CN103778976A - Passive waste heat discharging system on secondary side of steam generator - Google Patents
Passive waste heat discharging system on secondary side of steam generator Download PDFInfo
- Publication number
- CN103778976A CN103778976A CN201210405882.0A CN201210405882A CN103778976A CN 103778976 A CN103778976 A CN 103778976A CN 201210405882 A CN201210405882 A CN 201210405882A CN 103778976 A CN103778976 A CN 103778976A
- Authority
- CN
- China
- Prior art keywords
- steam generator
- waste heat
- discharging system
- passive
- reactor
- 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.)
- Pending
Links
Images
Classifications
-
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention belongs to a special safety system for a nuclear power plant, specifically relates to a passive waste heat discharging system on a secondary side of a steam generator. The passive waste heat discharging system comprises a direct current steam generator, wherein a passive discharged waste heat exchanger is arranged between a main steam pipeline and a main water feeding pipe of the direct current steam generator, and inlet and outlet pipelines of the passive discharged waste heat exchanger are respectively provided with an inlet isolating valve and an outlet isolating valve, and the outlet isolating valve is frequently closed. The passive waste heat discharging system provided by the invention is arranged on the main steam pipeline and the main water feeding pipeline at the side of the steam generator and fully utilizes the characteristic of high heat exchange efficiency between steam and water phases, and the decay heat of a reactor core is derived under a working condition of power cut of the whole plant; thus, the safety of a reactor is guaranteed, requirements on arrangement space are lowered, pipelines directly connected with a reactor coolant system are reduced, the cracking probability of the pipelines is reduced, and security is improved.
Description
Technical field
The invention belongs to nuclear power plant's engineered safety system, be specifically related to be arranged at the Heat Discharging System of Chinese of steam generator secondary side.
Background technology
Decay heat derivation problem after reactor shutdown is the gordian technique that is related to npp safety, especially under the operating mode of losing at power supply, if can not derive reactor core decay heat, reactor temperature, pressure will sharply raise, thereby cause reactor pressure vessel to occur superpressure, even cause reactor core to melt, make radiomaterial lose second barrier, cause beyond design basis accident, although its probability of happening is very low, but to nuclear power plant, even the security implication of surrounding resident is very large, therefore, the derivation problem that related system solves reactor core decay heat under station blackout or other heat conduction approach forfeiture operating mode need be set.
The core decay heat export system that current existing nuclear power station adopts is active equipment, needs the driving of electric power.
Summary of the invention
The object of this invention is to provide a kind of Heat Discharging System of Chinese that is arranged at steam generator secondary side, to guarantee the safety of reactor in station blackout or other heat conduction approach forfeiture operating mode.
The present invention realizes like this, a kind of Heat Discharging System of Chinese that is arranged at steam generator secondary side, it comprises once through steam generator, between the main steam line of once through steam generator and main feed water pipe road, passive residual heat removal heat exchanger is set, import and export difference inlet porting isolation valve and outlet isolation valve on pipeline at passive residual heat removal heat exchanger, outlet isolation valve often closes.
Described passive residual heat removal heat exchanger is placed in pond.
Between the gateway pipeline of described passive residual heat removal heat exchanger, water supply tank is set.
Advantage of the present invention is not adopt the mode that Heat Discharging System of Chinese derivation residual heat of nuclear core is set in reactor coolant side.But pass through in steam generator side, by Heat Discharging System of Chinese being set on main steam and main feed water pipe road, make full use of the feature that steam-water twin phases heat exchange efficiency is high, under station blackout operating mode, derive reactor core decay heat, guarantee the safety of reactor, reduce the requirement to arrangement space, reduce the pipeline being directly connected with reactor coolant loop simultaneously, reduced the probability of pipe breakage, improved security.
Accompanying drawing explanation
Fig. 1 is a kind of Heat Discharging System of Chinese schematic diagram that is arranged at steam generator secondary side provided by the present invention.
