CN110970141A - Diversity protection system and method for marine nuclear power platform - Google Patents

Diversity protection system and method for marine nuclear power platform Download PDF

Info

Publication number
CN110970141A
CN110970141A CN201811150292.1A CN201811150292A CN110970141A CN 110970141 A CN110970141 A CN 110970141A CN 201811150292 A CN201811150292 A CN 201811150292A CN 110970141 A CN110970141 A CN 110970141A
Authority
CN
China
Prior art keywords
signal
liquid level
steam generator
voltage stabilizer
level signal
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
CN201811150292.1A
Other languages
Chinese (zh)
Inventor
邓峰
刘小瑞
朱增辉
罗捷林
屈建平
吴昊
王慕
陈珊珊
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.)
719th Research Institute of CSIC
Original Assignee
719th Research Institute of CSIC
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 719th Research Institute of CSIC filed Critical 719th Research Institute of CSIC
Priority to CN201811150292.1A priority Critical patent/CN110970141A/en
Publication of CN110970141A publication Critical patent/CN110970141A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a diversity protection system and a method of an ocean nuclear power platform, wherein the diversity protection system comprises a diversity drive cabinet and a diversity drive disc, the diversity drive cabinet comprises a first signal receiving module and a judgment module which are connected with each other, and the diversity drive disc comprises a second signal receiving module which is electrically connected with the judgment module; relates to the technical field of nuclear safety protection of nuclear reactors. The invention can make the reactor of the ocean nuclear power platform and the turbine stop emergently under the condition that the reactor has expected transient state and design benchmark accident and the reactor protection system is invalid, and respectively adopts two paths of signals which are independently collected from the reactor and the reactor protection system to carry out comprehensive judgment, thereby preventing unnecessary shutdown and shutdown caused by signal error and considering the safety, the economy and the reliability of a diversity system.

