CN104282349A - Method for guiding nuclear power plant to be safe under condition of fire disaster - Google Patents
Method for guiding nuclear power plant to be safe under condition of fire disaster Download PDFInfo
- Publication number
- CN104282349A CN104282349A CN201410384452.4A CN201410384452A CN104282349A CN 104282349 A CN104282349 A CN 104282349A CN 201410384452 A CN201410384452 A CN 201410384452A CN 104282349 A CN104282349 A CN 104282349A
- Authority
- CN
- China
- Prior art keywords
- fire
- power plant
- nuclear power
- unit
- function
- 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.)
- Granted
Links
Classifications
-
- 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
Abstract
The invention belongs to a nuclear power plant design technology and particularly relates to a method for guiding a nuclear power plant to be safe under the condition of a fire disaster. The method includes the steps that first, existing running accident regulations of the nuclear power plant are cleared up, and key information used for unit state judgment and regulation guidance is cleared out; unavailable functions, equipment and information caused by the fire disaster are cleared up for each fireproof space, and whether unacceptable results are caused by the fire disaster or not is judged; if unacceptable results are caused by the fire disaster, operators perform specific operation in order to guarantee the safety of the unit besides basic fire extinguishment and rescue actions. Due to a series of action requirements, the unit can be guided to be safe under the condition of the fire disaster, the operators can operate the unit according to a basis under the condition of the fire disaster, human errors are reduced, and a nuclear power plant accident handling mode is perfected.
Description
Technical field
The invention belongs to nuclear power plant design technology, be specifically related to a kind of method nuclear power plant being guided under fire condition safe condition.
Background technology
After within 2011, Fukushima, Japan nuclear accident occurs, countries in the world generally improve the safety requirements to nuclear power station.The Chinese government requires that design of nuclear power plant adopts state-of-the-art standard, with General Promotion nuclear power plant reliability and emergency response level, guarantees the safety of nuclear power station.Except traditional fire prevention, restriction fire spread and the technological means that stamps out a fire, improving nuclear power plant's fire safety level also needs to guarantee that unit can correctly be guided to safe recession pattern by operator in case of fire.Therefore, the Accident Handling Method studied under nuclear power plant's fire condition is one of Main Trends of The Development of nuclear power fire protection design.
The design proposal current according to domestic most nuclear power plant, when a fire, it is on that relevant operations staff and fire fighter all participate in fire fighting and rescue, main control room operator is by contact on-the-spot operator, fire brigade, rescue group etc., take the action such as fire confirmation, evacuating personnel, isolation ventilation, fire-extinguishing operations, contact with foreign countries and organization and administration, these operations and action are through the mature technology of practice test, and have been embodied in power plant's associated documents.
But, except considering fire extinguishing and rescue action, fire also can cause safety related functions and have a strong impact on, and now which equipment and information are available and reliable, which equipment and information have been subject to fire damage and unavailable, should how to find a reliable operation path that unit is guided to safe condition, operator is perfectly clear, the region that can only occur according to available data and fire provides general judgement, likely cause maloperation or miss optimal trip-reclosure time, and then the risk that initiation set state worsens further.
Summary of the invention
The object of the invention is to the defect for prior art, a kind of method in case of fire nuclear power plant being guided to safe condition is provided, instruct operator to control nuclear power generating sets in case of fire by the method, and unit take specific safe condition to the most at last.
Technical scheme of the present invention is as follows: a kind of method under fire condition, nuclear power plant being guided to safe condition, comprises the steps:
(1) combing is carried out to the existing operation of nuclear power plant, malfunction protocol, clean out for the key message that set state judges and code leads, these information are for of crucial importance the operation of unit and accident treatment, to judging that set state plays a decisive role, and operator can be guided to choose rational operation strategy;
(2) for each fire protection space, unavailable function, equipment and information that combing fire causes, judge whether fire causes unacceptable consequence;
(3) if fire can not cause unacceptable consequence, then fire is to unit safety function moment-less influence, only takes basic fire extinguishing, rescue action; If fire can cause unacceptable consequence, then enter step (4);
(4) except basic fire extinguishing, rescue action, in order to ensure unit safety, operator performs following operation:
A) foresight operation, puts into operation available redundance unit in advance, and startup corresponding operating arrives the recession pattern of specifying to guide unit as early as possible; Meanwhile, the necessary precautionary measures are taked to prevent the deterioration of set state in advance;
B) power operation, is initiatively cut off the power supply of the nuclear safety relevant device by influence of fire by operator;
C) marking operation, to being subject to influence of fire, disabled function marks;
D) alternative information or designated value operation is provided, due in case of fire will be no longer reliable by influence of fire and disabled information, by the information of its redundancy or determine that alternate parameter is to ensure that unit can be brought into the reliable behavior of specifying by the operation performed by operator in case of fire in advance;
E) determine that recession pattern operates, described recession pattern refers under fire causes the disabled situation of Partial security function, and unit can reach and the acceptable safe condition maintained;
F) record other because of fire disabled equipment, information and false alarm.
