CN103871505A - Automatic rapid cooling method for nuclear power plant steam discharge system - Google Patents
Automatic rapid cooling method for nuclear power plant steam discharge system Download PDFInfo
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- CN103871505A CN103871505A CN201210530187.7A CN201210530187A CN103871505A CN 103871505 A CN103871505 A CN 103871505A CN 201210530187 A CN201210530187 A CN 201210530187A CN 103871505 A CN103871505 A CN 103871505A
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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
Abstract
The invention belongs to a pressurized water reactor nuclear power plant accident treatment method, and specifically relates to an automatic rapid cooling method for a steam generator steam discharge system in a pressurized water reactor nuclear power plant. The automatic rapid cooling method comprises: 1, trigger a signal; 2, continuously monitoring; 3, carrying out analysis and judgment; 4, adjusting a steam discharge rate; and 5, rapidly cooling and stopping judgment. The automatic rapid cooling method has the following advantages that: the existing steam generator steam discharge system is improved to achieve automatic cooling and pressure reducing on RCS under the premise of assurance of no influence on the conventional protection function, such that the emergency reactor core cooling water can be rapidly injected into the reactor coolant system so as to increase the safety margin of the nuclear power plant under accident conditions.
Description
Technical field
The invention belongs to a kind of PWR nuclear power plant accident countermeasure, be specifically related to a kind of steam generator steam-dump system for PWR nuclear power plant automatic method for rapid cooling is provided.
Background technology
The one important moisturizing means of safety injection system after as accident, in the time there is the accident conditions that need to carry out moisturizing to a loop, (for example reactor coolant forfeiture accident (LOCA)) injects emergent reactor core chilled water to a loop.And in the situation that safety injection system is definite, its flow that is injected into the emergent reactor core chilled water in a loop is determined by the pressure in a loop.In the existing operation nuclear power station of China, the pressure in a loop mainly determines by the feature of each accident conditions self.For example, to LOCA accident, the pressure in a loop changes mainly because reactor coolant forfeiture causes.
By the automatic cooling function of steam generator steam-dump system is set, can realize the automatic cooling step-down to reactor coolant loop (RCS), make emergent reactor core chilled water piii reactor coolant system faster, improve the safety allowance of nuclear power station under accident conditions.
Summary of the invention
The object of this invention is to provide a kind of steam generator steam-dump system for PWR nuclear power plant automatic method for rapid cooling is provided, it can effective cooling RCS, and guarantee that system pressure can reduce smoothly, make emergent reactor core chilled water piii reactor coolant system faster, improve the safety allowance of nuclear power station under accident conditions.
The present invention is achieved in that the automatic method for rapid cooling of a kind of nuclear power plant steam exhaust system, and it comprises the steps,
The first step: trigger pip;
Second step: continue to monitor;
The 3rd step: analyze judgement;
The 4th step: discharge of steam rate adaptation;
The 5th step: quick cooling termination judgement.
The described first step is triggered by peace note signal for cooling fast.
Described second step is after signal triggers, and measuring system continues RCS temperature to monitor, and the temperature data monitoring is delivered to steering logic, by steering logic to the data analysis collecting, processing.
The 3rd described step is that steering logic is receiving after the temperature data of measuring system collection, can be converted to real-time RCS cooldown rate, now, steering logic is according to the comparison of this real-time cooldown rate and default cooldown rate, by logical operation, be converted to the valve opening setting valve of corresponding steam generator steam-dump system, and these data are passed to steam-dump system.
The 4th described step is that steam-dump system carries out corresponding adjusting according to the definite unlatching setting valve of steering logic module to the valve of steam-dump system, thereby obtains the discharge of steam speed of expection.
If the 5th described step be the valve opening setting valve of steam-dump system definite in the 3rd step definite lower the valve opening setting valve of steam-dump system maintains this lower limit in limited time lower than one, automatically coolingly fast automatically finish.
Advantage of the present invention is; it improves existing steam generator steam-dump system; guaranteeing under the impregnable prerequisite of its GPF (General Protection False function; can realize the automatic cooling step-down to RCS; thereby can make emergent reactor core chilled water piii reactor coolant system faster, thereby improve the safety allowance of nuclear power station under accident conditions.