In figure: 1 steam generator, 2 passive residual heat removal heat exchangers, 3 main steam lines, 4 main feed water pipe roads, 5 ponds, 6 water supply tanks, 7 entrance isolation valves, 8 outlet isolation valves.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail:
The present invention arranges Heat Discharging System of Chinese for derive reactor core decay heat under station blackout operating mode in steam generator secondary side, by passive residual heat removal heat exchanger being set on once through steam generator main steam line and main feed water pipe road, on the pipeline of Heat Discharging System of Chinese gateway, water supply tank is set, provide driving force and balanced system pressure for system initial start, utilize the heat exchange of vapour-water two-phase, reactor decay heat is passed to hot trap-pond, thereby by reactor temperature, be controlled within the scope of acceptable, guarantee the long-term safety of reactor.The in the situation that of station blackout or the forfeiture of other heat conduction approach, derive for a long time reactor core decay heat, guarantee the safety of reactor.
Embodiment 1:
A kind of Heat Discharging System of Chinese that is arranged at steam generator secondary side as shown in Figure 1, it comprises once through steam generator 1, by passive residual heat removal heat exchanger 2 being set on the main steam line 3 at once through steam generator 1 and main feed water pipe road 4, passive residual heat removal heat exchanger 2 is placed in pond 5, on the pipeline of the gateway of passive residual heat removal heat exchanger 2, water supply tank 6 is set, water supply tank 6 provides driving force and balanced system pressure for system initial start, import and export difference inlet porting isolation valve 7 and outlet isolation valve 8 on pipeline at passive residual heat removal heat exchanger 2, outlet isolation valve 8 often closes.
In the time of normal reactor operation, outlet isolation valve 8 often closes, make system in stand-by state, there is station blackout, or in the situation of other heat conduction approach forfeitures, outlet isolation valve 8 is opened automatically, under water supply tank inner cold water drives, in system, water enters steam generator, evaporated at the interior water of steam generator 1, steam enters passive residual heat removal heat exchanger 2 by pipeline and utilizes the heat exchange of vapour-water two-phase, and reactor decay heat is passed to hot trap-pond 5, thereby by reactor temperature, be controlled within the scope of acceptable, guarantee the long-term safety of reactor.The in the situation that of station blackout or the forfeiture of other heat conduction approach, derive for a long time reactor core decay heat, guarantee the safety of reactor.
Claims (3)
1. one kind is arranged at the Heat Discharging System of Chinese of steam generator secondary side, it is characterized in that: it comprises once through steam generator (1), between the main steam line (3) of once through steam generator (1) and main feed water pipe road (4), passive residual heat removal heat exchanger (2) is set, import and export difference inlet porting isolation valve (7) and outlet isolation valve (8) on pipeline at passive residual heat removal heat exchanger (2), outlet isolation valve (8) often closes.
2. a kind of Heat Discharging System of Chinese that is arranged at steam generator secondary side as claimed in claim 1, is characterized in that: described passive residual heat removal heat exchanger (2) is placed in pond (5).
3. a kind of Heat Discharging System of Chinese that is arranged at steam generator secondary side as claimed in claim 1, is characterized in that: between the gateway pipeline of described passive residual heat removal heat exchanger (2), water supply tank (6) is set.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210405882.0A CN103778976A (en) | 2012-10-22 | 2012-10-22 | Passive waste heat discharging system on secondary side of steam generator |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210405882.0A CN103778976A (en) | 2012-10-22 | 2012-10-22 | Passive waste heat discharging system on secondary side of steam generator |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN103778976A true CN103778976A (en) | 2014-05-07 |
Family
ID=50571128
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201210405882.0A Pending CN103778976A (en) | 2012-10-22 | 2012-10-22 | Passive waste heat discharging system on secondary side of steam generator |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103778976A (en) |
Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104361913A (en) * | 2014-11-19 | 2015-02-18 | 中科华核电技术研究院有限公司 | Secondary side passive waste heat removal system |
| CN105070327A (en) * | 2015-08-31 | 2015-11-18 | 上海核工程研究设计院 | Nuclear power station secondary side long-term waste heat removal system |
| CN105957567A (en) * | 2016-05-06 | 2016-09-21 | 中国核动力研究设计院 | Steam generator secondary side passive residual heat removal system |
| CN106887263A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | The secondary laterally opened Heat Discharging System of Chinese of once through steam generator |
| CN107833642A (en) * | 2017-10-10 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | Heat exchanger is located at the outer marine PWR Passive residual heat removal system of water tank |
| CN108010593A (en) * | 2017-12-29 | 2018-05-08 | 安徽中科超安科技有限公司 | A kind of nuclear power treasured and its passive residual heat removal system |
| CN110021447A (en) * | 2018-01-10 | 2019-07-16 | 中广核（北京）仿真技术有限公司 | A kind of secondary side passive residual heat deriving system |
| CN110265158A (en) * | 2019-06-24 | 2019-09-20 | 上海核工程研究设计院有限公司 | A kind of more power scale integral reactors and its application method |
| CN111247602A (en) * | 2018-09-28 | 2020-06-05 | 原子能技术科学研究设计院股份公司 | Method and system for transferring a nuclear power plant emergency to a safe state |
| CN111430050A (en) * | 2020-04-24 | 2020-07-17 | 上海核工程研究设计院有限公司 | Reactor secondary side passive waste heat removal system and use method |
| CN111540486A (en) * | 2020-04-16 | 2020-08-14 | 中国核动力研究设计院 | Small pressurized water reactor and long-term passive heat discharge system of containment |
| CN112530611A (en) * | 2020-12-24 | 2021-03-19 | 上海核工程研究设计院有限公司 | Advanced and simplified small-pile passive special safety system |
| CN113053548A (en) * | 2021-03-17 | 2021-06-29 | 西安热工研究院有限公司 | High-temperature gas cooled reactor with natural circulation reactor core waste heat derivation function |
| CN114082247A (en) * | 2021-11-05 | 2022-02-25 | 中广核研究院有限公司 | Steam-water separator and waste heat deriving system |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006138744A (en) * | 2004-11-12 | 2006-06-01 | Mitsubishi Heavy Ind Ltd | Reactor cooling device |
| CN102169733A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
| CN202948736U (en) * | 2012-10-22 | 2013-05-22 | 中国核动力研究设计院 | Passive waste heat discharging system on secondary side of steam generator |
-
2012
- 2012-10-22 CN CN201210405882.0A patent/CN103778976A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006138744A (en) * | 2004-11-12 | 2006-06-01 | Mitsubishi Heavy Ind Ltd | Reactor cooling device |
| CN102169733A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Passive and active combined special safety system for nuclear power plant |
| CN202948736U (en) * | 2012-10-22 | 2013-05-22 | 中国核动力研究设计院 | Passive waste heat discharging system on secondary side of steam generator |
Non-Patent Citations (2)
| Title |
|---|
| 王明军等: "主给水管道破口尺寸对CPR1000二次侧非能动应急热阱事故缓解能力影响研究", 《原子能科学技术》 * |
| 陈薇 等: "二次侧非能动余热排出系统设计及验证分析", 《中国核电》 * |
Cited By (21)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104361913A (en) * | 2014-11-19 | 2015-02-18 | 中科华核电技术研究院有限公司 | Secondary side passive waste heat removal system |
| CN105070327A (en) * | 2015-08-31 | 2015-11-18 | 上海核工程研究设计院 | Nuclear power station secondary side long-term waste heat removal system |
| CN106887263A (en) * | 2015-12-15 | 2017-06-23 | 中国核动力研究设计院 | The secondary laterally opened Heat Discharging System of Chinese of once through steam generator |
| CN105957567A (en) * | 2016-05-06 | 2016-09-21 | 中国核动力研究设计院 | Steam generator secondary side passive residual heat removal system |
| CN105957567B (en) * | 2016-05-06 | 2018-03-06 | 中国核动力研究设计院 | A kind of steam generator secondary side Heat Discharging System of Chinese |
| CN107833642A (en) * | 2017-10-10 | 2018-03-23 | 中国船舶重工集团公司第七〇九研究所 | Heat exchanger is located at the outer marine PWR Passive residual heat removal system of water tank |
| CN108010593A (en) * | 2017-12-29 | 2018-05-08 | 安徽中科超安科技有限公司 | A kind of nuclear power treasured and its passive residual heat removal system |
| CN110021447A (en) * | 2018-01-10 | 2019-07-16 | 中广核（北京）仿真技术有限公司 | A kind of secondary side passive residual heat deriving system |