Further, under fire condition as above, nuclear power plant is guided to the method for safe condition, the unacceptable consequence described in step (2) comprises:
1) one or more support function is completely lost, support that function is namely in order to ensure nuclear steam supply system (Normal Steam Supply System, be called for short NSSS) validity and required function, mainly comprise function of supplying power, for airway dysfunction, instrument controlling functions, refrigerating function etc.;
2) the foreseeable or reactor emergency shut-down that occurred, the normal operation function of adjoint kernel steam supply system lost efficacy simultaneously;
3) inefficacy of the normal operation function of nuclear steam supply system may cause event transient state or accident transient state;
4) other unacceptable consequence.
Beneficial effect of the present invention is as follows: fire is brought in the Incident Management system of unit operation by the present invention first, optimizes the operation strategy under fire condition, improves the safety management level that rear nuclear power generating sets occur fire; Under the fire condition formed by the method, unit is guided to a series of action requirements of safe condition, make operator evidence-based to the operation of unit operation in case of fire, reduce human-equation error, perfect nuclear power plant's accident treatment pattern.
Accompanying drawing explanation
Fig. 1 is the method flow diagram under fire condition of the present invention, nuclear power plant being guided to safe condition.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail.
As shown in Figure 1, under a kind of fire condition provided by the invention, nuclear power plant is guided to the method for safe condition, comprise the steps:
(1) combing is carried out to the existing operation of nuclear power plant, malfunction protocol, find the key message that those set states judge and code leads, these information are for of crucial importance the operation of unit and accident treatment, to judging that set state plays a decisive role, and operator can be guided to choose rational operation strategy;
(2) for each fire protection space, unavailable function, equipment and information that combing fire causes, and judge whether fire can cause following unacceptable consequence:
2-1) completely lose one or more support function, support that function is namely in order to ensure nuclear steam supply system (Normal Steam Supply System, be called for short NSSS) validity and required function, mainly comprise function of supplying power, for airway dysfunction, instrument controlling functions, refrigerating function etc.;
2-2) the foreseeable or reactor emergency shut-down that occurred, adjoint kernel steam supply system (Normal Steam Supply System is called for short NSSS) normal operation function lost efficacy simultaneously;
2-3) inefficacy of the normal operation function of certain nuclear steam supply system (NSSS) may cause event transient state or accident transient state (such as, lose down under primary Ioops single phase let out function);
2-4) other unacceptable consequence;
(3) if fire can not cause the unacceptable consequence described in step (2), then fire is to unit safety function moment-less influence, only takes the action such as basic fire extinguishing, rescue;
(4) if fire causes one of unacceptable consequence described in step (2), then except substantially putting out a fire, except rescue action, in order to ensure unit safety, operator also needs to perform following operation:
A) foresight operation, on the one hand, in order to reduce the impact of fire on unit operation, puts into operation available redundance unit in advance, and startup corresponding operating arrives the recession pattern of specifying to guide unit as early as possible; On the other hand, some unnecessary transient state caused to prevent fire thus cause the deterioration of set state, needs to take the necessary precautionary measures in advance;
B) power operation, in order to clear and definite NSSS functional status, to reduce the risk that equipment malfunction is done and sent instruction by mistake, initiatively cuts off by operator the nuclear safety relevant device that some is subject to influence of fire;
C) marking operation, in order to optimize the execution of accident treatment program, operator is accurately judged in time, fast processing accident conditions, and corresponding " substituting " equipment that directly puts into operation after knowing the unavailable information of function, to being subject to influence of fire, disabled function (comprise NSSS function and support function) marks;
D) alternative information or designated value operation is provided, due in case of fire will be no longer reliable by influence of fire and disabled information (comprising condition adjudgement and navigation information), by the information of its redundancy or determine that alternate parameter is to ensure that unit can be brought into the reliable behavior of specifying by the operation performed by operator in case of fire in advance;
E) determine recession pattern operation (namely final safe condition), described recession pattern refers to considers disabled equipment, and unit can reach and the acceptable safe condition maintained;
F) except above-mentioned main unavailable function and information, record other because of fire disabled equipment, information and false alarm, understand for operator the disabled details of equipment that fire causes in more detail, the integrality of unit is had to understanding and the control of the overall situation.