Description

Diversity protection system and method for marine nuclear power platform
Technical Field
The invention relates to the technical field of nuclear safety protection of nuclear reactors, in particular to a diversity protection system and method of an ocean nuclear power platform.
Background
Under the circumstances of the prominent energy crisis and the environmental deterioration in the world, nuclear energy is increasingly regarded as an important clean energy source. The marine nuclear power platform is a small-sized marine mobile nuclear power station, and compared with a land nuclear power station, the marine mobile small-sized marine mobile nuclear power station has the unique advantage of providing safe and effective energy and fresh water supply to meet the economic development of sea areas. However, the nuclear safety problem cannot be ignored, and how to minimize the potential safety risk while ensuring the full utilization of the advantages of nuclear energy has become a key problem in nuclear power development.
Because of the importance of the functions undertaken by safety-level instrumentation and control systems, HAF102-2004 (Nuclear Power plant design safety rules) regulations dictate that the possibility of common cause failures occurring in safety instrumentation and control systems must be considered to determine where to apply the principles of diversity, multiplicity, and independence to achieve system reliability. An ATWT (Anticipated Transient Without scram Trip) event is an Anticipated Transient in which a control rod cannot be inserted into the core and a scram cannot be achieved due to a common cause failure. Therefore, in order to ensure the safety of the system after a potential common cause fault occurs in the safety level instrument control system, a diversity protection system is required to be arranged. The diversity protection system is a diversity means set for ATWT events, and is a hardware and functional protection measure for the reactor protection system in the event of failure.
When the diversity protection system of a typical three-loop M310 type nuclear power plant normally operates, when the water supply flow of a steam generator is lower than a set value and a reactor operates at a set power level, namely the neutron fluence rate in the middle range is higher than the set value, diversity protection is triggered, and then an auxiliary water supply system is started, the tripping of a steam turbine is triggered, the reactor is shut down, a steam discharge interlock is triggered, and a blowdown isolation valve is closed.
However, the diversity protection system and method for the nuclear power plant cannot be applied to an ocean nuclear power platform, on one hand, the ocean nuclear power platform is different from the nuclear power plant in system configuration, for example, the ocean nuclear power platform is a double loop, and the nuclear power plant is a three loop; on the other hand, the diversity protection system of the nuclear power plant cannot meet the working condition requirements of inclination, swinging, corrosion and the like in the marine environment, and therefore, in order to meet the regulation and actual requirements, a diversity protection system and a method of the marine nuclear power platform need to be designed.
Disclosure of Invention
The invention aims to overcome the defects of the background technology and provide a diversity protection system and a method suitable for an ocean nuclear power platform,
the invention provides a diversity protection method for an ocean nuclear power platform, which comprises the following steps:
receiving a first liquid level signal of a steam generator and a first liquid level signal of a voltage stabilizer sent by a nuclear reactor instrument, and a second liquid level signal of the steam generator and a second liquid level signal of the voltage stabilizer sent by a reactor protection system instrument;
judging whether a steam generator abnormal state signal is generated or not according to the first steam generator liquid level signal and the second steam generator liquid level signal, and judging whether a voltage stabilizer abnormal state signal is generated or not according to the first voltage stabilizer liquid level signal and the second voltage stabilizer liquid level signal;
judging whether a first driving signal, a second driving signal and a third driving signal are generated or not according to the steam generator abnormal state signal and the voltage stabilizer abnormal state signal, wherein the first driving signal is sent to a power supply cabinet and used for controlling shutdown of a reactor; the second driving signal is sent to the steam turbine and used for controlling the shutdown of the steam turbine; and the third driving signal is sent to the waste heat discharging pump and used for controlling the starting of the waste heat discharging pump.
On the basis of the technical scheme, the step of judging whether to generate the steam generator abnormal state signal according to the first liquid level signal and the second liquid level signal of the steam generator is specifically as follows:
and when the first liquid level signal of the steam generator and the second liquid level signal of the steam generator both exceed a set threshold value, generating an abnormal state signal of the steam generator.
On the basis of the technical scheme, the step of judging whether to generate a voltage stabilizer abnormal state signal according to the first liquid level signal and the second liquid level signal of the voltage stabilizer specifically comprises the following steps:
and when the first liquid level signal and the second liquid level signal of the voltage stabilizer both exceed the set threshold, generating an abnormal state signal of the voltage stabilizer.
On the basis of the technical scheme, the set threshold values of the first liquid level signal of the steam generator and the first liquid level signal of the voltage stabilizer are higher than the set threshold values of the second liquid level signal of the steam generator and the second liquid level signal of the voltage stabilizer.
