CN1148721A - Safety system and recirculation control of safety casing spray system for nuclear power plant - Google Patents

Safety system and recirculation control of safety casing spray system for nuclear power plant Download PDF

Info

Publication number
CN1148721A
CN1148721A CN96109051A CN96109051A CN1148721A CN 1148721 A CN1148721 A CN 1148721A CN 96109051 A CN96109051 A CN 96109051A CN 96109051 A CN96109051 A CN 96109051A CN 1148721 A CN1148721 A CN 1148721A
Authority
CN
China
Prior art keywords
safety injection
recycle
peace
signal
spray
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
Application number
CN96109051A
Other languages
Chinese (zh)
Inventor
王守川
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Individual
Original Assignee
Individual
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Individual filed Critical Individual
Priority to CN96109051A priority Critical patent/CN1148721A/en
Publication of CN1148721A publication Critical patent/CN1148721A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

The recirculatkion control of safety injection system and containment spray system for nuclear power plant includes section valves, level meters and gate circuits, etc.. When the reloading water storage tank reaches to lower level, the recirculation signal is delivered from two channels, one channel signal is passed through NOT gate, and inputted into an AND gate together with safety injection signal, at this very moment said AND gate has no output, another channel signal is inputted into another AND gate together with safety injection or manual safety injection signal, so that said AND gate can give out signal to make the valves related to the safety injection and containment spray ystem accurately and automatically open or close. Said control system raises its reliability and reduces the possibility of error operation.