When the impact that nuclear power plant's fire causes meets step (2) (namely fire causes unit operation and safety and has a strong impact on), a series of action requirements that operator is formed according to step (4), form a set of working specification, to be taken to by unit in case of fire and to maintain the safe condition of specifying.
Embodiment
Now for certain nuclear power plant's nuclear auxiliary building hot penetration piece place fire protection space (being numbered 1ZFSN0280A), method nuclear power plant being guided under above-mentioned fire condition safe condition is adopted progressively to be analyzed as follows:
First, the all accident treatment codes of this nuclear power plant are analyzed, clean out the key message wherein for condition adjudgement and code guiding, comprise primary Ioops pressure, water level, temperature, undersaturation degree, secondary circuit pressure, water level, containment pressure and dosage water equality monitor value.
Secondly, the cable in fire protection space 1ZFSN0280A and equipment are analyzed.Draw in conjunction with fire risk and device characteristics: fire can cause lower pressure release power and flow control valve (RCV 013VP) and charging flow regulating valve (RCV 046VP) standard-sized sheet, outer isolation valve (RCV 010VP) complete shut-down of letdown line containment, namely fill on causing standard-sized sheet and under let out isolation, cause filling and under the normal operation function of NSSS let out unavailable, simultaneously due to above fill and under the flow let out do not mate, voltage stabilizer liquid level also can be caused to rise rapidly and produce " voltage stabilizer liquid level is high by 3 " reactor scram signal.In addition, to fill letdown flow information, voltage stabilizer auxiliary spray, high-pressure safety injection, residual heat removal system (RRA) and cvcs (RCV) interface function on also causing unavailable etc. for fire.
According to above-mentioned analysis result, propose to take action as follows requirement, to alleviate the result of accident treatment:
A) foresight operation
(1) when reactor capability is greater than 10% full power (P>P7) running status, due to above fill and under the flow let out do not mate, cause voltage stabilizer liquid level to rise rapidly and produce " under P7 permission signal, voltage stabilizer liquid level is high " reactor scram signal, therefore emergency shut-down requirement is performed to require operator to confirm at the very start, and take to isolate fill and under the action of letting out, simultaneously because volume control tank (RCV 002BA) liquid level declines, need to confirm that RCV Pump Suction Nozzle has been converted to the operation of material-changing water tank (PTR 001BA) from RCV 002BA,
Due under let out and isolate, then main pump shaft water shutoff is injected and primary Ioops water loading amount will be caused to rise, in order to avoid causing primary Ioops superpressure, need to carry out cooling down operation by the atmospheric dump valve (GCTa) of three steam generators to primary Ioops, and unit is brought to residual heat removal system (RRA) connection status.
(2) when reactor is in that power is less than 10% full power (P<P7) running status, steam generator cools normal shutdown pattern (NS/SG) or RRA cools normal shutdown pattern two-phase state (NS/RRA biphasic), take the operation that same P>P7 state is same, the confirmation of reactor emergency shut-down operation requires consistent with the malfunction protocol of power plant.
(3) when reactor be in RRA cool normal shutdown pattern single phase (NS/RRA monophasic) or maintenance cold shut and primary Ioops be closed condition time, very easily due on fill letdown flow and do not mate and cause primary Ioops superpressure transient state, operation now will adopt and " leading and stable code " (DOS) operation strategy under similar state.
B) power operation
Because some equipment or its service cable are positioned at this fire protection space, these equipment probably lost efficacy due to fire.In order to reduce, equipment malfunction is done, clear and definite set state, operator will initiatively cut off the power supply of these equipment, specific to this fire protection space is: the power supply above filling the valves such as equipment and cvcs isolation valve (RCV 010VP, RCV094VP) such as pump house Emergency Venting System blower fan (DVH 001ZV), safety injection system boric acid recirculation pump (RIS 022PO), boron heating system power distribution cabinet (RRB 001TB, 002TB).
