CN104332207B - Method for automatically stopping coolant pump under reactor coolant loss accident condition - Google Patents
Method for automatically stopping coolant pump under reactor coolant loss accident condition Download PDFInfo
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- CN104332207B CN104332207B CN201310307099.5A CN201310307099A CN104332207B CN 104332207 B CN104332207 B CN 104332207B CN 201310307099 A CN201310307099 A CN 201310307099A CN 104332207 B CN104332207 B CN 104332207B
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- reactor coolant
- coolant pump
- reactor
- low
- pump inlet
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to a coping method for pressurized water reactor nuclear power station accidents and especially relates to a method for automatically stopping a coolant pump under the reactor coolant loss accident condition. The method comprises the following steps: the step 1) triggering a safe injection signal and a reactor coolant pump inlet and outlet pressure difference low logic; and the step 2) when the safe injection signal coexists with the condition of reactor coolant pump inlet and outlet low pressure difference, triggering the reactor coolant pump to stop operation. The method has the advantages that the method can realize automatic shutdown of the reactor coolant pump before reactor core deterioration under the LOCA condition, and the time when operators do not need to intervene the accident is prolonged greatly.
Description
Technical field
The invention belongs to a kind of pressurized-water reactor nuclear power plant accident countermeasure is and in particular to thing lost by a kind of reactor coolant
Therefore automatic stoppage in transit cooling medium pump method under operating mode.
Background technology
The accident analysiss result of existing nuclear power station shows, when reacting reactor coolant forfeiture accident (loca), one time
Road reactor coolant is quickly run off by cut, and primary Ioops pressure and water loading amount reduce, and are triggered by manostat pressure low signal
Reactor emergency shut-down, manostat pressure low low signal triggering peace note puts into.With the continuous loss of primary Ioops water loading amount, react
Heap reactor core is gradually exposed, needs to stop transport reactor coolant pump as early as possible to prevent reactor core worsening condition from causing fuel can temperature mistake
High and be damaged.
Domestic active service nuclear power station is not provided with the automatic stoppage in transit reactor coolant pump signal for loca operating mode, thus
Need operator judge there occurs loca after as early as possible manually stoppage in transit reactor coolant pump with prevent reactor core deteriorate.Due to from
Loca occurs the time interval to reactor coolant pump of must stopping transport shorter, and the therefore requirement to operator is just higher, holds
Easily there is maloperation.
By arranging reasonably stoppage in transit reactor coolant pump signal automatically, in the situation that other accidents are not produced with impact
Under, reactor coolant pump of automatically stopping transport in loca operating mode, the time that operator can not intervene this accident can be greatly prolonged,
Reduce the error of operator.
Content of the invention
It is an object of the invention to provide automatic stoppage in transit cooling medium pump method under accident conditions lost by a kind of reactor coolant,
It can before reactor core deteriorates automatic stoppage in transit reactor coolant pump, thus avoiding reactor core to occur deteriorating, extending operator can
Do not intervene the time of this accident, reduce the error of operator.
The present invention is achieved in that automatic stoppage in transit cooling medium pump side under accident conditions lost by a kind of reactor coolant
Method, it comprises the steps,
The first step: the triggering of peace note signal and reactor coolant pump inlet outlet pressure differential low logic
After loca occurs, reactor coolant loop rapid pressure drop, when pressure drop is low whole to manostat pressure
Trigger reactor peace note signal, on the other hand persistently spurting due to cut during definite value, lead to reactor coolant pump pressure reduction to drop
Low, automatically touch when reactor coolant pump inlet outlet pressure differential is reduced to " reactor coolant pump inlet outlet pressure differential is low " setting valve
Send out reactor coolant pump pressure reduction low logic；
Second step: peace note signal meet triggering reactor coolant pump low with reactor coolant pump inlet outlet pressure differential is stopped transport
Once peace note signal is low with reactor coolant pump inlet outlet pressure differential exist simultaneously, then trigger automatic stoppage in transit reactor
Cooling medium pump.
It is an advantage of the invention that it can achieve under loca operating mode before reactor core deterioration automatically stoppage in transit reactor coolant
Pump, substantially prolongs the time that operator can not intervene this accident.
Brief description
Fig. 1 is that automatic stoppage in transit cooling medium pump method flow diagram under accident conditions lost by a kind of reactor coolant.
Specific embodiment
With reference to the accompanying drawings and examples the present invention is described in detail:
When PWR nuclear power plant (station) occurs loca, by setting, " safety injection signal and reactor coolant pump enter
Pressure reduction is low meets for outlet " signal triggers automatic stoppage in transit reactor coolant pump.This signal will before reactor core deteriorates automatically
Stoppage in transit reactor coolant pump, afterwards with the reduction of cut flow, peace beam amount can gradually compensate and exceed cut flow, heap
Core water level gradually gos up, and finally floods reactor core completely, and operator brings reactor into corresponding process according to accident treatment code
State.
The relevant device being related in the scheme of automatic stoppage in transit reactor coolant pump under loca operating mode include control logic and
Operator's interface.
Newly-increased realize automatic stoppage in transit reactor coolant pump under loca operating mode control logic be " safety injection signal with instead
Answer that reactor coolant pump inlet outlet pressure differential is low to be met " signal.
Operator's interface is to provide operator " safety injection signal meets " with reactor coolant pump inlet outlet pressure differential is low
The instruction of signal and reseting interface.