On the basis of the technical scheme, the step of judging whether to generate the first driving signal, the second driving signal and the third driving signal according to the steam generator abnormal state signal and the voltage stabilizer abnormal state signal is specifically as follows:
and if the abnormal state signal of the steam generator and/or the abnormal state signal of the voltage stabilizer are received, generating a first driving signal, a second driving signal and a third driving signal.
The invention also provides a diversity protection system of the marine nuclear power platform, which comprises:
the driving cabinet comprises a first signal receiving module and a judging module which are connected with each other;
the first signal receiving module is used for receiving a first liquid level signal of a steam generator and a first liquid level signal of a voltage stabilizer sent by a nuclear reactor instrument, and a second liquid level signal of the steam generator and a second liquid level signal of the voltage stabilizer sent by a reactor protection system instrument;
the judgment module comprises a first judgment unit and a second judgment unit, the first judgment unit judges whether a steam generator abnormal state signal is generated or not according to the first liquid level signal of the steam generator and the second liquid level signal of the steam generator, and the second judgment unit judges whether a voltage stabilizer abnormal state signal is generated or not according to the first liquid level signal of the voltage stabilizer and the second liquid level signal of the voltage stabilizer;
the judging module further comprises a third judging unit, the third judging unit judges whether to generate a first driving signal, a second driving signal and a third driving signal according to the steam generator abnormal state signal and the voltage stabilizer abnormal state signal, and the first driving signal is sent to the power cabinet and used for controlling the shutdown of the reactor; the second driving signal is sent to the steam turbine and used for controlling the shutdown of the steam turbine; and the third driving signal is sent to the waste heat discharging pump and used for controlling the starting of the waste heat discharging pump.
On the basis of the technical scheme, the diversity protection system further comprises a diversity driving disc, the diversity driving disc comprises a second signal receiving module electrically connected with the judging module, and the second signal receiving module is used for receiving the steam generator abnormal state signal generated by the first judging unit and the voltage stabilizer abnormal state signal generated by the second judging unit.
On the basis of the technical scheme, the diversity driving disc further comprises a steam generator state prompting device and a voltage stabilizer state prompting device which are electrically connected with the second signal receiving module, and when the second signal receiving module receives an abnormal state signal of the steam generator, the steam generator state prompting device gives a prompt; when the second signal receiving module receives the abnormal state signal of the voltage stabilizer, the voltage stabilizer state prompting device prompts.
On the basis of the above technical solution, the diversity driving disc further includes:
a manual trip operator for generating a manual trip signal and transmitting the signal to the power supply cabinet to control a manual trip of the reactor;
a manual shutdown operator for generating a manual shutdown signal and transmitting the signal to the steam turbine to control a manual shutdown of the steam turbine;
a waste heat removal pump controller for generating and sending an activation signal to the waste heat removal pump to control manual activation of the waste heat removal pump.
On the basis of the technical scheme, the diversity driving disc further comprises a chemical reactor shutdown device, the chemical reactor shutdown device comprises an operation button and a boric acid tank, the boric acid tank leads to the reactor through a pipeline, a valve for controlling the opening and closing of the pipeline is arranged on the pipeline, and the operation button is used for generating a chemical reactor shutdown signal to control the opening and closing of the valve.
Compared with the prior art, the invention has the following advantages:
the diversity protection system and the method of the marine nuclear power platform can enable the reactor of the marine nuclear power platform to be shut down emergently, the turbine to be shut down emergently and the waste heat discharge pump to be started to discharge waste heat under the condition that the reactor has expected transient and design basis accidents and the reactor protection system is invalid, and respectively adopt two paths of signals which are independently collected in the reactor and collected in the reactor protection system to carry out comprehensive judgment, thereby preventing unnecessary shutdown and shutdown caused by signal errors; meanwhile, according to the system configuration of the marine nuclear power platform, the evaporator liquid level signal and the voltage stabilizer liquid level signal are monitored simultaneously, the safety protection precision is high, and the system configuration of the marine nuclear power platform is met.
Drawings
FIG. 1 is a block flow diagram of a method of diversity protection for an offshore nuclear power platform according to an embodiment of the present invention;
FIG. 2 is a functional block diagram of a diversity protection system for an offshore nuclear power platform according to an embodiment of the present invention.