C) mark
Marking being subject to influence of fire and disabled function (comprise NSSS function and support function), announcing RCV fills, under let out, the function such as auxiliary spray, high-pressure safety injection, RRA and RCV interface is unavailable.
D) alternative information or designated value
For guarantee information reliability, to being subject to influence of fire, disabled information (comprising condition adjudgement and navigation information) carries out forcing assignment or adopting alternative redundant information, primary Ioops letdown flow information (RCV005MD) is forced to 0, primary Ioops charging stream amount information (RCV 018MD) is forced to 0, peace note flow information (RCV 021MD, 022MD and 023MD) records initial value, uses the RIS 099MD information that RIS 001MD information substitution lost efficacy.
E) recession pattern (namely final safe condition) is determined
If under fire occurs in unit normal operation, then unit recession pattern is that normal shutdown-RRA gets involved, shutdown in the middle of two-phase; If fire occurs in primary Ioops when being full water state, then pattern of dropping back is cold shut RCP system decompression pattern.
F) other disabled equipment, information and false alarm is provided
Except above-mentioned critical function and information, also record other because of fire unavailable device, valve and information, be the unavailable information of the systems such as DVH, KRT, RCV, REA, RIS specific to this fire protection space.
Finally, above-mentioned action is required form a main control room operator working specification in case of fire targetedly.When fire protection space 1ZFSN0280A breaking out of fire, unit, under this code is guided, by calling other relevant code, taking to and maintaining the safe condition of specifying by operator.
Obviously, those skilled in the art can carry out various change and modification to the present invention and not depart from the spirit and scope of the present invention.Like this, if belong within the scope of the claims in the present invention and equivalent technology thereof to these amendments of the present invention and modification, then the present invention is also intended to comprise these change and modification.
Claims (2)
1. under fire condition, nuclear power plant is guided to a method for safe condition, comprise the steps:
(1) combing is carried out to the existing operation of nuclear power plant, malfunction protocol, clean out for the key message that set state judges and code leads;
(2) for each fire protection space, unavailable function, equipment and information that combing fire causes, judge whether fire causes unacceptable consequence;
(3) if fire can not cause unacceptable consequence, then fire is to unit safety function moment-less influence, only takes basic fire extinguishing, rescue action; If fire can cause unacceptable consequence, then enter step (4);
(4) except basic fire extinguishing, rescue action, in order to ensure unit safety, operator performs following operation:
A) foresight operation, puts into operation available redundance unit in advance, and startup corresponding operating arrives the recession pattern of specifying to guide unit as early as possible; Meanwhile, the necessary precautionary measures are taked to prevent the deterioration of set state in advance;
B) power operation, is initiatively cut off the power supply of the nuclear safety relevant device by influence of fire by operator;
C) marking operation, to being subject to influence of fire, disabled function marks;
D) alternative information or designated value operation is provided, due in case of fire will be no longer reliable by influence of fire and disabled information, by the information of its redundancy or determine that alternate parameter is to ensure that unit can be brought into the reliable behavior of specifying by the operation performed by operator in case of fire in advance;
E) determine that recession pattern operates, described recession pattern refers under fire causes the disabled situation of Partial security function, and unit can reach and the acceptable safe condition maintained;
F) record other because of fire disabled equipment, information and false alarm.