| CN110021447B (en) * | 2018-01-10 | 2021-06-11 | 中广核（北京）仿真技术有限公司 | Secondary side passive waste heat deriving system |
| CN111247602A (en) * | 2018-09-28 | 2020-06-05 | 原子能技术科学研究设计院股份公司 | Method and system for transferring a nuclear power plant emergency to a safe state |
| CN111247602B (en) * | 2018-09-28 | 2023-11-03 | 原子能技术科学研究设计院股份公司 | Method and system for switching to a safe state after an emergency situation in a nuclear power plant |
| CN110265158A (en) * | 2019-06-24 | 2019-09-20 | 上海核工程研究设计院有限公司 | A kind of more power scale integral reactors and its application method |
| CN111540486A (en) * | 2020-04-16 | 2020-08-14 | 中国核动力研究设计院 | Small pressurized water reactor and long-term passive heat discharge system of containment |
| CN111430050A (en) * | 2020-04-24 | 2020-07-17 | 上海核工程研究设计院有限公司 | Reactor secondary side passive waste heat removal system and use method |
| CN111430050B (en) * | 2020-04-24 | 2024-06-18 | 上海核工程研究设计院股份有限公司 | Passive residual heat removal system for secondary side of reactor and use method |
| WO2022135245A1 (en) * | 2020-12-24 | 2022-06-30 | 上海核工程研究设计院有限公司 | Passive safety system for reactor |
| CN112530611A (en) * | 2020-12-24 | 2021-03-19 | 上海核工程研究设计院有限公司 | Advanced and simplified small-pile passive special safety system |
| CN113053548A (en) * | 2021-03-17 | 2021-06-29 | 西安热工研究院有限公司 | High-temperature gas cooled reactor with natural circulation reactor core waste heat derivation function |
| CN114082247A (en) * | 2021-11-05 | 2022-02-25 | 中广核研究院有限公司 | Steam-water separator and waste heat deriving system |
| CN114082247B (en) * | 2021-11-05 | 2023-02-03 | 中广核研究院有限公司 | Steam-water separator and waste heat deriving system |
| WO2023077674A1 (en) * | 2021-11-05 | 2023-05-11 | 中广核研究院有限公司 | Steam-water separator and waste heat removal system |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103778976A (en) | Passive waste heat discharging system on secondary side of steam generator | |
| CN103903659B (en) | Floating nuclear power plant Heat Discharging System of Chinese | |
| CN202948738U (en) | Kinetic and non-kinetic combined waste heat discharging system | |
| CN103377728B (en) | A kind of Flooded-type containment complete passive after-heat removal system | |
| KR101447514B1 (en) | Safety System of Ocean System-integrated Modular Advanced Reactor | |
| CN202102728U (en) | Safety system used for guaranteeing safety of nuclear power plant | |
| CN201698776U (en) | Continuous-operation safety injection and spray system for nuclear power station | |
| CN201788707U (en) | Safety system for ensuring safety of nuclear power station | |
| CN201741419U (en) | Main water supply flow control system of nuclear power plant | |
| CN104361913A (en) | Secondary side passive waste heat removal system | |
| CN103871509A (en) | Pressurized water reactor nuclear power plant reactor coolant system | |
| CN203276869U (en) | Steam generator sewage drainage system preventing overflow of steam generator | |
| CN204010702U (en) | A kind of steam generator emergency feedwater supply system | |
| CN103778974A (en) | Kinetic and non-kinetic combined waste heat discharging system | |
| KR101463441B1 (en) | High concentration boron injection system and safety injection system having the same | |
| CN104103325A (en) | Heat derivation system for long-term passive containment | |
| CN109273112A (en) | A kind of direct cooling passive residual heat removal system of anti-gravity direction flowing | |
| CN202770265U (en) | Natural circulation heat exchanger for supercritical water reactor waste heat removing | |
| CN102820067A (en) | Natural circulation heat exchanger for discharging waste heat of supercritical water reactor | |
| CN202948736U (en) | Passive waste heat discharging system on secondary side of steam generator | |
| CN103390435B (en) | The exhaust apparatus of nuclear power plant reactor coolant system pressure vessel and method | |
| CN104078086A (en) | Active and passive combined containment sump water cooling system | |
| CN104134474A (en) | Passive cooling system | |
| CN202948737U (en) | Passive residual heat removal system directly connected with main loop | |
| CN203338775U (en) | Nuclear power plant steam generator overflow prevention structure |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20140507 |
|
| RJ01 | Rejection of invention patent application after publication |