Reference numerals: 1-diversity drive cabinet, 11-first signal receiving module, 12-judging module, 2-diversity drive disc, 21-second signal receiving module, 22-steam generator state prompting device, 23-voltage stabilizer state prompting device, 24-manual shutdown operator, 25-manual shutdown operator, 26-waste heat discharge pump controller, and 27-chemical shutdown device.
Detailed Description
The invention is described in further detail below with reference to the figures and the embodiments.
Referring to fig. 1, an embodiment of the present invention provides a diversity protection method for an ocean nuclear power platform, including:
receiving a first liquid level signal of a steam generator and a first liquid level signal of a voltage stabilizer sent by a nuclear reactor instrument, and a second liquid level signal of the steam generator and a second liquid level signal of the voltage stabilizer sent by a reactor protection system instrument;
judging whether a steam generator abnormal state signal is generated or not according to the first steam generator liquid level signal and the second steam generator liquid level signal, and judging whether a voltage stabilizer abnormal state signal is generated or not according to the first voltage stabilizer liquid level signal and the second voltage stabilizer liquid level signal;
judging whether a first driving signal, a second driving signal and a third driving signal are generated or not according to the steam generator abnormal state signal and the voltage stabilizer abnormal state signal, wherein the first driving signal is sent to a power supply cabinet and used for controlling shutdown of a reactor; the second driving signal is sent to the steam turbine and used for controlling the shutdown of the steam turbine; and the third driving signal is sent to the waste heat discharging pump and used for controlling the starting of the waste heat discharging pump.
The diversity protection system and the method of the marine nuclear power platform can enable the reactor of the marine nuclear power platform to be shut down emergently, the turbine to be shut down emergently and the waste heat discharge pump to be started to discharge waste heat under the condition that the reactor has expected transient and design basis accidents and the reactor protection system is invalid, and respectively adopt two paths of signals which are independently collected in the reactor and collected in the reactor protection system to carry out comprehensive judgment, thereby preventing unnecessary shutdown and shutdown caused by signal errors; meanwhile, according to the system configuration of the marine nuclear power platform, the evaporator liquid level signal and the voltage stabilizer liquid level signal are monitored simultaneously, the safety protection precision is high, and the system configuration of the marine nuclear power platform is met.
On the basis of the technical solution of the above embodiment, preferably, the determining whether the steam generator abnormal state signal is generated according to the first liquid level signal of the steam generator and the second liquid level signal of the steam generator specifically includes:
and when the first liquid level signal of the steam generator and the second liquid level signal of the steam generator both exceed a set threshold value, generating an abnormal state signal of the steam generator.
Further, the step of judging whether to generate an abnormal state signal of the voltage stabilizer according to the first liquid level signal and the second liquid level signal of the voltage stabilizer specifically comprises:
and when the first liquid level signal and the second liquid level signal of the voltage stabilizer both exceed the set threshold, generating an abnormal state signal of the voltage stabilizer.
In this embodiment, the first liquid level signal of steam generator, the first liquid level signal of stabiliser all independently gathers in the reactor, steam generator second liquid level signal, stabiliser second liquid level signal all gathers in reactor protection system, and distribute through the signal distribution subassembly that has the isolation function, guarantee the independence between two sets of signals, prevent because signal error causes unnecessary shutdown and shut down, the security of diversity system has been considered, economy and reliability, when having reduced ocean nuclear power platform because of reactor protection system common cause trouble and taking place anticipated transient state and design benchmark accident, the unable shutdown of reactor, the unable shutdown of steam turbine, cause the risk of producing super design benchmark event.
In other embodiments, since the marine nuclear power platform is a dual loop system configuration, the steam generator level signal can be further divided into a left loop steam generator level signal and a right loop steam generator level signal, and the two loop signals are equally divided into two paths, one path of the left loop steam generator first liquid level signal and the right loop steam generator first liquid level signal are collected in the reactor, the other path of the left loop steam generator second liquid level signal and the right loop steam generator second liquid level signal are collected in the reactor protection system, when the first liquid level signal of the left-loop steam generator and the second liquid level signal of the left-loop steam generator both exceed the set threshold, generating an abnormal state signal of the left ring steam generator, and generating an abnormal state signal of the right ring steam generator when the first liquid level signal of the right ring steam generator and the second liquid level signal of the right ring steam generator both exceed a set threshold.