Description

The recycle control of nuclear power plant's safety injection system and containment spray system
The invention belongs to the control field, be specifically related to the recycle control of a kind of nuclear power plant safety injection system and containment spray system.
PWR nuclear power plant is made up of pressurized water reactor (light-water is forced into about 155 crust in the heap), a circuit system and three major parts of secondary coolant circuit system.Nuclear fission is to carry out in the reactor core of being made up of nuclear fuel in pressure vessel.Presurized water reactor is that fuel, light-water are cooling medium and moderator with the low-enrichment uranium.The nuclear fission liberated heat take out-pile out of by the water under high pressure of a circuit system in the heap of flowing through and in steamer generator with the water of heat transferred secondary circuit.The steam pushing turbine that produces after water is heated, steam turbine then drives generator for electricity generation.The fuel assembly that loads in the reactor core is made up of fuel rod (charging capacity reaches tens thousand of) one by one.The involucrum of fuel rod is made by zircaloy, and ceramic UO pellet is contained in involucrum pipe the inside.Involucrum pipe two ends are sealed by the welding end plug, fill with helium in the pipe.PWR nuclear power plant radiomaterial when normal operation is inclusive in the air gap between ceramic UO pellet or pellet and the involucrum, not having radiomaterial runs out, even the clad failure of a spot of fuel rod is arranged, also can remove the radiomaterial that is discharged in the cooling medium by cleaning system.The decay heat that produces after heat that produces during normal operation the or the shutdown is shifted out by normal cooling way (comprising residual heat removal system), and fuel element is fully cooled off all the time.
To PWR nuclear power plant, in case during the water under high pressure generation cut of a circuit system, the light water coolant in the reactor will run off from cut, loss of-coolant accident (LOCA) takes place.If when at this moment the normal moisturizing ability in a loop can not remedy the cooling medium of leakage, the nuclear fuel in the reactor core will lose cooling gradually, may cause fuel can to burn because of overheated, even the accident that causes uranium dioxide pellet to melt.For this reason, in the design of nuclear power plant, except normal cooling way is set, also is provided with a cover especially and is specifically designed to the cooling system that tackles dehydration and so on accident.This cover cooling system is called engineered safeguards features.It comprises high pressure safety injection system, low-voltage safety injected system (being referred to as safety injection system) and containment spray system etc.Containment spray system is after loss of-coolant accident (LOCA), the space environment in the whole containment of cooling containing, do not make containment because of a large amount of steam enter overvoltage, make it during accident, still to keep its integrality.Under the prerequisite of being kept perfectly property of containment, even loss of-coolant accident (LOCA) takes place, even when causing can breakage or reactor core to melt, a large amount of radioactivity can not take place yet be discharged into the situation of going in the environment.In case when loss of-coolant accident (LOCA) took place, normal cooling system had lost effect, safety injection system and containment spray system are just devoted oneself to work after receiving corresponding signal.If engineered safeguards features design imperfection, they just can not correctly bring into play design function, might make reactor core can not get abundant cooling, the accident that causes can breakage even fuel pellet to melt.In case this situation appears, with cause ten million, more than one hundred million even tens economic loss, when serious not only bed rearrangement nuclear power plant scrap, also can cause radioactive contamination to environment.Three Mile Island accident is exactly because operations staff's maloperation causes reactor core to melt, cause the loss of-coolant accident (LOCA) of multi-million dollar loss in the processing accident.