Accompanying drawing explanation
Fig. 1 is the automatic method for rapid cooling process flow diagram of a kind of nuclear power plant steam exhaust system provided by the present invention.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail:
Ultimate principle of the present invention is as described below:
After accident occurs, nuclear power station protection system is sent the guard signal that requires safety injection according to power station virtual condition.This signal will trigger " steam generator steam-dump system is cooling fast to RCS's " RCS will be implemented to cooling step-down.Simultaneously, according to the RCS temperature variation monitoring, discharge of steam speed is regulated, by the cooldown rate control of RCS within the specific limits, the range of control of this cooldown rate is determined by following principle: guaranteeing that cooldown rate is no more than under the prerequisite that maximum heat that RCS system and equipment can bear impacts, and adopts the high cooldown rate of trying one's best to accelerate the step-down of RCS system.To avoid the too fast cooling thermal shock that RCS system and equipment are caused.Make emergent reactor core chilled water piii reactor coolant system faster, improve the safety allowance of nuclear power station under accident conditions.
Major Systems/the equipment of application is as follows:
Steam generator steam-dump system provides the related system/equipment relating in automatic quick cooling scheme to comprise: measuring system, steering logic, operator's interface.
Measuring system is mainly under accident conditions, the measurement that reactor core import and export medial temperature is continued, and measurement data is passed to steering logic.
Steering logic is " safety injection signal triggering steam generator steam-dump system is cooling fast to RCS's ".This logic control requires according to the drainage rate of the cooldown rate steam regulation exhaust system of RCS, thereby the cooldown rate of RCS is controlled within the scope of the cooldown rate of setting.
The normal defencive function of steam generator steam-dump system remains unchanged, to guarantee that under accidental conditions and transient condition, this system can be carried out conventional defencive function, avoids system pressure to transfinite.On this basis, set up discharge of steam speed automatic regulation function, in the time that steam generator steam-dump system is carried out automatic quick cooling function, discharge of steam speed is controlled.
Operator's interface is to provide the corresponding indication of operator and alerting signal; Demonstration and the reseting interface of " steam generator steam-dump system is cooling fast to RCS's " are provided; The interface of Operator actions " steam generator steam-dump system is cooling fast to RCS's " is provided.
The automatic method for rapid cooling of a kind of nuclear power plant steam exhaust system, it comprises the steps:
The first step: trigger pip
Fast coolingly triggered by peace note signal.Peace note signal belongs to the main protection system of nuclear power plant, has very high reliability, can guarantee effectively to trigger under accident conditions cooling fast.
Second step: continue to monitor
After signal triggers, measuring system continues RCS temperature to monitor, and the temperature data monitoring is delivered to steering logic, by steering logic to the data analysis collecting, processing.
The 3rd step: analyze judgement
Steering logic, receiving after the temperature data of measuring system collection, can be converted to real-time RCS cooldown rate.Now, steering logic is according to the comparison of this real-time cooldown rate and default cooldown rate, by logical operation, be converted to the valve opening setting valve of corresponding steam generator steam-dump system, and these data are passed to steam-dump system by certain time interval.
The 4th step: discharge of steam rate adaptation
Steam-dump system carries out corresponding adjusting according to the definite unlatching setting valve of steering logic module to the valve of steam-dump system, thereby obtains the discharge of steam speed of expection.
The 5th step: quick cooling termination judgement
If definite lower the valve opening setting valve of steam-dump system maintains this lower limit to the valve opening setting valve of definite steam-dump system in limited time lower than one in the 3rd step, automatically coolingly fast automatically finish.In addition, operator also can be automatically cooling fast by manually intervening termination.
Claims (6)
1. the automatic method for rapid cooling of nuclear power plant steam exhaust system, is characterized in that: it comprises the steps,
The first step: trigger pip;
Second step: continue to monitor;
The 3rd step: analyze judgement;
The 4th step: discharge of steam rate adaptation;
The 5th step: quick cooling termination judgement.