On the basis of the technical solution of the above embodiment, preferably, the threshold set by the first liquid level signal of the steam generator and the first liquid level signal of the voltage stabilizer is higher than the threshold set by the second liquid level signal of the steam generator and the second liquid level signal of the voltage stabilizer; when a design benchmark accident occurs on the marine nuclear power platform, one of the liquid level of the steam generator and the liquid level of the voltage stabilizer is obviously reduced or is simultaneously reduced, the second liquid level signal of the steam generator or the second liquid level signal of the voltage stabilizer of a reactor protection system instrument exceeds a set threshold value, the existing reactor protection system needs to take protection measures to stop the reactor, stop the steam turbine and start the waste heat discharge pump, then the first liquid level signal of the steam generator or the first liquid level signal of the voltage stabilizer of the nuclear reactor instrument is increased back and cannot exceed the set threshold value, and the diversity protection system of the invention cannot be triggered, when the reactor protection system fails and does not take protection measures, one of the liquid level of the steam generator and the liquid level of the voltage stabilizer continues to be reduced or is simultaneously reduced, the first liquid level signal of the steam generator or the first liquid level signal of the voltage stabilizer of the nuclear reactor instrument exceeds the set threshold value, at this time, it can be determined that the existing reactor protection system has failed, no protection measures are taken, and the diversified protection system of the present invention needs to be started.
On the basis of the technical solution of the foregoing embodiment, preferably, the determining whether to generate the first driving signal, the second driving signal, and the third driving signal according to the steam generator abnormal state signal and the regulator abnormal state signal specifically includes:
and if the abnormal state signal of the steam generator and/or the abnormal state signal of the voltage stabilizer are received, generating a first driving signal, a second driving signal and a third driving signal.
In this embodiment, the evaporator liquid level signal and the voltage stabilizer liquid level signal are monitored simultaneously, when a design benchmark accident occurs on the marine nuclear power platform, one of the protection variables, namely the steam generator liquid level and the voltage stabilizer liquid level, which are subjected to safety analysis, is obviously reduced or is simultaneously reduced, when the action threshold of the reactor protection system is reached, the reactor protection system should trigger reactor shutdown, steam turbine shutdown and residual heat removal pump start, namely, a diversity protection system generates a first driving signal, a second driving signal and a third driving signal, and the first driving signal is sent to a power supply cabinet and used for controlling the reactor shutdown; the second driving signal is sent to the steam turbine and used for controlling the shutdown of the steam turbine; and the third driving signal is sent to the waste heat discharging pump and used for controlling the starting of the waste heat discharging pump.
In other embodiments, because the marine nuclear power platform is a dual-loop system configuration, the steam generator level signal can be further divided into a left-loop steam generator level signal and a right-loop steam generator level signal, and the two-loop signals are equally divided into two loops, one loop of the left-loop steam generator first level signal and the right-loop steam generator first level signal are collected in the reactor, the other loop of the left-loop steam generator second level signal and the right-loop steam generator second level signal are collected in the reactor protection system, and then whether the first driving signal, the second driving signal and the third driving signal are generated is judged: and when the abnormal state signal of the left-ring steam generator or the abnormal state signal of the right-ring steam generator or the abnormal state signal of the voltage stabilizer is received, generating a first driving signal, a second driving signal and a third driving signal.
The embodiment of the invention also provides a diversity protection system of the marine nuclear power platform, which comprises the following steps:
the driving cabinet comprises a diversity driving cabinet 1, wherein the diversity driving cabinet 1 comprises a first signal receiving module 11 and a judging module 12 which are connected with each other;
the first signal receiving module 11 is configured to receive a first steam generator liquid level signal and a first voltage stabilizer liquid level signal sent by a nuclear reactor instrument, and a second steam generator liquid level signal and a second voltage stabilizer liquid level signal sent by a reactor protection system instrument;
the judging module 12 includes a first judging unit and a second judging unit, the first judging unit judges whether to generate a steam generator abnormal state signal according to the steam generator first liquid level signal and the steam generator second liquid level signal, and the second judging unit judges whether to generate a voltage stabilizer abnormal state signal according to the voltage stabilizer first liquid level signal and the voltage stabilizer second liquid level signal;
the judging module 12 further includes a third judging unit, which judges whether to generate a first driving signal, a second driving signal and a third driving signal according to the steam generator abnormal state signal and the voltage stabilizer abnormal state signal, wherein the first driving signal is sent to the power cabinet for controlling the shutdown of the reactor; the second driving signal is sent to the steam turbine and used for controlling the shutdown of the steam turbine; and the third driving signal is sent to the waste heat discharging pump and used for controlling the starting of the waste heat discharging pump.