The duty of PWR nuclear power plant safety injection system can be divided into two stages: 1. the direct injection stage---in this stage, the safety injection pump of safety injection system is from reloading water storage bin suction and water injected reactor core, water in the case is used for being full of reactor pit when reloading, the operation of reloading is carried out all the time under water, prevented fuel superheater; 2. recycle stage---when loss of-coolant accident (LOCA), water in the case is as the water source of safety injection system and spray system, when reaching low low-water level, the water in the case represents that the water in the case has run low, safety injection system then switches to from the melt pit of containment and fetches water, this water is to be pooled in the containment sump by the water that cut and spray system flow out in the stage of directly injecting, make this system enter the recycle stage, reactor core is cooled off for a long time.The direct injection mode of safety injection system is annotated signal triggering by peace.Safety injection system one is received peace and is annotated signal, and safety injection pump and have closing valve just to open or shut by designing requirement directly is injected in core piles water in the water storage bin that reloads.When the water in the water storage bin that reloads reaches low low-water level, then send egr signal.This signal is shut the safety injection pump and the isolation valve on the pipeline that reloads between the water storage bin, and the isolation valve on the pipeline between safety injection pump and the melt pit opened, water in the melt pit is injected into the water in the melt pit in the reactor core by safety injection pump (low pressure safety injection pump or low pressure safety injection pump and high-pressure safety injection pump are connected in series), realize recycle peace notes, enter the recycle stage of safety injection system.
The working condition and the safety injection system of containment spray system are similar, and just this system sprays the water in the water storage bin that reloads in the space of containment at direct spray phase, then the water in the melt pit is sprayed in the space of containment in the recycle stage.
There is following problem in the automatic recycle design of present domestic PWR nuclear power plant safety injection system and containment spray system:
1. the reliability of egr signal is not high.The PWR nuclear power plant safety injection system of present domestic design and the automatic egr signal of containment spray system send part, just the reload liquid level indication of storage bin of water, four liquid level gauges are set in design, by two uninterrupted power sources, every is two liquid level gauge power supplies, adopt the output of 2/4 logic, this design does not have redundancy concerning power supply, a power supply breaks down, just make two liquid level gauges lose indication because of losing power supply, thereby send low liquid level signal, will send egr signal according to 2/4 logic output relation, so the reliability of this system's generation egr signal part is not high;
2. the PWR nuclear power plant of domestic design, former design is automatic recycle, afterwards automatic recycle was changed into manual recycle, so just introduced the human intervention factor, might cause maloperation that safety injection system and container spray shell systems can not normally be played a role in the recycle stage, change automatic recycle into manual recycle and reduced automaticity;
3. automatic recycle is changed into manual recycle and still do not solve the incorrect problem of interlock connection between the valve.As previously mentioned, concerning safety injection system and spray system, in the recycle stage, safety injection pump and spray pump and the isolation valve that reloads between the water storage bin should be closed, but this interlocking imperfection in its design, in fact safety injection pump and spray pump and reload between the water storage bin isolation valve the recycle stage except that being subjected to recycle isolation signals control, still be subjected to peace notes signal controlling and do not have final plant closure, some peace is annotated signal and is existed in accident process always, so this several valves the recycle stage as not taking other measure, they still can be among the alternating state of certain switching, reason is that these valves are subjected to two signal controlling at this moment: the direct safety injection signal makes it open, and recycle peace notes signal makes its pass, so only closing these isolation valves by egr signal can not bar up fully, therefore make safety injection pump and spray pump can not bring into play its normal effect because of cavitation, consequence is well imagined;
4., may send false egr signal when if egr signal can not correctly provide; And the interlock connection between the valve is incorrect, makes these two systems can not provide necessary chilled water and shower water for reactor core and containment in the recycle stage probably, and its consequence may be very serious.
The purpose of this invention is to provide the recycle control of a kind of nuclear power plant safety injection system and containment spray system.