2. under fire condition as claimed in claim 1, nuclear power plant is guided to the method for safe condition, it is characterized in that: the unacceptable consequence described in step (2) comprises:
1) one or more support function is completely lost;
2) the foreseeable or reactor emergency shut-down that occurred, the simultaneously inefficacy of the normal operation function of adjoint kernel steam supply system;
3) inefficacy of the normal operation function of nuclear steam supply system may cause event transient state or accident transient state;
4) other unacceptable consequence.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410384452.4A CN104282349B (en) | 2014-08-05 | 2014-08-05 | Nuclear power plant is guided under a kind of fire condition to the method for safe condition |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410384452.4A CN104282349B (en) | 2014-08-05 | 2014-08-05 | Nuclear power plant is guided under a kind of fire condition to the method for safe condition |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104282349A true CN104282349A (en) | 2015-01-14 |
| CN104282349B CN104282349B (en) | 2017-03-15 |
Family
ID=52257157
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410384452.4A Active CN104282349B (en) | 2014-08-05 | 2014-08-05 | Nuclear power plant is guided under a kind of fire condition to the method for safe condition |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104282349B (en) |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106846169A (en) * | 2016-12-20 | 2017-06-13 | 岭东核电有限公司 | A kind of method and device controlled under nuclear power plant's fire condition |
| CN107564595A (en) * | 2017-08-21 | 2018-01-09 | 中广核工程有限公司 | A kind of processing method and system of nuclear power plant's fire operation common mode |
| CN107863168A (en) * | 2017-11-15 | 2018-03-30 | 苏州热工研究院有限公司 | A kind of nuclear power generating sets Power operation loses the recession time series analysis method of ultimate heat sink |
| CN107945897A (en) * | 2017-11-15 | 2018-04-20 | 中广核工程有限公司 | The method and device of Nuclear Power Accident processing |
| CN109235545A (en) * | 2018-10-15 | 2019-01-18 | 上海凯泉泵业（集团）有限公司 | A kind of outdoor type movable type wisdom pump house can be used for emergency repair water supply |
| CN109597393A (en) * | 2018-11-15 | 2019-04-09 | 中国核电工程有限公司 | The design implement method of key security functionality in a kind of nuclear power plant's accident treatment strategy |
| CN112271008A (en) * | 2020-10-26 | 2021-01-26 | 岭澳核电有限公司 | Assessment method for nuclear power plant fire accident safe shutdown path |
| CN112349441A (en) * | 2020-10-27 | 2021-02-09 | 岭澳核电有限公司 | Safety processing method for cable fire misoperation of nuclear power plant |
| CN115050157A (en) * | 2022-06-10 | 2022-09-13 | 中国矿业大学(北京) | Fire control monitor terminal and fire control safety coefficient |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103678795A (en) * | 2013-12-03 | 2014-03-26 | 中国核电工程有限公司 | Method for nuclear power plant flameproof protection analysis |
-
2014
- 2014-08-05 CN CN201410384452.4A patent/CN104282349B/en active Active
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103678795A (en) * | 2013-12-03 | 2014-03-26 | 中国核电工程有限公司 | Method for nuclear power plant flameproof protection analysis |
Non-Patent Citations (5)
| Title |
|---|
| 任兆鹰 等: "核电厂火灾情况下的就地操作研究", 《中国核科学技术进展报告》 * |
| 刘文华 等: "我国运行核电厂的消防安全状况与建议", 《中国土木工程学会工程防火技术分会成立大会暨学术交流会论文集》 * |
| 刘文华: "浅析岭澳核电二期工程消防设计及改进遵循的法规标准及原则", 《机电信息》 * |
| 李向东 等: "核电厂常规岛的消防策略研究", 《中国土木工程学会工程防火技术分会成立大会暨学术交流会论文集》 * |
| 鲁磊 等: "核电厂火灾风险分析及事故应急救援对策", 《中国公共安全-学术版》 * |
Cited By (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106846169A (en) * | 2016-12-20 | 2017-06-13 | 岭东核电有限公司 | A kind of method and device controlled under nuclear power plant's fire condition |
| CN106846169B (en) * | 2016-12-20 | 2020-09-18 | 岭东核电有限公司 | Method and device for controlling nuclear power plant under fire condition |
| CN107564595A (en) * | 2017-08-21 | 2018-01-09 | 中广核工程有限公司 | A kind of processing method and system of nuclear power plant's fire operation common mode |
| CN107564595B (en) * | 2017-08-21 | 2019-07-19 | 中广核工程有限公司 | A kind of processing method and system of nuclear power plant's fire operation common mode |
| CN107945897B (en) * | 2017-11-15 | 2020-07-17 | 中广核工程有限公司 | Method and device for processing nuclear power accidents |