According to the diversity protection system of the marine nuclear power platform, the independent diversity drive cabinet 1 is arranged, the physical isolation from a reactor protection system is ensured, and the drive cabinet 1 realizes the automatic control of reactor shutdown, turbine shutdown and waste heat discharge pump starting.
On the basis of the technical solution of the foregoing embodiment, preferably, the diversity protection system further includes a diversity driving disc 2, the diversity driving disc 2 includes a second signal receiving module 21 electrically connected to the determining module 12, and the second signal receiving module 21 is configured to receive the steam generator abnormal state signal generated by the first determining unit and the regulator abnormal state signal generated by the second determining unit.
Further, the diversity driver board 2 further comprises a steam generator state prompting device 22 and a voltage stabilizer state prompting device 23 electrically connected to the second signal receiving module 21, and when the second signal receiving module 21 receives the steam generator abnormal state signal, the steam generator state prompting device 22 gives a prompt; when the second signal receiving module 21 receives the regulator abnormal state signal, the regulator state prompting device 23 prompts.
In this embodiment, set up steam generator state suggestion device 22 and stabiliser state suggestion device 23 on driving-disc 2 for the liquid level state of monitoring steam generator and stabiliser, when the operating mode takes place that does not stop in the anticipated transient state, obvious reduction can take place through one of safety analysis's protection variable steam generator liquid level, stabiliser liquid level, or reduce simultaneously, through steam generator state suggestion device 22 and stabiliser state suggestion device 23, operating personnel can in time know the unusual operating mode of nuclear power platform, and in time make the processing.
In other embodiments, since the marine nuclear power platform is a dual-loop system configuration, the steam generator status prompting device 22 on the driving disk 2 is further configured to include a left-loop steam generator status prompting device and a right-loop steam generator status prompting device, and when the second signal receiving module 21 receives the abnormal status signal of the left-loop steam generator, the left-loop steam generator status prompting device prompts; when the second signal receiving module 21 receives the abnormal state signal of the right-ring steam generator, the right-ring steam generator state prompting device prompts.
On the basis of the technical solution of the above embodiment, preferably, the diversity driving disc 2 further includes: a manual trip operator 24 for generating and transmitting a manual trip signal to the power supply cabinet to control a manual trip of the reactor;
a manual stop operator 25 for generating a manual stop signal and transmitting the signal to the steam turbine to control a manual stop of the steam turbine;
a waste heat removal pump controller 26 for generating and sending an activation signal to the waste heat removal pump to control manual activation of the waste heat removal pump.
The diversity driving disc 2 is provided with a manual shutdown operator 24, a manual shutdown operator 25 and a waste heat discharge pump controller 26, when the automatic control of reactor shutdown, steam turbine shutdown and a waste heat discharge pump in the diversity driving disc 1 fails, an operator can perform manual shutdown and shutdown waste heat discharge operation according to the prompt of the steam generator state prompt device 22 and the voltage stabilizer state prompt device 23, a manual shutdown signal directly reaches a power supply cabinet of the nuclear power platform, a manual shutdown signal directly reaches an adjusting protection cabinet of the steam turbine, and a waste heat discharge signal directly reaches the waste heat discharge pump, so that the manual operation is not influenced by the automatic control failure, the design concept of depth defense is integrated into the whole diversity protection system, and the system safety, the economy and the reliability are comprehensively considered.
On the basis of the technical solution of the above embodiment, preferably, the diversity driving disc 2 further includes a chemical reactor shutdown device 27, where the chemical reactor shutdown device 27 includes an operation button and a boric acid tank, the boric acid tank leads to the reactor through a pipeline, the pipeline is provided with a valve for controlling the opening and closing of the pipeline, and the operation button is used for generating a chemical reactor shutdown signal to control the opening of the valve.
When the manual shutdown operator 24 also fails or a rod-sticking accident occurs in the reactor, the chemical shutdown device 27 can be used, because the reactor coolant of the nuclear power platform is light water without boric acid, the reactivity of the reactor can be affected after the boric acid is injected into the reactor coolant, the reactor is shut down, the last line of defense for protecting the diversified protection system is also the most effective means, but the reactor needs to be cleaned and overhauled after the accident, so the chemical shutdown device 27 needs to be carefully used, and the manual chemical shutdown device 27 is incorporated into the diversified protection system, so that the system can handle more complex emergency conditions.
Various modifications and variations of the embodiments of the present invention may be made by those skilled in the art, and they are also within the scope of the present invention, provided they are within the scope of the claims of the present invention and their equivalents.
What is not described in detail in the specification is prior art that is well known to those skilled in the art.