This nuclear power plant's safety injection system and containment spray system recycle control, comprise isolation valve, the reload liquid level gauge of the low low liquid level of water storage bin of energy measurement, can control isolation valve and switch to the gate circuit that the recycle container spray was annotated or switched to by direct container spray to the recycle peace by direct safety injection, wherein, three or four liquid level gauges have two-way output by 2/3 or 2/4 logical circuit, one the tunnel output by not gate NOT be connected with the input end of door AND2, another is input as peace and annotates signal with door AND2, under normal operation, do not export with door AND2, have only when the signal existence of peace notes and do not exist when hanging down liquid level signal and output is just arranged with an AND2, this signal makes safety injection system and containment spray system enter direct safety injection and direct spray phase, open safety injection pump and containment spray pump and reload direct safety injection and direct spray isolation valve between the water storage bin, the recycle peace of closing simultaneously between safety injection pump and containment spray pump and the melt pit is annotated and recycle spray isolation valve, realizes direct safety injection and spray; Reload water storage bin liquid level gauge 2/3 or 2/4 logical circuit the output of another road and connect with the input end of door AND1, annotate signal or manually pacify the notes signal and also accept peace with door AND1, under normal operation and direct safety injection, spray phase and not output of door AND1, only when the water storage bin that reloads sends low low liquid level signal and peace is annotated or manually peace is annotated signal and existed simultaneously, output is just arranged with a door AND1, this signal makes safety injection system and containment spray system enter the recycle stage, the recycle peace of opening between melt pit and safety injection pump and the spray pump is annotated and recycle spray isolation valve, close safety injection pump and spray pump and reload direct safety injection and direct spray isolation valve between the water storage bin, realize that the recycle peace is annotated and recycle sprays.
The recycle control of safety injection system, it comprises isolation valve V1A/B, V2A/B, V3A/B, V4A/B, liquid level gauge, with door AND1, AND2, not gate NOT, self-sustaining unit Z, delay unit S, wherein, the reload liquid level gauge of the low low liquid level of water storage bin of energy measurement has two-way output by 2/3 or 2/4 logical circuit, one the tunnel output by not gate NOT be connected with the input end of door AND2, another is input as peace notes signal and with door AND2, under normal operation, do not export with door AND2, have only when peace and annotate that signal exists and not input and with a door AND2 output is arranged just when having output promptly not have low liquid level signal of not gate NOT, by and electric signal of door AND2 output is opened safety injection pump and reload direct safety injection isolation valve V1A/B and V2A/B between the water storage bin, the recycle peace of closing simultaneously between safety injection pump and the melt pit is annotated isolation valve V3A/B and V4A/B, realizes direct safety injection; Another road is exported and is connected with the input end of door AND1, manually or automatically peace annotate signal through self-sustaining unit Z with connect with another input end of door AND1, under normal operation, do not export with door AND1 with the direct safety injection stage, only when the water storage bin that reloads sends low low liquid level signal and peace is annotated or manually peace is annotated signal and existed simultaneously, output is just arranged with a door AND1, this signal makes safety injection system enter the recycle stage, making recycle peace between melt pit and the safety injection pump annotate isolation valve V4A/B opens and then controls isolation valve V3A/B and open, the direct safety injection isolation valve V1A/B and the V2A/B that make safety injection pump and reload between the water storage bin close through delay unit S, realize recycle peace notes.