2. the automatic method for rapid cooling of a kind of nuclear power plant steam exhaust system as claimed in claim 1, is characterized in that: the described first step is triggered by peace note signal for cooling fast.
3. the automatic method for rapid cooling of a kind of nuclear power plant steam exhaust system as claimed in claim 1, it is characterized in that: described second step is after signal triggers, measuring system continues RCS temperature to monitor, and the temperature data monitoring is delivered to steering logic, by steering logic to the data analysis collecting, processing.
4. the automatic method for rapid cooling of a kind of nuclear power plant steam exhaust system as claimed in claim 1, it is characterized in that: the 3rd described step is that steering logic is receiving after the temperature data of measuring system collection, can be converted to real-time RCS cooldown rate, now, steering logic is according to the comparison of this real-time cooldown rate and default cooldown rate, by logical operation, be converted to the valve opening setting valve of corresponding steam generator steam-dump system, and these data are passed to steam-dump system.
5. the automatic method for rapid cooling of a kind of nuclear power plant steam exhaust system as claimed in claim 1, it is characterized in that: the 4th described step is that steam-dump system carries out corresponding adjusting according to the definite unlatching setting valve of steering logic module to the valve of steam-dump system, thereby obtain the discharge of steam speed of expecting.
6. the automatic method for rapid cooling of a kind of nuclear power plant steam exhaust system as claimed in claim 1, it is characterized in that: if the 5th described step be steam-dump system definite in the 3rd step valve opening setting valve lower than one definite lower in limited time, the valve opening setting valve of steam-dump system maintains this lower limit, automatically fast coolingly automatically finishes.
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| CN201210530187.7A CN103871505A (en) | 2012-12-11 | 2012-12-11 | Automatic rapid cooling method for nuclear power plant steam discharge system |
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| CN201210530187.7A CN103871505A (en) | 2012-12-11 | 2012-12-11 | Automatic rapid cooling method for nuclear power plant steam discharge system |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113421663A (en) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | Natural circulation cooling method suitable for pressurized water reactor nuclear power plant |
| CN113421662A (en) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | Natural circulation cooling method under failure of liquid level indication of pressure vessel of nuclear power plant |
| WO2023020635A1 (en) * | 2022-03-09 | 2023-02-23 | 深圳中广核工程设计有限公司 | Automatic low-pressure full-speed cooling method and system for nuclear power plant unit |
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| EP0405720A2 (en) * | 1989-06-26 | 1991-01-02 | Westinghouse Electric Corporation | Passive safety injection system using borated water |
| US5309487A (en) * | 1992-06-24 | 1994-05-03 | Westinghouse Electric Corp. | Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems |
| US5377242A (en) * | 1993-11-15 | 1994-12-27 | B&W Nuclear Service Company | Method and system for emergency core cooling |
| CN101847451A (en) * | 2009-06-19 | 2010-09-29 | 中广核工程有限公司 | Safety injection system |
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Patent Citations (4)
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| EP0405720A2 (en) * | 1989-06-26 | 1991-01-02 | Westinghouse Electric Corporation | Passive safety injection system using borated water |
| US5309487A (en) * | 1992-06-24 | 1994-05-03 | Westinghouse Electric Corp. | Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems |
| US5377242A (en) * | 1993-11-15 | 1994-12-27 | B&W Nuclear Service Company | Method and system for emergency core cooling |
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| 叶道权: "AP1000反应堆冷却剂系统(RCS)自动卸压设计分析", 《中国核科学技术进展报告（第二卷）——中国核学会2011年学术年会论文集第3册（核能动力分卷（下））》 * |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113421663A (en) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | Natural circulation cooling method suitable for pressurized water reactor nuclear power plant |
| CN113421662A (en) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | Natural circulation cooling method under failure of liquid level indication of pressure vessel of nuclear power plant |
| CN113421663B (en) * | 2021-06-18 | 2022-04-15 | 中国核动力研究设计院 | Natural circulation cooling method suitable for pressurized water reactor nuclear power plant |
| WO2023020635A1 (en) * | 2022-03-09 | 2023-02-23 | 深圳中广核工程设计有限公司 | Automatic low-pressure full-speed cooling method and system for nuclear power plant unit |
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