Claims (10)

1. A diversity protection method for an ocean nuclear power platform is characterized by comprising the following steps:
receiving a first liquid level signal of a steam generator and a first liquid level signal of a voltage stabilizer sent by a nuclear reactor instrument, and a second liquid level signal of the steam generator and a second liquid level signal of the voltage stabilizer sent by a reactor protection system instrument;
judging whether a steam generator abnormal state signal is generated or not according to the first steam generator liquid level signal and the second steam generator liquid level signal, and judging whether a voltage stabilizer abnormal state signal is generated or not according to the first voltage stabilizer liquid level signal and the second voltage stabilizer liquid level signal;
judging whether a first driving signal, a second driving signal and a third driving signal are generated or not according to the steam generator abnormal state signal and the voltage stabilizer abnormal state signal, wherein the first driving signal is sent to a power supply cabinet and used for controlling shutdown of a reactor; the second driving signal is sent to the steam turbine and used for controlling the shutdown of the steam turbine; and the third driving signal is sent to the waste heat discharging pump and used for controlling the starting of the waste heat discharging pump.
2. The method of claim 1 for diversity protection of an offshore nuclear power platform, comprising: the specific step of judging whether the steam generator abnormal state signal is generated according to the first steam generator liquid level signal and the second steam generator liquid level signal is as follows:
and when the first liquid level signal of the steam generator and the second liquid level signal of the steam generator both exceed a set threshold value, generating an abnormal state signal of the steam generator.
3. The method of claim 2 for diversity protection of an offshore nuclear power platform, comprising: the step of judging whether to generate a voltage stabilizer abnormal state signal according to the first liquid level signal and the second liquid level signal of the voltage stabilizer is specifically as follows:
and when the first liquid level signal and the second liquid level signal of the voltage stabilizer both exceed the set threshold, generating an abnormal state signal of the voltage stabilizer.
4. The method of claim 3 for diversity protection of an offshore nuclear power platform, comprising: the set threshold values of the first liquid level signal of the steam generator and the first liquid level signal of the voltage stabilizer are higher than the set threshold values of the second liquid level signal of the steam generator and the second liquid level signal of the voltage stabilizer.
5. The method of claim 1 for diversity protection of an offshore nuclear power platform, comprising: the method for judging whether to generate the first driving signal, the second driving signal and the third driving signal according to the abnormal state signal of the steam generator and the abnormal state signal of the voltage stabilizer specifically comprises the following steps:
and if the abnormal state signal of the steam generator and/or the abnormal state signal of the voltage stabilizer are received, generating a first driving signal, a second driving signal and a third driving signal.
6. A diversity protection system for an ocean nuclear power platform, comprising:
the driving cabinet comprises a diversity driving cabinet (1), wherein the diversity driving cabinet (1) comprises a first signal receiving module (11) and a judging module (12) which are connected with each other;
the first signal receiving module (11) is used for receiving a first steam generator liquid level signal and a first voltage stabilizer liquid level signal sent by a nuclear reactor instrument, and a second steam generator liquid level signal and a second voltage stabilizer liquid level signal sent by a reactor protection system instrument;
the judging module (12) comprises a first judging unit and a second judging unit, the first judging unit judges whether a steam generator abnormal state signal is generated or not according to the first liquid level signal of the steam generator and the second liquid level signal of the steam generator, and the second judging unit judges whether a voltage stabilizer abnormal state signal is generated or not according to the first liquid level signal of the voltage stabilizer and the second liquid level signal of the voltage stabilizer;
the judging module (12) further comprises a third judging unit, the third judging unit judges whether to generate a first driving signal, a second driving signal and a third driving signal according to the steam generator abnormal state signal and the voltage stabilizer abnormal state signal, and the first driving signal is sent to the power cabinet and used for controlling shutdown of the reactor; the second driving signal is sent to the steam turbine and used for controlling the shutdown of the steam turbine; and the third driving signal is sent to the waste heat discharging pump and used for controlling the starting of the waste heat discharging pump.
7. The diversity protection system for an offshore nuclear power platform of claim 6, wherein: the diversity protection system further comprises a diversity driving disc (2), the diversity driving disc (2) comprises a second signal receiving module (21) electrically connected with the judging module (12), and the second signal receiving module (21) is used for receiving the steam generator abnormal state signal generated by the first judging unit and the voltage stabilizer abnormal state signal generated by the second judging unit.
8. The diversity protection system for an offshore nuclear power platform of claim 7, wherein: the diversity driving disc (2) further comprises a steam generator state prompting device (22) and a voltage stabilizer state prompting device (23) which are electrically connected with the second signal receiving module (21), and when the second signal receiving module (21) receives an abnormal state signal of the steam generator, the steam generator state prompting device (22) gives a prompt; when the second signal receiving module (21) receives the abnormal state signal of the voltage stabilizer, the state prompting device (23) of the voltage stabilizer prompts.
9. A diversity protection system for an offshore nuclear power platform according to claim 7, characterized in that said diversity driver disc (2) further comprises:
a manual trip operator (24) for generating and sending a manual trip signal to the power supply cabinet to control manual trip of the reactor;
a manual shutdown operator (25) for generating a manual shutdown signal and transmitting the signal to the steam turbine to control manual shutdown of the steam turbine;
a waste heat removal pump controller (26) for generating and sending an activation signal to the waste heat removal pump to control manual activation of the waste heat removal pump.
10. The diversity protection system for an offshore nuclear power platform of claim 7, wherein: the diversity driving disc (2) further comprises a chemical reactor shutdown device (27), the chemical reactor shutdown device (27) comprises an operation button and a boric acid tank, the boric acid tank leads to the reactor through a pipeline, a valve for controlling the opening and closing of the pipeline is arranged on the pipeline, and the operation button is used for generating a chemical reactor shutdown signal to control the opening of the valve.
CN201811150292.1A 2018-09-29 2018-09-29 Diversity protection system and method for marine nuclear power platform Pending CN110970141A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201811150292.1A CN110970141A (en) 2018-09-29 2018-09-29 Diversity protection system and method for marine nuclear power platform

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201811150292.1A CN110970141A (en) 2018-09-29 2018-09-29 Diversity protection system and method for marine nuclear power platform

Publications (1)

Publication Number Publication Date
CN110970141A true CN110970141A (en) 2020-04-07

Family

ID=70027626

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201811150292.1A Pending CN110970141A (en) 2018-09-29 2018-09-29 Diversity protection system and method for marine nuclear power platform

Country Status (1)

Country Link
CN (1) CN110970141A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112009658A (en) * 2020-08-31 2020-12-01 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) Nuclear power device integrated control system suitable for ocean nuclear power platform

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20090022929A (en) * 2007-08-31 2009-03-04 두산중공업 주식회사 Component interface module
CN101968974A (en) * 2010-08-09 2011-02-09 中广核工程有限公司 Protecting system of nuclear power station reactor
CN104485142A (en) * 2014-12-08 2015-04-01 中广核工程有限公司 Diversified driving method, diversified driving device and diversified driving system for nuclear power station
CN105448368A (en) * 2015-11-12 2016-03-30 中广核工程有限公司 Nuclear power plant diversity driving system, nuclear power plant diversity driving method and diversity protection system
CN103700414B (en) * 2013-12-10 2017-02-22 中广核工程有限公司 Diversity driving system and method for nuclear power plant

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20090022929A (en) * 2007-08-31 2009-03-04 두산중공업 주식회사 Component interface module
CN101968974A (en) * 2010-08-09 2011-02-09 中广核工程有限公司 Protecting system of nuclear power station reactor
CN103700414B (en) * 2013-12-10 2017-02-22 中广核工程有限公司 Diversity driving system and method for nuclear power plant
CN104485142A (en) * 2014-12-08 2015-04-01 中广核工程有限公司 Diversified driving method, diversified driving device and diversified driving system for nuclear power station
CN105448368A (en) * 2015-11-12 2016-03-30 中广核工程有限公司 Nuclear power plant diversity driving system, nuclear power plant diversity driving method and diversity protection system

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
林诚格: "《非能动安全先进核电厂AP1000》", 31 August 2008 *
王振营,孙钢: "DAS实施关键技术问题分析研究", 《自动化仪表》 *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112009658A (en) * 2020-08-31 2020-12-01 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) Nuclear power device integrated control system suitable for ocean nuclear power platform

Similar Documents

Publication Publication Date Title
US5426681A (en) Boiling water reactor with combined active and passive safety systems
US4584165A (en) Redundant reactivity control system
CN105427911A (en) Control method and control system of PWR nuclear power plant power switching test
CN103700411A (en) Method and system for dealing with loss of coolant accident (LOCA) of nuclear power station
CN104332207A (en) Method for automatically stopping coolant pump under reactor coolant loss accident condition
CN110970141A (en) Diversity protection system and method for marine nuclear power platform
EP2602794B1 (en) Control system for nuclear power plant
CN110415849B (en) Protection system for coping with heat extraction increase superposition SWCCF accident
JP2009176205A (en) Primary risk factor analysis device by sequence tree
CN114694858A (en) Automatic low-pressure full-speed cooling method and system for nuclear power plant unit
Roth-Seefrid et al. Implementation of bleed and feed procedures in Siemens PWRs
GB2537957A (en) Emergency core cooling system of nuclear power plant
JP2922374B2 (en) Nuclear power plant accident response support system
Watanabe Accident sequence precursor analyses for steam generator tube rupture events that actually occurred
Yu et al. Application of PSA Technology in Safe Operation of Nuclear Power Plant
CN114647939B (en) Selection method of diversified protection parameters of marine nuclear power device
Lu et al. Analysis of the tripping and load rejection event caused by single component failure of governor oil pressure device of a large hydropower station
JP3268090B2 (en) Reactor transient mitigation system
TW200910380A (en) Preliminary risk factor analysis device for a sequence tree
Arai et al. US-ABWR design features and FLEX concept for extended loss of AC power events
Zhang et al. Research on Operating Strategy of Total Loss of Essential Service Water System With RHR Not Connected in PWR Unit
Zhang et al. Research on Operating Strategy of Total Loss of Essential Service Water System With RHR Not Connected in PWR Unit
Schweizer et al. Use of PSA Data for the Performance Specification of Safety Control Systems in Nuclear Power Plants
Dingman et al. Core damage frequency prespectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results
Xie et al. Research on periodic test scheme of safety digital control system for nuclear power plant

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
RJ01 Rejection of invention patent application after publication

Application publication date: 20200407

RJ01 Rejection of invention patent application after publication