Container spray recycle switching controls, it comprises isolation valve V4A/B, V5A/B, V6A/B, liquid level gauge, with door AND1, AND2, not gate NOT, self-sustaining unit Z, delay unit S, wherein, the liquid level gauge of the low liquid level of energy measurement material-changing water tank has two-way output by 2/3 or 2/4 logical circuit, one the tunnel output by not gate NOT be connected with the input end of door AND2, another is input as peace notes signal and with door AND2, under normal operation, do not export with door AND2, have only when peace and annotate that signal exists and not input and with a door AND2 output is arranged just when having output promptly not have low liquid level signal of not gate NOT, by and electric signal of door AND2 output is opened containment spray pump and the direct spray isolation valve V5A/B between the water storage bin of reloading, isolation valve V4A/B and V6A/B between closed safe shell spray pump and the melt pit realizes direct container spray simultaneously; Another road is exported and is connected with the input end of door AND1, peace annotate or manually peace annotate signal through self-sustaining unit Z with connect with another input end of door AND1, the container spray stage does not have output with door AND1 under normal operation and directly, only when the water storage bin that reloads sends low low liquid level signal and peace is annotated or manually peace is annotated signal and existed simultaneously, output is just arranged with a door AND1, this signal makes containment spray system enter the recycle stage, making recycle spray isolation valve V4A/B between melt pit and the spray pump open and then control isolation valve V6A/B opens, the direct spray isolation valve V5A/B that makes spray pump and reload between the water storage bin closes through delay unit S, realizes the recycle spray.
The liquid level gauge of the low liquid level of this control system measurement is formed by 3~4, is respectively its power supply by 3~4 uninterrupted power sources.
Can also in this system, not add not gate NOT and with door AND2, and on peace notes signal line, put a relay J, the manual operation relay J disconnects relay tip J1-1 when entering recycle peace notes and recycle spray, thereby cuts off the control of peace notes signal to each isolation valve.
Advantage of the present invention is:
1. the liquid level gauge of water storage bin of reloading adopts three or four uninterrupted power sources, every liquid level gauge is all by independently uninterrupted power source power supply, when adopting three liquid level gauges, be respectively its power supply by three uninterrupted power sources, and adopt the output of 2/3 logic, when adopting four liquid level gauges, be respectively its power supply by four uninterrupted power sources, and adopt the output of 2/4 logic, at any time provide low liquid level signal so always can guarantee two liquid level gauges, Pei Zhi indication mechanism has very high reliability like this, and the closing valve that has of safety injection system and containment spray system can correctly be opened and closed after receiving egr signal;
2. safety injection system and the containment spray system process that switches to the recycle stage from the direct injection stage can be finished automatically, thereby has reduced the possibility of people for maloperation, has improved the reliability of safety injection system and containment spray system;
3. solved safety injection pump and spray pump and reload isolation valve between the water storage bin and the isolation valve between melt pit and safety injection pump and the spray pump the recycle stage except that being subjected to the control of recycle isolation signals, still pacified the problem of annotating signal controlling and thoroughly not closing.
The invention will be further described below in conjunction with accompanying drawing:
Fig. 1 is the safety injection system synoptic diagram, containment comprises the water storage bin 1 that reloads, high-pressure safety injection pump 2~5, low pressure safety injection pump 6,7, electronic isolation valve V1A/B, V2A/B, V3A/B outward, comprises melt pit 8, electronic isolation valve V4A/B, presurized water reactor 9, a loop 10, secondary circuit 11, voltage stabilizer 12 etc. in the containment.
Fig. 2 is the containment spray system synoptic diagram, and containment comprises the water storage bin 1 that reloads, spray pump 13,14, electronic isolation valve V4A/B, V5A/B, V6A/B etc. outward, comprises melt pit 8, nozzle sets 15 etc. in the containment.
Fig. 3 is the automatic recirculation control system synoptic diagram of safety injection system, comprises and door AND1, AND2, not gate NOT, electronic isolation valve V1A/B, V2A/B, V3A/B, V4A/B, self-sustaining unit Z, delay unit S etc.
Fig. 4 comprises and door AND1, AND2, not gate NOT, electronic isolation valve V4A/B, V5A/B, V6A/B, self-sustaining unit Z, delay unit S for the automatic recycle control of containment spray system is synoptic diagram.
Fig. 5 is the manual recirculation control system synoptic diagram of safety injection system, comprises and door AND1, relay tip J1-1, electronic isolation valve V1A/B, V2A/B, V3A/B, V4A/B, self-sustaining unit Z, delay unit S etc.
