging on pipeline being connected with remaining escape hole pressure inlet, between the first isolation valve and the second isolation valve, be parallel with the pipeline that two-way residual heat removal exchanger and residual heat removal pump form.
The obtained beneficial effect of the present invention is as follows: this method is by making variation to the structure of the tight cylinder of vessel internal pressure, carry out perforate at it corresponding to the position that enters mouthful pressure inlet more than normal, and the position of perforate is lower than the position of main pump pipe connecting flange, therefore can guarantee that the water level of reactor pressure vessel drains into the dismountable position of main pump.Simultaneously due to clamping cylinder perforate, reactor coolant can be flowed inside and outside clamping cylinder, so just can guarantee effectively taking out of of between main pump turn(a)round reactor waste, solve that waste heat between integral reactor main pump turn(a)round is derived and the problem of reactor pressure vessel draining.
Accompanying drawing explanation
The integrated main reactor pump drainage for overhaul of Fig. 1 and waste heat are discharged schematic diagram;
In figure: 1. reactor pressure vessel; 2. main pump; 3. clamping cylinder; 4. clamping cylinder perforate; 5. residual heat removal pump; 6. residual heat removal exchanger; 7. the first isolation valve; 8. the second isolation valve; 9. more than, enter a mouthful pressure inlet; 10. escape hole pressure inlet more than; 11. main pumps are taken over; 12. pipe connecting flanges; 13. sealing ring cavities; 14. change appearance system.
Embodiment
Below in conjunction with the drawings and specific embodiments, the present invention is described in detail.
As shown in Figure 1, the main pump of pressure vessel 1 one sides of integral reactor is taken over 11 mouths of pipe upward, takes on 11 pipe connecting flange 12 is installed at main pump, and main pump 2 is fixedly connected with pipe connecting flange 12.More than being provided with, pressure vessel 1 opposite side enters mouthful pressure inlet 9 and remaining escape hole pressure inlet 10, clamping cylinder 3 is arranged in pressure vessel 1 center, the outer wall of clamping cylinder 3 and pressure vessel 1 inwall flow out certain intervals, thereby form sealing ring cavity 13, once through steam generator is arranged in sealing ring cavity 13, the existence of sealing ring cavity 13 makes reactor pressure vessel cannot directly utilize it to take over draining, thereby cannot form Efficient Cycle derivation residual heat of nuclear core 12 below time when water level in reactor pressure vessel is positioned at main pump pipe connecting flange.
The present invention is processed with perforate 4 in order to address the above problem on the clamping cylinder 3 in pressure vessel 1 first on the position corresponding to this stub (tube) 9, pore size with more than to enter mouthful pressure inlet 9 pipe diameter sizes identical.The position of perforate 4 simultaneously sets low than the horizontal position of main pump pipe connecting flange 12.
Then normal residual heat removal system is connected in pressure vessel 1, as shown in Figure 1, normal residual heat removal system comprises more than above-mentioned and enters mouthful pressure inlet 9 and remaining escape hole pressure inlet 10, also be included in and remaining the first isolation valve 7 arranging on the pipeline that mouthful pressure inlet 9 is connected that enters, the second isolation valve 8 with arranging on pipeline being connected with remaining escape hole pressure inlet 10 is parallel with the pipeline that two-way residual heat removal exchanger 6 and residual heat removal pump 5 form between the first isolation valve 7 and the second isolation valve 8.
Like this in the time that main pump need overhaul, after shutdown, reactor coolant temperature is down to after cold shut temperature, utilize residual heat removal pump 5, residual heat removal exchanger 6 maintains the circulation of reactor coolant and cooling, and continue draining by normal residual heat removal system and the interface of changing appearance system 14, because the position of perforate 4 on clamping cylinder 3 is lower than the position of main pump pipe connecting flange 12, the water level that therefore can guarantee reactor pressure vessel 1 drains into the dismountable position of main pump, simultaneously due to clamping cylinder perforate 4, reactor coolant can mutually be flowed inside and outside clamping cylinder 3, so just can guarantee effectively taking out of of between main pump turn(a)round reactor waste.
Obviously, those skilled in the art can carry out various changes and modification and not depart from the spirit and scope of the present invention the present invention.If these are revised and within modification belongs to the scope of the claims in the present invention and equivalent technologies thereof, the present invention is also intended to comprise these changes and modification interior.
Claims (2)
1. integral reactor main pump drainage for overhaul and a waste heat discharge method, is characterized in that, it comprises step:
1) in inner clamping cylinder (3) the upper processing perforate (4) of pressure vessel (1), the horizontal level of perforate (4) is lower than the horizontal level of main pump pipe connecting flange (12);
2) at the upper position processing mounting holes corresponding to the upper perforate (4) of clamping cylinder (3) of pressure vessel (1);
3) normal residual heat removal system is connected in pressure vessel (1), more than inciting somebody to action, entering a mouthful pressure inlet (9) is arranged in above-mentioned mounting hole, it is upper that remaining escape hole pressure inlet (10) is arranged on pressure vessel (1), and remaining escape hole pressure inlet (10) is positioned at more than above-mentioned and enters a mouthful pressure inlet (9) below;
4) will change on the export pipeline that appearance system (14) is arranged on normal remaining heat-extraction system.