Automatic stoppage in transit cooling medium pump method under accident conditions lost by a kind of reactor coolant, and carrying out practically flow process is as follows:
The first step: the triggering of peace note signal and reactor coolant pump inlet outlet pressure differential low logic
After loca occurs, reactor coolant loop rapid pressure drop, when pressure drop is low whole to manostat pressure
Reactor peace note signal is triggered during definite value.
On the other hand persistently spurting due to cut, leads to reactor coolant pump pressure reduction to reduce, works as reactor coolant
Pump inlet outlet pressure differential triggers reactor coolant pump when being reduced to " reactor coolant pump inlet outlet pressure differential is low " setting valve automatically
Pressure reduction low logic.
Second step: peace note signal meet triggering reactor coolant pump low with reactor coolant pump inlet outlet pressure differential is stopped transport
Once peace note signal is low with reactor coolant pump inlet outlet pressure differential exist simultaneously, then trigger automatic stoppage in transit reactor
Cooling medium pump.
After operator, corresponding process state into is brought reactor according to corresponding accident treatment code.
Claims (1)
1. a kind of reactor coolant lose under accident conditions automatically stoppage in transit cooling medium pump method it is characterised in that: it include as
Lower step,
The first step: the triggering of peace note signal and reactor coolant pump inlet outlet pressure differential low logic
After loca occurs, reactor coolant loop rapid pressure drop, when pressure drop is to the low setting valve of manostat pressure
When trigger reactor peace note signal, on the other hand persistently spurting due to cut, lead to reactor coolant pump pressure reduction reduce, when
Reactor coolant pump inlet outlet pressure differential is reduced to and automatically triggers anti-during " reactor coolant pump inlet outlet pressure differential is low " setting valve
Answer reactor coolant pump pressure difference low logic；
Second step: peace note signal meet triggering reactor coolant pump low with reactor coolant pump inlet outlet pressure differential is stopped transport
Once peace note signal is low with reactor coolant pump inlet outlet pressure differential exist simultaneously, then trigger automatic stoppage in transit reactor cooling
Agent pump.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310307099.5A CN104332207B (en) | 2013-07-22 | 2013-07-22 | Method for automatically stopping coolant pump under reactor coolant loss accident condition |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310307099.5A CN104332207B (en) | 2013-07-22 | 2013-07-22 | Method for automatically stopping coolant pump under reactor coolant loss accident condition |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104332207A CN104332207A (en) | 2015-02-04 |
| CN104332207B true CN104332207B (en) | 2017-01-18 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201310307099.5A Active CN104332207B (en) | 2013-07-22 | 2013-07-22 | Method for automatically stopping coolant pump under reactor coolant loss accident condition |
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Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108665990A (en) * | 2018-04-26 | 2018-10-16 | 中国核动力研究设计院 | A kind of device and method of reliable stoppage in transit reactor coolant pump |
| CN109859866B (en) * | 2019-03-06 | 2022-02-22 | 中国核动力研究设计院 | Method for relieving accident consequence of main steam pipeline rupture |
| CN111125972B (en) * | 2019-12-26 | 2021-10-19 | 西安交通大学 | Hydraulic load analysis method for water loss accident of break of nuclear power plant |
| CN111540483B (en) * | 2020-05-15 | 2022-02-11 | 中国核动力研究设计院 | Method for coping with small-sized crevasse loss of coolant accident in pressurized water reactor nuclear power plant |
| CN111554425B (en) * | 2020-05-15 | 2022-02-11 | 中国核动力研究设计院 | Method for coping with extremely-small-break water loss accident of pressurized water reactor nuclear power plant |
| CN112863719B (en) * | 2021-01-12 | 2023-12-22 | 中国核电工程有限公司 | Design method for continuous steps in digital operation regulations of nuclear power plant |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
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| US3763836A (en) * | 1970-12-29 | 1973-10-09 | H Guehr | Coolant loss and coolant pump malfunction detection system for internal combustion engines |
| CN101079333A (en) * | 2006-05-26 | 2007-11-28 | 中国核动力研究设计院 | Nuclear reactor non-energy and multi-function pool voltage-stabling system |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20110255650A1 (en) * | 2010-03-31 | 2011-10-20 | Mcdaniel Robin Jerry | Bi-stable nuclear reactor |
| CN102881340B (en) * | 2012-09-27 | 2015-09-23 | 中国核电工程有限公司 | A kind of active and non-active last moment emergency shut-down of combining and method |
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- 2013-07-22 CN CN201310307099.5A patent/CN104332207B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3763836A (en) * | 1970-12-29 | 1973-10-09 | H Guehr | Coolant loss and coolant pump malfunction detection system for internal combustion engines |
| CN101079333A (en) * | 2006-05-26 | 2007-11-28 | 中国核动力研究设计院 | Nuclear reactor non-energy and multi-function pool voltage-stabling system |
Non-Patent Citations (4)
| Title |
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| Analysis of an Advanced Test Reactor Small-Break Loss-of-Coolant Accident with an Engineered Safety Feature to Automatically Trip the Primary Coolant Pumps;Steven T.Polkinghorne .et al;《Nuclear Technology》;20001031;第132卷(第1期);第167～178页 * |
| AP1000先进核电厂大破口RELAPS5建模及特性分析;殷煜皓;《中国优秀硕士学位论文全文数据库 工程科技II辑》;20120715(第7期);第37～55页 * |
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| CN104332207A (en) | 2015-02-04 |
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