Fig. 6 is the manual recirculation control system synoptic diagram of containment spray system, comprises and door AND1, relay tip J1-1, electronic isolation valve V4A/B, V5A/B, V6A/B, self-sustaining unit Z, delay unit S.
Embodiment 1:
See that from Fig. 3 in the direct safety injection stage, valve V1A/B and V2A/B are in open mode, and V3A/B and V4A/B still are in closed condition.When the water in the water storage bin that reloads uses up (reaching low low-water level), need switch in containment sump and fetch water, at this moment valve V1A/B and V2A/B then shut, and valve V3A/B and V4A/B then open, and finish handoff procedure.
With door AND1 on two inputs are arranged: one is direct safety injection signal (through self-contained unit), comprise manually and automatically peace annotate signal, another is an egr signal, is provided by the low liquid level signal 2/4 or 2/3 of the water storage bin that reloads.Then AND1 has output when these two signals exist simultaneously.This output signal is opened melt pit isolation valve V4A/B; Sending signal after V4A/B opens opens V3A/B; Through a chronotron (can establish and not establish) V2A/B and V1A/B are shut after V3A/B opens,, realize the recycle of peace notes, safety injection pump is fetched water from melt pit inject reactor core so finish change action automatically according to concrete engineering design.Must guarantee that in the direct safety injection stage V1A/B and V2A/B open, must guarantee that V3A/B and V4A/B shut simultaneously; Must guarantee that in the recycle stage V1A/B and V2A/B shut; Simultaneously must guarantee that V3A/B and V4A/B open.For this reason, the present invention establishes a not gate after the low liquid level of the water storage bin that reloads meets logic 2/4 or Unit 2/3, and this not gate is annotated signal with peace and provided an output through one with door AND2, and this output is added on valve V1A/B and V2A/B and V4A/B and the V3A/B; In the direct safety injection stage, the water storage bin that reloads does not reach low liquid level, so not gate is not imported but output is arranged, and peace notes signal is in the direct safety injection stage, at this moment with electric signal of door AND2 output, V1A/B and V2A/B are opened, V3A/B and V4A/B are shut, above-mentioned course of action has satisfied the requirement of direct safety injection fully.When entering recycle during the stage, the water storage bin that reloads reaches low liquid level, send egr signal by 2/4 or 2/3 logic, at this moment not gate has input but no-output, after this signal is added to and goes up with door AND2, AND2 has not just exported, valve V1A/B and V2A/B have cut off the instruction of opening, valve V3A/B and V4A/B have cut off the instruction of closing, egr signal and manual or automatic peace notes signal are added on the AND1 simultaneously at this moment, and V4A/B is opened, and send signal after V4A/B opens V3A/B is opened, send signal after V3A/B opens V1A/B and V2A/B are shut, safety injection system then switched to the recycle peace by direct safety injection and annotates duty after above-mentioned action was finished.According to some specific design situation, can on some link, add delay circuit; Also can on some link, annotate the input signal place as the peace before the AND2 and add a self-sustaining unit.
Fig. 4 is the recycle switch logic figure of containment spray system, as long as use the valve V5A/B of containment spray system to replace valve V1A/B in the safety injection system and V2A/B, V3A/B replaces with V6A/B, and the logical relation and the handoff procedure of relevant safety injection system just have been applicable to containment spray system.
Embodiment 2:
Can see as long as the manual operation relay J makes contact J1-1 action cut off peace to annotate signal when the water storage bin that reloads reaches low low liquid level from Fig. 5, Fig. 6, at this moment each isolation valve only is subjected to the recycle peace to annotate signal controlling, be not subjected to peace to annotate signal controlling, and egr signal makes direct safety injection isolation valve V1A/B, V2A/B and directly sprays isolation valve V5A/B and closes, recycle peace notes isolation valve and recycle spray isolation valve V3A/B, V4A/B, V6A/B are opened, and realization recycle peace is annotated and the recycle container spray.Under normal operation, relay tip J1-1 is a normally closed contact, enter direct safety injection during the stage, relay tip J1-1 is closed, the manual operation relay J disconnects relay tip J1-1 when being switched to the recycle injection by direct injection, assurance recycle is normally carried out, and relay J is installed in the central control room.

Claims (5)

1. the recycle of nuclear power plant's safety injection system and containment spray system control, it is characterized in that it comprises isolation valve, the reload liquid level gauge of the low low liquid level of water storage bin of energy measurement, can control isolation valve and switch to the gate circuit that the recycle container spray was annotated or switched to by direct container spray to the recycle peace by direct safety injection, wherein, three or four liquid level gauges have two-way output by 2/3 or 2/4 logical circuit, one the tunnel output by not gate NOT be connected with the input end of door AND2, another is input as peace and annotates signal with door AND2, under normal operation, do not export with door AND2, when peace annotates that signal exists and not input and with a door AND2 output is arranged just when having output promptly not have low liquid level signal of not gate NOT, this signal makes safety injection system and containment spray system enter direct safety injection and direct spray phase, open safety injection pump and containment spray pump and the direct safety injection isolation valve between the water storage bin of reloading, the recycle peace of closing simultaneously between safety injection pump and containment spray pump and the melt pit is annotated and recycle spray isolation valve, realizes direct safety injection and spray; Another road output of 2/3 or 2/4 logical circuit of water storage bin liquid level gauge of reloading connects with the input end of an AND1, and also accept the peace notes or manually pacify to annotate signal with door AND1, under normal operation and direct safety injection, spray phase and not output of door AND1, when the water storage bin that reloads sends low low liquid level signal and peace is annotated or manually peace is annotated signal and existed simultaneously, output is just arranged with a door AND1, this signal makes safety injection system and containment spray system enter the recycle stage, the recycle peace of opening between melt pit and safety injection pump and the containment spray pump is annotated and recycle spray isolation valve, close safety injection pump and containment spray pump and reload direct safety injection and direct spray isolation valve between the water storage bin, realize that the recycle peace is annotated and recycle sprays.
2. the recycle control of nuclear power plant according to claim 1 safety injection system and containment spray system, the recycle control that it is characterized in that safety injection system comprises isolation valve V1A/B, V2A/B, V3A/B, V4A/B, liquid level gauge, with door AND1, AND2, not gate NOT, self-sustaining unit Z, delay unit S, wherein, the liquid level gauge of the low liquid level of energy measurement material-changing water tank has two-way output by 2/3 or 2/4 logical circuit, one the tunnel output by not gate NOT be connected with the input end of door AND2, another is input as peace notes signal and with door AND2, under normal operation, do not export with door AND2, when peace annotates that signal exists and not input and with a door AND2 output is arranged just when having output promptly not have low liquid level signal of not gate NOT, by and electric signal of door AND2 output is opened safety injection pump and reload direct safety injection isolation valve V1A/B and V2A/B between the water storage bin, the recycle peace of closing simultaneously between safety injection pump and the melt pit is annotated isolation valve V3A/B and V4A/B, realizes direct safety injection; Another road is exported and is connected with the input end of door AND1, peace annotate or manually peace annotate signal through self-sustaining unit Z with connect with another input end of door AND1, under normal operation, do not export with door AND1 with the direct safety injection stage, only when the water storage bin that reloads sends low low liquid level signal and peace is annotated or manually peace is annotated signal and existed simultaneously, output is just arranged with a door AND1, this signal makes safety injection system enter the recycle stage, making recycle peace between melt pit and the safety injection pump annotate isolation valve V4A/B opens and then controls isolation valve V3A/B and open, the direct safety injection isolation valve V1A/B and the V2A/B that make safety injection pump and reload between the water storage bin close through delay unit S, realize recycle peace notes.
3. the recycle control of nuclear power plant according to claim 1 safety injection system and containment spray system, the recycle control that it is characterized in that containment spray system comprises isolation valve V4A/B, V5A/B, V6A/B, liquid level gauge, with door AND1, AND2 not gate NOT, self-sustaining unit Z, delay unit S, wherein, the reload liquid level gauge of the low low liquid level of water storage bin of energy measurement has two-way output by 2/3 or 2/4 logical circuit, one the tunnel output by not gate NOT be connected with the input end of door AND2, another is input as peace notes signal and with door AND2, under normal operation, do not export with door AND2, have only when peace and annotate that signal exists and not input and with a door AND2 output is arranged just when having output promptly not have low liquid level signal of not gate NOT, by and electric signal of door AND2 output is opened containment spray pump and the direct spray isolation valve V5A/B between the water storage bin of reloading, isolation valve V4A/B and V6A/B between closed safe shell spray pump and the melt pit realizes direct container spray simultaneously; Another road is exported and is connected with the input end of door AND1, peace annotate or manually peace annotate signal through self-sustaining unit Z with connect with another input end of door AND1, spray phase and door AND1 do not export under normal operation with directly, only when the water storage bin that reloads sends low low liquid level signal and peace is annotated or manually peace is annotated signal and existed simultaneously, output is just arranged with a door AND1, this signal makes containment spray system enter the recycle stage, making recycle spray isolation valve V4A/B between melt pit and the spray pump open and then control isolation valve V6A/B opens, the direct spray isolation valve V5A/B that makes spray pump and reload between the water storage bin closes through delay unit S, realizes the recycle spray.
4. the recycle control of nuclear power plant according to claim 1 safety injection system and containment spray system is characterized in that the liquid level gauge of the low liquid level of control system measurement is formed by 3~4, is respectively its power supply by 3~4 uninterrupted power sources.
5. the recycle of nuclear power plant's safety injection system and containment spray system control is characterized in that entering recycle manual operation relay J when injecting, and relay tip J1-1 is disconnected.
CN96109051A 1996-08-05 1996-08-05 Safety system and recirculation control of safety casing spray system for nuclear power plant Pending CN1148721A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN96109051A CN1148721A (en) 1996-08-05 1996-08-05 Safety system and recirculation control of safety casing spray system for nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN96109051A CN1148721A (en) 1996-08-05 1996-08-05 Safety system and recirculation control of safety casing spray system for nuclear power plant

Publications (1)

Publication Number Publication Date
CN1148721A true CN1148721A (en) 1997-04-30

Family

ID=5120182

Family Applications (1)

Application Number Title Priority Date Filing Date
CN96109051A Pending CN1148721A (en) 1996-08-05 1996-08-05 Safety system and recirculation control of safety casing spray system for nuclear power plant

Country Status (1)

Country Link
CN (1) CN1148721A (en)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
CN102402230A (en) * 2011-11-29 2012-04-04 中广核工程有限公司 Liquid level measuring and controlling system
CN101840738B (en) * 2009-06-24 2012-06-27 中广核工程有限公司 Installation method of safety injection tank of nuclear island building of nuclear power plant
CN105427903A (en) * 2015-12-11 2016-03-23 哈尔滨工程大学 Recycling safety injection system adopting gas-liquid booster pump and applied to nuclear power plant
CN107131012A (en) * 2017-06-09 2017-09-05 中广核工程有限公司 Nuclear power station prevents the method and system of nuclear island peace note signal false triggering
US10993087B1 (en) 2019-12-03 2021-04-27 Motorola Solutions, Inc. Communication systems with call interrupt capabilities

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101840738B (en) * 2009-06-24 2012-06-27 中广核工程有限公司 Installation method of safety injection tank of nuclear island building of nuclear power plant
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
CN102034559B (en) * 2010-09-19 2012-08-01 中广核工程有限公司 Rapid mutual-backup system of nuclear power station and mutual-backup method thereof
CN102402230A (en) * 2011-11-29 2012-04-04 中广核工程有限公司 Liquid level measuring and controlling system
CN105427903A (en) * 2015-12-11 2016-03-23 哈尔滨工程大学 Recycling safety injection system adopting gas-liquid booster pump and applied to nuclear power plant
CN107131012A (en) * 2017-06-09 2017-09-05 中广核工程有限公司 Nuclear power station prevents the method and system of nuclear island peace note signal false triggering
CN107131012B (en) * 2017-06-09 2019-07-23 中广核工程有限公司 Nuclear power station prevents the method and system of nuclear island peace note signal false triggering
US10993087B1 (en) 2019-12-03 2021-04-27 Motorola Solutions, Inc. Communication systems with call interrupt capabilities

Similar Documents

Publication Publication Date Title
US3528884A (en) Safety cooling system for a nuclear reactor
CN102638095B (en) A kind of method of supplying power to of nuclear power plant cold-state function test
CN102881340B (en) A kind of active and non-active last moment emergency shut-down of combining and method
CN202887744U (en) Combined active and passive emergency shut-down system
CN110517801A (en) A kind of nuclear power unit control rod avoids engineered safeguards features from acting method and system when falling extremely
CN109903863A (en) A kind of safety injection system and nuclear power system
CN104992733B (en) A kind of safety injection system
CN1148721A (en) Safety system and recirculation control of safety casing spray system for nuclear power plant
Dazhong et al. Technical design features and safety analysis of the 200 MWt nuclear heating reactor
CN207529679U (en) A kind of safety injection system and nuclear power system
JP2953787B2 (en) Light water reactor
US3702281A (en) Removal of heat from a nuclear reactor under emergency conditions
US5213755A (en) Low pressure coolant injection modification for boiling water reactors
US10726960B2 (en) Nuclear reactor safety system
CN209625811U (en) A kind of safety injection system and nuclear power station
Burns et al. Preliminary development of an integrated approach to the evaluation of pressurized thermal shock as applied to the Oconee Unit 1 Nuclear Power Plant
JPH053559B2 (en)
CN101727995B (en) Anti-error safety injection and spraying method for power-fail experiment of control switchboard of nuclear power stations
Zhang et al. The reliability analysis of pressurized water reactor safety injection system based on GO-FLOW
Do Yeon Kima et al. A Study on SGTR accident management using the MELCOR code
Dengke et al. Research on Power Supply of Electric Isolation Valve in the Containment of CPR1000 Unit
Statsura et al. Key results of commissioning activities for the emergency and scheduled cooldown system of the AES-2006 unit with the V-392M reactor plant
Dingman et al. Core damage frequency prespectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results
CN104715800A (en) Nuclear power plant emergency power source power supply test method and system
CN110970140A (en) Boron implantation system

Legal Events

Date Code Title Description
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C06 Publication
PB01 Publication
C02 Deemed withdrawal of patent application after publication (patent law 2001)
WD01 Invention patent application deemed withdrawn after publication