2. integral reactor main pump drainage for overhaul as claimed in claim 1 and waste heat discharge method, it is characterized in that: more than described normal remaining heat-extraction system comprises, enter a mouthful pressure inlet (9) and remaining escape hole pressure inlet (10), also be included in and remaining the first isolation valve (7) arranging on the pipeline that a mouthful pressure inlet (9) is connected that enters, with the second isolation valve (8) arranging on pipeline being connected with remaining escape hole pressure inlet (10), between the first isolation valve (7) and the second isolation valve (8), be parallel with the pipeline that two-way residual heat removal exchanger (6) and residual heat removal pump (5) form.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210410523.4A CN103778978B (en) | 2012-10-25 | 2012-10-25 | Integral reactor main pump drainage for overhaul and Residual heat removal method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210410523.4A CN103778978B (en) | 2012-10-25 | 2012-10-25 | Integral reactor main pump drainage for overhaul and Residual heat removal method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103778978A true CN103778978A (en) | 2014-05-07 |
| CN103778978B CN103778978B (en) | 2016-08-10 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201210410523.4A Active CN103778978B (en) | 2012-10-25 | 2012-10-25 | Integral reactor main pump drainage for overhaul and Residual heat removal method |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110448844A (en) * | 2019-07-12 | 2019-11-15 | 岭澳核电有限公司 | The synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station |
| CN113299418A (en) * | 2021-05-25 | 2021-08-24 | 中国核动力研究设计院 | Safety injection triggering method, device and system for nuclear power plant under shutdown working condition after shutdown of main pump |
Citations (8)
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| US4039377A (en) * | 1974-03-20 | 1977-08-02 | Commissariat A L'energie Atomique | Nuclear boiler |
| US4072563A (en) * | 1976-06-24 | 1978-02-07 | The Babcock & Wilcox Company | Industrial technique for an integral compact reactor |
| CN85101411A (en) * | 1985-04-01 | 1987-01-17 | 西屋电器公司 | Small integral pressurized water nuclear reactor |
| US20090010374A1 (en) * | 1999-12-28 | 2009-01-08 | Kabushiki Kaisha Toshiba | Reactivity control rod for core, core of nuclear reactor, nuclear reactor and nuclear power plant |
| US20100316181A1 (en) * | 2009-06-10 | 2010-12-16 | Thome Ted L | Integral helical coil pressurized water nuclear reactor |
| CN102034559A (en) * | 2010-09-19 | 2011-04-27 | 中广核工程有限公司 | Rapid mutual-backup system of nuclear power station and mutual-backup method thereof |
| US20120155596A1 (en) * | 2010-12-20 | 2012-06-21 | Westinghouse Electric Company Llc | Nuclear control rod position indication system |
| CN102737734A (en) * | 2011-04-13 | 2012-10-17 | 巴布科克和威尔科克斯核能股份有限公司 | Compact integral pressurized water nuclear reactor |
-
2012
- 2012-10-25 CN CN201210410523.4A patent/CN103778978B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4039377A (en) * | 1974-03-20 | 1977-08-02 | Commissariat A L'energie Atomique | Nuclear boiler |
| US4072563A (en) * | 1976-06-24 | 1978-02-07 | The Babcock & Wilcox Company | Industrial technique for an integral compact reactor |
| CN85101411A (en) * | 1985-04-01 | 1987-01-17 | 西屋电器公司 | Small integral pressurized water nuclear reactor |
| US20090010374A1 (en) * | 1999-12-28 | 2009-01-08 | Kabushiki Kaisha Toshiba | Reactivity control rod for core, core of nuclear reactor, nuclear reactor and nuclear power plant |
| US20100316181A1 (en) * | 2009-06-10 | 2010-12-16 | Thome Ted L | Integral helical coil pressurized water nuclear reactor |
| CN102034559A (en) * | 2010-09-19 | 2011-04-27 | 中广核工程有限公司 | Rapid mutual-backup system of nuclear power station and mutual-backup method thereof |
| US20120155596A1 (en) * | 2010-12-20 | 2012-06-21 | Westinghouse Electric Company Llc | Nuclear control rod position indication system |
| CN102737734A (en) * | 2011-04-13 | 2012-10-17 | 巴布科克和威尔科克斯核能股份有限公司 | Compact integral pressurized water nuclear reactor |
Non-Patent Citations (1)
| Title |
|---|
| 卢放: "核电厂半环工况下热功水力及事件树分析", 《中国优秀硕士论文学位论文全文数据库工程科技II辑》 * |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110448844A (en) * | 2019-07-12 | 2019-11-15 | 岭澳核电有限公司 | The synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station |
| CN113299418A (en) * | 2021-05-25 | 2021-08-24 | 中国核动力研究设计院 | Safety injection triggering method, device and system for nuclear power plant under shutdown working condition after shutdown of main pump |
| CN113299418B (en) * | 2021-05-25 | 2022-03-01 | 中国核动力研究设计院 | Safety injection triggering method, device and system for nuclear power plant under shutdown working condition after shutdown of main pump |
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| Publication number | Publication date |
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| CN103778978B (en) | 2016-08-10 |
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