| CN107863168A (en) * | 2017-11-15 | 2018-03-30 | 苏州热工研究院有限公司 | A kind of nuclear power generating sets Power operation loses the recession time series analysis method of ultimate heat sink |
| CN107945897A (en) * | 2017-11-15 | 2018-04-20 | 中广核工程有限公司 | The method and device of Nuclear Power Accident processing |
| CN107863168B (en) * | 2017-11-15 | 2020-04-07 | 苏州热工研究院有限公司 | Method for analyzing withdrawal time of nuclear power unit when power operation loses final heat trap |
| CN109235545A (en) * | 2018-10-15 | 2019-01-18 | 上海凯泉泵业（集团）有限公司 | A kind of outdoor type movable type wisdom pump house can be used for emergency repair water supply |
| CN109235545B (en) * | 2018-10-15 | 2023-08-29 | 上海凯泉泵业（集团）有限公司 | Outdoor movable intelligent pump house for emergency rescue water supply |
| CN109597393A (en) * | 2018-11-15 | 2019-04-09 | 中国核电工程有限公司 | The design implement method of key security functionality in a kind of nuclear power plant's accident treatment strategy |
| CN109597393B (en) * | 2018-11-15 | 2021-03-19 | 中国核电工程有限公司 | Design implementation method for key safety function in accident handling strategy of nuclear power plant |
| CN112271008A (en) * | 2020-10-26 | 2021-01-26 | 岭澳核电有限公司 | Assessment method for nuclear power plant fire accident safe shutdown path |
| CN112349441A (en) * | 2020-10-27 | 2021-02-09 | 岭澳核电有限公司 | Safety processing method for cable fire misoperation of nuclear power plant |
| CN112349441B (en) * | 2020-10-27 | 2022-04-26 | 岭澳核电有限公司 | Safety processing method for cable fire misoperation of nuclear power plant |
| CN115050157A (en) * | 2022-06-10 | 2022-09-13 | 中国矿业大学(北京) | Fire control monitor terminal and fire control safety coefficient |
Also Published As
| Publication number | Publication date |
|---|---|
| CN104282349B (en) | 2017-03-15 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104282349A (en) | Method for guiding nuclear power plant to be safe under condition of fire disaster | |
| CN104538068B (en) | A kind of method that steam generator spill-over is prevented under shape pipe breaking accident operating mode of conducting heat | |
| CN103700411A (en) | Method and system for dealing with loss of coolant accident (LOCA) of nuclear power station | |
| JP2012083231A (en) | Control system of nuclear facility | |
| Yun et al. | Verification of SAMG entry condition for APR1400 | |
| Pavlova et al. | Steam line break investigation at full power reactor for VVER-1000/V320 | |
| CN105551535B (en) | Nuclear power plant containment shell disappears hydrogen system | |
| CN114887254B (en) | Nuclear power plant fire disaster condition nuclear power equipment processing method and device | |
| Parzer et al. | Feed-and-bleed procedure mitigating the consequences of a steam generator tube rupture accident | |
| CN111570070B (en) | Fire extinguishing steam control method, device, equipment and storage medium for medium-speed coal mill | |
| Mazurok et al. | Analytical Justifications As Part of the “Post-Fukushima” Upgrades Implementation on Zaporizhzhya NPP Unit 1 | |
| CN112271008B (en) | Assessment method for nuclear power plant fire accident safe shutdown path | |
| Julin et al. | Insights from PSA Comparison in Evaluation of EPR Designs | |
| Wang et al. | The Safety Analysis of the Design of the Reactor Coolant Pump Heat Shield in Qinshan Nuclear Power Plant | |
| Li et al. | Nuclear Power Plant Design Optimization Based on Risk-Informed Method | |
| Wang et al. | Study on identification of design extension conditions without significant fuel degradation and safety features of nuclear power plant | |
| Oh et al. | Improvement of the Emergency Operating Procedures for Domestic CANDU Plants | |
| Tong et al. | Thermal hydraulic behaviors during loss of RHR system at mid-loop operation of Chinese 300 MWe PWR NPP | |
| Tian et al. | Design characteristics analysis of RTVO for a nuclear power plant | |
| Groudev et al. | Investigation of primary to secondary leakage with loss of primary coolant to the environment through SG SV | |
| Jiang et al. | Analysis of containment pressure control strategy in HPR1000 NPP under severe accidents | |
| Ebersole et al. | An integrated safe shutdown heat removal system for light water reactors | |
| Pingting et al. | Research on Severe Accident Management Guidelines for HPR1000 NPP | |
| Yi et al. | The Emergency Operating Strategy Study of Containment Spray Based on Radiation Level in LBLOCA Condition | |
| Hayashi et al. | Emergency operating procedures (EOPs) for the AP1000 simulator |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |