CN116110631A - Accident handling method and system for small pressurized water reactor - Google Patents

Accident handling method and system for small pressurized water reactor Download PDF

Info

Publication number
CN116110631A
CN116110631A CN202310154551.2A CN202310154551A CN116110631A CN 116110631 A CN116110631 A CN 116110631A CN 202310154551 A CN202310154551 A CN 202310154551A CN 116110631 A CN116110631 A CN 116110631A
Authority
CN
China
Prior art keywords
module
sub
loop
pressurized water
water reactor
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
CN202310154551.2A
Other languages
Chinese (zh)
Inventor
杨庆明
孙茜
陆斌
李力
于爱民
张刚和
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.)
China Nuclear Power Engineering Co Ltd
Original Assignee
China Nuclear Power Engineering Co Ltd
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 China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Priority to CN202310154551.2A priority Critical patent/CN116110631A/en
Publication of CN116110631A publication Critical patent/CN116110631A/en
Pending legal-status Critical Current

Links

Images

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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices

Landscapes

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

Abstract

The invention provides an accident handling method of a small pressurized water reactor, which comprises the following steps: and (3) receiving emergency shutdown signals, diagnosing and processing the small pressurized water reactor accident, monitoring safety function parameters of the small pressurized water reactor, interrupting the diagnosis and processing of the small pressurized water reactor accident after an abnormality occurs in a certain safety function parameter, monitoring the safety function parameters of the small pressurized water reactor, processing the safety function parameter abnormality phenomenon, and continuing to perform the diagnosis and processing of the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor after the safety function parameters are recovered to be normal. The invention can rapidly cope with accidents, timely monitor and find multiple faults, and always ensure functional safety. Meanwhile, the number of regulations is greatly reduced, the interfaces of the regulations are simplified, the friendliness of operators is improved, the number of operators is reduced, and great convenience is brought to digital operation design.

Description

Accident handling method and system for small pressurized water reactor
Technical Field
The invention relates to the technical field of nuclear power safety, in particular to an accident handling method and system for a small pressurized water reactor.
Background
In order to ensure the safety of the nuclear power plant, a series of safety systems and measures are designed on the basis of designing a set of system for maintaining the operation of the nuclear power plant to generate electricity, wherein the safety systems and measures comprise a system for preventing or correcting accidents, a reactor protection system for controlling the development of the accidents, special safety facilities and design extension facilities for relieving the consequences of the accidents. Because of the absolute importance of nuclear safety to the nuclear power plant, on the basis of the design safety and comprehensive safety analysis of a complex normal operation system and an accident response system, the nuclear power plant needs to be designed and equipped with a whole set of operation rules for providing operation instructions for each working condition such as normal operation, expected operation events, accident working conditions and the like of the nuclear power plant so as to ensure the operation safety of the nuclear power plant.
Accident handling regulations, the most complex operating regulations for handling predicted operating events, design basis accidents and over-design basis accidents, emergency operating regulations may be formulated by means of event-oriented, state-oriented or symptom-oriented methods. The event-oriented protocol should make decisions and take action to respond to the event based on the nuclear power plant status associated with the event as predetermined in the design and safety analysis report. In the symptom-oriented protocol, the response measures for an event should be determined according to the symptoms and states (such as safety parameter values and critical safety functions) of the nuclear power plant system.
Currently, most nuclear power plants are large commercial pressurized water reactors, and the accident handling method comprises event guiding, state guiding, symptom guiding and the like. The system configuration and composition of the large commercial pressurized water reactor are complex, the accident regulations are numerous, and the response operation relationship after the accident is complex. For example, the large pressurized water reactor emergency operation regulation system adopting the event guiding method comprises more than 60 regulations such as a support system loss regulation, an abnormality of a nuclear steam supply system, an accident regulation and the like. For the large pressurized water reactor accident handling regulations adopting the symptom guiding method, the total of the optimal recovery regulations and the functional recovery regulations is more than 50, and the jump relation between the regulations after the accident is more complicated.
The novel small pressurized water reactor is of a passive integrated reactor type, an integrated reactor and passive technology is adopted, the safety margin is high, the system setting is simplified, the automatic response of the system is perfect, the accident response time is long, and the operator does not interfere with the system. Compared with a large pressurized water reactor, the potential accident occurrence rate is reduced, the accident spectrum is reduced, and the passive and automatic response is perfect. For example, the integrated reactor eliminates a large LOCA accident of a first loop, eliminates a shaft seal break accident by adopting a shielding reactor coolant pump, adopts passive reactor core emergency cooling, and thus has no complicated operation of an injection pump, adopts a passive waste heat discharging system, and thus does not need operation of a second loop, and adopts a normally open passive containment air cooling system without personnel operation.
Therefore, if a large pressurized water reactor accident handling procedure is adopted for a small pressurized water reactor, the number of procedures is huge, the response operation relationship after the accident is complex, and the method is not consistent with the advancement of the small pressurized water reactor. At the same time, the economics of small pressurized water reactor nuclear power plants are an important challenge, and operator equipment and maintenance of operating procedures are all matters that need to be optimized. Corresponding to the design advancement of the small pressurized water reactor, it is desirable to provide simplified and friendly accident handling procedures for operation of accident conditions to enhance the operational advancement of the small pressurized water reactor nuclear power plant.
Disclosure of Invention
The technical problem to be solved by the invention is to provide an accident handling method of a small pressurized water reactor, which is used for covering basic accident working conditions and multiple faults of the small pressurized water reactor, has the characteristics of simple rule execution and friendly operator, and correspondingly provides a system for realizing the method.
The technical scheme adopted for solving the technical problems of the invention is as follows:
the invention provides an accident handling method of a small pressurized water reactor, which comprises the following steps:
receiving the emergency shutdown signal, diagnosing and treating the small pressurized water reactor accident,
And after the safety function parameters are recovered to be normal, the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor are continuously executed.
Optionally, the diagnosis and treatment of the small pressurized water reactor accident specifically comprises:
monitoring whether a safety signal appears, if so, turning to the next step, and if not, executing a shutdown protection procedure;
judging whether the pressure of the steam generator is abnormal, if so, executing a two-loop cooling loss procedure, and if not, turning to the next step;
judging whether the radioactivity of the secondary side of the SG is abnormal, if so, executing a steam generator heat transfer tube cracking procedure, and if not, turning to the next step;
judging whether the pressure of a loop is abnormal, and if so, executing a loop coolant loss procedure.
Optionally, the executing the shutdown protection procedure specifically includes:
starting a shutdown state check to judge whether the shutdown state is abnormal, if so, executing a reactive abnormal operation, and turning to the next step after finishing, if not, turning to the next step;
Starting a loop system state check to judge whether a loop state is abnormal, if so, executing a loop coolant loss procedure, and turning to the next step if not;
starting a two-loop system operation check to judge whether the two-loop system operation is abnormal, if so, executing a two-loop cooling loss procedure or a steam generator heat transfer tube rupture procedure, and turning to the next step if not;
and (3) evaluating the state of the small pressurized water reactor unit, judging whether the unit is allowed to continue to operate, and if not, executing cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is stopped.
Optionally, the performing a loop coolant loss procedure specifically includes:
judging whether the two-loop system is faulty or broken, if yes, executing two-loop cooling loss procedure or steam generator heat transfer tube breaking procedure, if no, turning to the next step,
regulating the charging flow, judging whether the safety injection stopping condition is met, if yes, stopping safety injection, and performing cooling and depressurization operation on a loop until the small pressurized water reactor enters a cold stop reactor, if not, turning to the next step,
judging whether a loop pressure release valve is partially opened, if so, performing cooling and depressurization operation on a loop until the small pressurized water reactor enters a cold shutdown reactor, if not, turning to the next step,
Executing low-pressure safety injection operation, judging whether a loop pressure release valve is completely opened, if yes, opening the built-in heat exchange water tank for injection, and if no, executing the following operations in sequence: and cooling and depressurizing the first loop, isolating the reactor core water supplementing tank and starting the residual row system.
Optionally, the performing a two-circuit cooling loss procedure specifically includes:
isolating the fault steam generator, judging whether the fault steam generator is complete, if not, executing a steam generator heat transfer tube rupture procedure, and if so, turning to the next step;
adjusting the charging flow;
and judging whether the safety injection stopping condition is met, if so, stopping safety injection, and performing cooling and depressurization operation on a loop until the small pressurized water reactor enters a cold stop reactor, and if not, turning to the previous step.
Optionally, the performing a steam generator heat transfer tube rupture protocol specifically includes:
s1: a faulty steam generator is identified and isolated,
s2: the charging flow is regulated to control the water level of the primary circuit within a preset range,
s3: the spraying system is started to reduce the pressure of a loop,
s4: the temperature of the first loop is reduced,
s5: judging whether the pressure of the loop and the pressure of the fault steam generator are balanced, if not, turning to the step S3, if yes, turning to the step S6,
S6: the spraying system is stopped,
s7: the charging flow is regulated to control the water level of the primary circuit within a preset range,
s8: and judging whether the safety injection stopping condition is met, if so, stopping safety injection, and continuing to perform cooling and depressurization operation on the first loop until the small pressurized water reactor enters the cold stop reactor, and if not, turning to the step S7.
Optionally, the monitoring the safety function parameter of the small pressurized water reactor specifically includes:
a: judging whether the temperature of the outlet of the reactor core is abnormal, if so, executing a reactor core cooling function rule, and continuing to execute the steps of diagnosing and treating the accident of the small pressurized water reactor and monitoring the safety function parameter of the small pressurized water reactor until the temperature of the outlet of the reactor core is recovered to be normal, if not, turning to the step b;
b: judging whether the heat rejection flow is abnormal, if so, executing a heat rejection function rule, and continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor until the heat rejection flow is recovered to be normal, if not, turning to the step c;
c: and c, judging whether the containment pressure is abnormal, if so, executing a containment function rule, and continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor until the containment pressure is recovered to be normal, otherwise, turning to the step a.
Optionally, the performing core cooling function procedure specifically includes:
checking whether the emergency core cooling configuration is perfect, if not, turning to the next step after the emergency core cooling configuration is perfect, if so, turning to the next step,
detecting whether the outlet temperature of the reactor core is abnormal, if so, turning to the next step, if not, ending executing the reactor core cooling function procedure, continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor,
and (3) sequentially executing a loop pressure relief operation and an injection operation of the built-in refueling water tank, and continuously executing the steps of diagnosing and treating the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor after the temperature of the outlet of the reactor core is recovered to be normal.
Optionally, the performing the heat removal function procedure specifically includes:
checking whether the configuration of the heat extraction system is perfect, if not, turning to the next step after the configuration of the heat extraction system is perfect, if so, turning to the next step,
checking the availability of the steam generator, if not, changing or repairing the steam generator, and then turning to the next step, if so,
and successively executing water supply operation of the steam generator and valve operation of the steam system, and continuously executing the steps of diagnosing and treating the accident of the small pressurized water reactor and monitoring the safety function parameters of the small pressurized water reactor after the heat rejection flow is recovered to be normal.
Optionally, the executing the containment function procedure specifically includes:
checking whether the safety shell isolating valve is damaged, if so, turning to the next step after replacing the safety shell isolating valve, if not, turning to the next step,
detecting whether the containment pressure is abnormal, if so, turning to the next step, if not, ending executing the core cooling function procedure, continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor,
and successively executing the containment ventilation operation and the containment cooling operation, and continuing to execute the steps of diagnosing and treating the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor after the containment pressure is recovered to be normal.
The invention also provides an accident handling system of the small pressurized water reactor, which comprises:
the diagnosis subsystem is used for receiving the emergency shutdown signal, diagnosing and processing the small pressurized water reactor accident,
the monitoring subsystem is used for monitoring safety function parameters of the small pressurized water reactor while the diagnosis subsystem works, triggering the diagnosis subsystem to interrupt the step of diagnosing and processing the small pressurized water reactor accident after an abnormality occurs in one safety function parameter, stopping the step of monitoring the safety function parameter of the small pressurized water reactor, and processing the safety function parameter abnormality until the safety function parameter is recovered to be normal, triggering the diagnosis subsystem to continuously execute the step of diagnosing and processing the small pressurized water reactor accident, and simultaneously starting the step of monitoring the safety function parameter of the small pressurized water reactor.
Optionally, the diagnostic subsystem comprises:
a monitoring module for monitoring whether a safety signal appears,
the first execution module is electrically connected with the monitoring module and is used for executing the shutdown protection procedure when the monitoring sub-module monitors that the safety signal does not appear,
the first judging module is electrically connected with the monitoring module and is used for judging whether the pressure of the steam generator is abnormal when the monitoring module monitors that the safety signal appears,
the second execution module is electrically connected with the first judgment module and is used for executing a two-loop cooling loss procedure when the first judgment module judges that the pressure of the steam generator is abnormal,
the second judging module is electrically connected with the first judging module and is used for judging whether the radioactivity of the secondary side of the SG is abnormal or not when the first judging module judges that the pressure of the steam generator is normal,
a third execution module electrically connected with the second judgment module and used for executing the cracking procedure of the heat transfer tube of the steam generator when the second judgment module judges that the radioactivity of the secondary side of the SG is abnormal,
a third judging module electrically connected with the second judging module for judging whether the loop pressure is abnormal or not when the second judging module judges that the radioactivity of the secondary side of the SG is normal,
and the fourth execution module is electrically connected with the third judgment module and is used for executing a loop coolant loss procedure when the third judgment module judges that the loop pressure is abnormal.
Optionally, the first execution module specifically includes:
a shutdown checking sub-module for starting shutdown state checking and judging whether the shutdown state is abnormal,
the reactive operation sub-module is electrically connected with the shutdown inspection sub-module and is used for executing reactive abnormal operation when the shutdown state judgment sub-module judges that the shutdown state is abnormal,
a loop checking sub-module, which is respectively and electrically connected with the shutdown checking sub-module and the reactive operation sub-module and is used for starting a loop system state check to judge whether the loop state is abnormal when the shutdown checking sub-module judges that the shutdown state is normal or after the reactive operation sub-module executes the reactive abnormal operation,
the fourth execution module is also electrically connected with a loop checking sub-module for executing a loop coolant loss procedure when the loop checking sub-module judges that a loop state is abnormal,
the two loop checking sub-modules are respectively and electrically connected with the loop checking sub-module and the fourth execution module and are used for starting the operation check of the two loop systems to judge whether the operation of the two loop systems is abnormal when the loop checking sub-module judges that the loop state is normal or when the loop checking sub-module judges that the loop state is abnormal and the fourth execution module starts the operation check of the two loop systems after the loop checking sub-module finishes the procedure of losing the loop coolant,
The second execution module is also electrically connected with the two-loop inspection sub-module and used for executing the two-loop cooling loss procedure when the two-loop inspection sub-module judges that the two-loop system is abnormal in operation, or the third execution module is also electrically connected with the two-loop inspection sub-module and used for executing the steam generator heat transfer tube rupture procedure when the two-loop inspection sub-module judges that the two-loop system is abnormal in operation,
the evaluation sub-module is respectively and electrically connected with the two-loop checking sub-module, the second execution module and the third execution module and is used for evaluating the state of the small pressurized water reactor unit after the second execution module executes the two-loop cooling loss procedure or the third execution module executes the steam generator heat transfer tube rupture procedure to judge whether the unit is allowed to continue to run when the two-loop checking sub-module judges that the two-loop system is normal in operation or when the two-loop checking sub-module judges that the two-loop system is abnormal in operation,
the first cold shutdown execution sub-module is electrically connected with the evaluation sub-module and is used for stopping safety injection when the evaluation sub-module judges that the unit is not allowed to run continuously, and executing cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shutdown.
Optionally, the fourth execution module specifically includes:
A two-loop judging sub-module for judging whether the two-loop system is failed or broken,
the second execution module is also electrically connected with the two-loop judging sub-module and is used for executing the two-loop cooling losing procedure when the two-loop judging sub-module judges the two-loop system to be faulty or broken, or the third execution module is also electrically connected with the two-loop judging sub-module and is used for executing the steam generator heat transfer tube breaking procedure when the two-loop judging sub-module judges the two-loop system to be faulty or broken,
the first adjusting sub-module is electrically connected with the two-loop judging sub-module and is used for adjusting the charging flow when the two-loop judging sub-module judges that the two-loop system is not failed or broken,
the first safety injection judging sub-module is electrically connected with the first adjusting sub-module and is used for judging whether the safety injection stopping condition is met after the first adjusting sub-module adjusts the charging flow,
the second cold shut-down execution sub-module is electrically connected with the first safety injection judgment sub-module and is used for stopping safety injection when the safety injection judgment sub-module judges that the safety injection stopping condition is met, executing the cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shut down,
the pressure release valve partial opening judging sub-module is electrically connected with the second cold shut-down executing sub-module and is used for judging whether the loop pressure release valve is partially opened or not when the second cold shut-down executing sub-module judges that the safety injection stopping condition is not met,
The second cold shut-down execution sub-module is also electrically connected with the pressure release valve partial opening judging sub-module and is used for stopping safety injection when the pressure release valve partial opening judging sub-module judges that the primary circuit pressure release valve is partially opened, executing the cooling and depressurization operation on the small-sized pressurized water reactor until the small-sized pressurized water reactor is cooled and shut down,
the low-pressure safety injection operation judging submodule is electrically connected with the pressure release valve partial opening judging submodule and is used for executing low-pressure safety injection operation and judging whether the loop pressure release valve is completely opened or not when the pressure release valve partial opening judging submodule judges that the loop pressure release valve is not partially opened,
the built-in heat exchange water tank injection opening sub-module is electrically connected with the low-pressure safety injection operation judging sub-module and is used for opening the built-in heat exchange water tank injection when the low-pressure safety injection operation judging sub-module judges that the primary circuit pressure release valve is completely opened,
the loop cooling operation submodule is electrically connected with the low-pressure safety injection operation judging submodule and is used for executing the following operations in sequence when the low-pressure safety injection operation judging submodule judges that the loop pressure release valve is closed completely: and cooling and depressurizing the first loop, isolating the reactor core water supplementing tank and starting the residual row system.
Optionally, the second execution module specifically includes:
An isolation judging sub-module for isolating the fault steam generator and judging whether the fault steam generator is complete,
the third execution module is also electrically connected with the isolation judgment sub-module and is used for executing the steam generator heat transfer tube rupture procedure when the isolation judgment sub-module judges that the fault steam generator is incomplete,
the second adjusting sub-module is electrically connected with the isolation judging sub-module and is used for adjusting the charging flow when the isolation judging sub-module judges that the fault steam generator is complete,
the second safety injection judging sub-module is electrically connected with the second adjusting sub-module and is used for judging whether the safety injection stopping condition is met after the adjusting module adjusts the upper charging flow,
a third cold shut-down execution sub-module electrically connected with the second safety injection judgment sub-module and used for stopping safety injection when the second safety injection judgment sub-module judges that the safety injection stopping condition is met, executing the cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shut down,
the second regulation submodule is also used for regulating the charging flow when the second safety injection judging submodule judges that the safety injection stopping condition is not met.
Optionally, the third execution module specifically includes:
an identification isolator sub-module for identifying and isolating a faulty steam generator,
A third regulation sub-module electrically connected with the identification and isolation sub-module for regulating the charging flow after the identification and isolation sub-module identifies and isolates the fault steam generator so as to control the water level of the primary circuit within a preset range,
the spraying opening sub-module is electrically connected with the third adjusting sub-module and is used for opening the spraying system after the third adjusting sub-module adjusts the charging flow so as to reduce the pressure of a loop,
a loop cooling sub-module electrically connected with the spray opening sub-module and used for cooling the loop after the spray opening sub-module opens the spray system,
the pressure balance judging sub-module is electrically connected with the loop cooling sub-module and is used for judging whether the loop pressure and the fault steam generator pressure are balanced after the loop cooling sub-module cools the loop,
the spraying stopping sub-module is electrically connected with the pressure balance judging sub-module and is used for closing the spraying system when the pressure balance judging sub-module judges that the pressure of the primary loop is balanced with the pressure of the fault steam generator,
the third regulating sub-module is also electrically connected with the spraying stopping sub-module and is used for regulating the charging flow when the spraying stopping sub-module closes the spraying system so as to control the water level of the primary circuit within a preset range,
The third safety injection judging sub-module is electrically connected with the third regulating sub-module and is used for judging whether the safety injection stopping condition is met after the third regulating sub-module controls the primary circuit water level within a preset range, if not, the third regulating sub-module is triggered to continuously regulate the charging flow,
and the fourth cold shut-down execution sub-module is electrically connected with the third safety injection judgment sub-module and is used for stopping safety injection when the third safety injection judgment sub-module judges that the safety injection stopping condition is met, and executing cooling and pressure reducing operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shut down.
Optionally, the monitoring subsystem specifically includes:
a reactor core outlet temperature judging module for judging whether the reactor core outlet temperature is abnormal,
the reactor core cooling function execution module is respectively and electrically connected with the reactor core outlet temperature judgment module and the diagnosis subsystem and is used for executing reactor core cooling function rules when the reactor core outlet temperature judgment module judges that the reactor core outlet temperature is abnormal, triggering the diagnosis subsystem to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the reactor core outlet temperature is recovered to be normal, triggering the reactor core outlet temperature judgment module to start,
the heat extraction flow judging module is electrically connected with the reactor core outlet temperature judging module and is used for judging whether the heat extraction flow is abnormal or not when the reactor core outlet temperature judging module judges that the reactor core outlet temperature is normal,
The heat rejection function execution module is respectively and electrically connected with the heat rejection flow judgment module, the reactor core outlet temperature judgment module and the diagnosis subsystem and is used for executing the heat rejection function rule when the heat rejection flow judgment module judges that the heat rejection flow is abnormal, triggering the diagnosis subsystem to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the heat rejection flow is recovered to be normal, triggering the reactor core outlet temperature judgment module to start,
the containment pressure judging module is electrically connected with the heat discharge flow judging module and is used for judging whether the containment pressure is abnormal or not when the heat discharge flow judging module judges that the heat discharge flow is normal,
the containment function execution module is respectively and electrically connected with the containment pressure judgment module, the reactor core outlet temperature judgment module and the diagnosis subsystem and is used for executing containment function rules when the containment pressure judgment module judges that the containment pressure is abnormal, triggering the diagnosis subsystem to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the containment pressure is recovered to be normal, triggering the reactor core outlet temperature judgment module to start,
the reactor core outlet temperature judging module is also electrically connected with the containment pressure judging module and used for starting when the containment pressure judging module judges that the containment pressure is normal.
Optionally, the core cooling function execution module specifically includes:
a core cooling configuration checking module for checking whether the emergency core cooling configuration is perfect,
a core cooling configuration perfecting module electrically connected with the core cooling configuration checking module for perfecting the core cooling configuration when the core cooling configuration checking module checks that the emergency core cooling configuration is imperfect,
the reactor core outlet temperature checking module is respectively and electrically connected with the reactor core cooling configuration checking module and the reactor core cooling configuration perfecting module and is used for detecting whether the reactor core outlet temperature is abnormal when the reactor core cooling configuration checking module checks the emergency reactor core cooling configuration perfecting or after the reactor core cooling configuration perfecting module perfects the reactor core cooling configuration,
the reactor core outlet temperature detection module is also respectively and electrically connected with the diagnosis subsystem and the reactor core outlet temperature judgment module and is used for triggering the diagnosis subsystem to continuously execute the steps of diagnosing and treating the small-sized pressurized water reactor accident when the detected reactor core outlet temperature is normal, and triggering the reactor core outlet temperature judgment module to start,
the outlet temperature recovery module is respectively and electrically connected with the reactor core outlet temperature inspection module, the diagnosis subsystem and the reactor core outlet temperature judgment module and is used for sequentially executing a loop pressure relief operation and a built-in refueling water tank injection operation when the reactor core outlet temperature inspection module detects the reactor core outlet temperature abnormality, triggering the diagnosis subsystem to continuously execute the steps of diagnosing and treating the small-sized pressurized water reactor accident after the reactor core outlet temperature is recovered to be normal, and triggering the reactor core outlet temperature judgment module to start.
Optionally, the heat rejection function execution module specifically includes:
a heat extraction system configuration checking module for checking whether the heat extraction system configuration is perfect,
a heat extraction system configuration perfecting module electrically connected with the heat extraction system configuration checking module for perfecting the heat extraction system configuration when the heat extraction system configuration checking module checks that the heat extraction system configuration is imperfect,
a steam generator checking module electrically connected with the heat extraction system configuration checking module and the heat extraction system configuration perfecting module respectively for checking the availability of the steam generator when the heat extraction system configuration checking module checks the heat extraction system configuration perfecting or after the heat extraction system configuration perfecting module perfecting the heat extraction system configuration,
a steam generator recovery module electrically connected with the steam generator inspection module for replacing or repairing the steam generator when the steam generator inspection module inspects that the steam generator is not available,
the heat rejection flow recovery module is respectively and electrically connected with the steam generator checking module, the steam generator recovery module, the diagnosis subsystem and the reactor core outlet temperature judging module and is used for sequentially executing the water supply operation of the steam generator and the valve operation of the steam system when the steam generator checking module checks that the steam generator is available or after the steam generator is replaced or repaired by the steam generator recovery module until the heat rejection flow is recovered to be normal, triggering the diagnosis subsystem to continuously execute the steps of diagnosing and treating the small-sized pressurized water reactor accident and triggering the reactor core outlet temperature judging module to start.
Optionally, the containment function execution module specifically includes:
an isolation valve inspection module for inspecting whether the containment isolation valve is damaged,
an isolation valve replacement module for replacing the containment isolation valve when the isolation valve inspection module inspects the containment isolation valve for damage,
the safety shell pressure detection module is respectively and electrically connected with the isolation valve inspection module and the isolation valve replacement module and is used for detecting whether the safety shell pressure is abnormal when the isolation valve inspection module inspects that the safety shell isolation valve is not damaged or after the isolation valve replacement module replaces the safety shell isolation valve,
the containment pressure detection module is also respectively and electrically connected with the diagnosis subsystem and the reactor core outlet temperature judgment module, and is used for triggering the diagnosis subsystem to continuously execute the steps of diagnosing and treating the small-sized pressurized water reactor accident when the containment pressure detection module detects that the containment pressure is normal, and triggering the reactor core outlet temperature judgment module to start,
the containment pressure recovery module is electrically connected with the containment pressure detection module, the diagnosis subsystem and the reactor core outlet temperature judgment module respectively and is used for sequentially executing containment ventilation operation and containment cooling operation when the containment pressure detection module detects that the containment pressure is abnormal, triggering the diagnosis subsystem to continuously execute the steps of diagnosing and treating the small-sized pressurized water reactor accident after the containment pressure is recovered to be normal, and triggering the reactor core outlet temperature judgment module to start.
The invention provides a monitoring and function guiding accident handling regulation method based on the characteristics and accident characteristics of a small pressurized water reactor system, which covers the basic accident working condition and multiple faults of the small pressurized water reactor, reflects the safety and non-activity of the small pressurized water reactor and meets the comprehensive requirement of the accident working condition on the regulation. The method not only meets the effective effect on the combination of the common accident handling method and the effective function safety guarantee of the event, but also simplifies the design of the accident handling rules. By the accident handling method based on monitoring and function guiding, accidents can be rapidly handled, multiple faults can be timely monitored and found, and function safety is always guaranteed. Meanwhile, the number of regulations is greatly reduced, the interfaces of the regulations are simplified, the friendliness of operators is improved, the number of operators is reduced, and great convenience is brought to digital operation design.
Drawings
FIG. 1 is a flow chart of an accident handling method for a small pressurized water reactor according to embodiment 1 of the present invention;
FIG. 2 is a flow chart for diagnosing and treating a small pressurized water reactor accident;
FIG. 3 is a flow chart of performing a shutdown protection procedure;
FIG. 4 is a flow chart of performing a loop coolant loss procedure;
FIG. 5 is a flow chart for performing a two-circuit loss of cooling procedure;
FIG. 6 is a flow chart of performing a steam generator heat transfer tube rupture protocol;
FIG. 7 is a flow chart for monitoring safety function parameters of a small pressurized water reactor;
FIG. 8 is a block diagram of an accident handling system for a small pressurized water reactor according to embodiment 2 of the present invention;
FIG. 9 is a block diagram of a diagnostic subsystem;
FIG. 10 is a block diagram of a first execution module;
FIG. 11 is a block diagram of a fourth execution module;
FIG. 12 is a block diagram of a second execution module;
FIG. 13 is a block diagram of a third execution module;
FIG. 14 is a block diagram of a monitoring subsystem;
FIG. 15 is a block diagram of a core cooling function execution module;
FIG. 16 is a block diagram of a heat rejection function execution module;
fig. 17 is a block diagram of a containment function execution module.
Detailed Description
The following description of the embodiments of the present invention will be made more apparent, and the embodiments described in detail, but not necessarily all, in connection with the accompanying drawings. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to fall within the scope of the invention.
In the description of the present invention, it should be noted that the orientation or positional relationship indicated by "upper" or the like is based on the orientation or positional relationship shown in the drawings, and is merely for convenience and simplicity of description, and is not meant to indicate or imply that the apparatus or element to be referred to must be provided with a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, the terms "first," "second," and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "connected," "configured," "mounted," "secured," and the like are to be construed broadly and may be either fixedly connected or detachably connected, or integrally connected, for example; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention will be understood by those skilled in the art in specific cases.
The invention provides an accident handling method of a small pressurized water reactor, which comprises the following steps:
receiving the emergency shutdown signal, diagnosing and treating the small pressurized water reactor accident,
and after the safety function parameters are recovered to be normal, the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor are continuously executed.
The invention also provides an accident handling system of the small pressurized water reactor, which comprises:
the diagnosis subsystem is used for receiving the emergency shutdown signal, diagnosing and processing the small pressurized water reactor accident,
the monitoring subsystem is used for monitoring safety function parameters of the small pressurized water reactor while the diagnosis subsystem works, triggering the diagnosis subsystem to interrupt the step of diagnosing and processing the small pressurized water reactor accident after an abnormality occurs in one safety function parameter, stopping the step of monitoring the safety function parameter of the small pressurized water reactor, and processing the safety function parameter abnormality until the safety function parameter is recovered to be normal, triggering the diagnosis subsystem to continuously execute the step of diagnosing and processing the small pressurized water reactor accident, and simultaneously starting the step of monitoring the safety function parameter of the small pressurized water reactor.
Example 1:
as shown in fig. 1, the embodiment proposes an accident handling method for a small pressurized water reactor, including:
receiving the emergency shutdown signal, diagnosing and treating the small pressurized water reactor accident,
and simultaneously monitoring safety function parameters of the small pressurized water reactor, after an abnormality occurs in a certain safety function parameter, interrupting the diagnosis and treatment of the small pressurized water reactor accident, simultaneously monitoring the safety function parameter of the small pressurized water reactor, treating the safety function parameter abnormality phenomenon, and continuously executing the diagnosis and treatment of the small pressurized water reactor accident until the safety function parameter is recovered to be normal, and simultaneously monitoring the safety function parameter of the small pressurized water reactor.
As shown in fig. 2, in this embodiment, diagnosis and treatment of a small pressurized water reactor accident specifically includes:
monitoring whether a safety signal appears, if so, turning to the next step, and if not, executing a shutdown protection procedure;
judging whether the pressure of the steam generator is abnormal, if so, executing a two-loop cooling loss procedure, and if not, turning to the next step;
judging whether the radioactivity of the secondary side of the SG is abnormal, if so, executing a steam generator heat transfer tube cracking procedure, and if not, turning to the next step;
judging whether the pressure of a loop is abnormal, and if so, executing a loop coolant loss procedure.
As shown in fig. 3, in this embodiment, a shutdown protection procedure is executed, which specifically includes:
starting a shutdown state check to judge whether the shutdown state is abnormal, if so, executing a reactive abnormal operation, and turning to the next step after finishing, if not, turning to the next step;
starting a loop system state check to judge whether a loop state is abnormal, if so, executing a loop coolant loss procedure, and turning to the next step if not;
starting a two-loop system operation check to judge whether the two-loop system operation is abnormal, if so, executing a two-loop cooling loss procedure or a steam generator heat transfer tube rupture procedure, and turning to the next step if not;
And (3) evaluating the state of the small pressurized water reactor unit, judging whether the unit is allowed to continue to operate, and if not, executing cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is stopped.
As shown in fig. 4, in this embodiment, a loop coolant loss procedure is performed, which specifically includes:
judging whether the two-loop system is faulty or broken, if yes, executing two-loop cooling loss procedure or steam generator heat transfer tube breaking procedure, if no, turning to the next step,
regulating the charging flow, judging whether the safety injection stopping condition is met, if yes, stopping safety injection, and performing cooling and depressurization operation on a loop until the small pressurized water reactor enters a cold stop reactor, if not, turning to the next step,
judging whether a loop pressure release valve is partially opened, if so, performing cooling and depressurization operation on a loop until the small pressurized water reactor enters a cold shutdown reactor, if not, turning to the next step,
executing low-pressure safety injection operation, judging whether a loop pressure release valve is completely opened, if yes, opening the built-in heat exchange water tank for injection, and if no, executing the following operations in sequence: and cooling and depressurizing the first loop, isolating the reactor core water supplementing tank and starting the residual row system.
As shown in fig. 5, in this embodiment, a two-circuit cooling loss procedure is performed, which specifically includes:
Isolating the fault steam generator, judging whether the fault steam generator is complete, if not, executing a steam generator heat transfer tube rupture procedure, and if so, turning to the next step;
adjusting the charging flow;
and judging whether the safety injection stopping condition is met, if so, stopping safety injection, and performing cooling and depressurization operation on a loop until the small pressurized water reactor enters a cold stop reactor, and if not, turning to the previous step.
As shown in fig. 6, in this embodiment, a steam generator heat transfer tube rupture procedure is performed, specifically including:
s1: a faulty steam generator is identified and isolated,
s2: the charging flow is regulated to control the water level of the primary circuit within a preset range,
s3: the spraying system is started to reduce the pressure of a loop,
s4: the temperature of the first loop is reduced,
s5: judging whether the pressure of the loop and the pressure of the fault steam generator are balanced, if not, turning to the step S3, if yes, turning to the step S6,
s6: the spraying system is stopped,
s7: the charging flow is regulated to control the water level of the primary circuit within a preset range,
s8: and judging whether the safety injection stopping condition is met, if so, stopping safety injection, and continuing to perform cooling and depressurization operation on the first loop until the small pressurized water reactor enters the cold stop reactor, and if not, turning to the step S7.
As shown in fig. 7, in this embodiment, the monitoring of the safety function parameters of the small pressurized water reactor specifically includes:
a: judging whether the temperature of the outlet of the reactor core is abnormal, if so, executing a reactor core cooling function rule, and continuing to execute the steps of diagnosing and treating the accident of the small pressurized water reactor and monitoring the safety function parameter of the small pressurized water reactor until the temperature of the outlet of the reactor core is recovered to be normal, if not, turning to the step b;
b: judging whether the heat rejection flow is abnormal, if so, executing a heat rejection function rule, and continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor until the heat rejection flow is recovered to be normal, if not, turning to the step c;
c: and c, judging whether the containment pressure is abnormal, if so, executing a containment function rule, and continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor until the containment pressure is recovered to be normal, otherwise, turning to the step a.
In this embodiment, the core cooling function procedure is executed, specifically including:
checking whether the emergency core cooling configuration is perfect, if not, turning to the next step after the emergency core cooling configuration is perfect, if so, turning to the next step,
Detecting whether the outlet temperature of the reactor core is abnormal, if so, turning to the next step, if not, ending executing the reactor core cooling function procedure, continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor,
and (3) sequentially executing a loop pressure relief operation and an injection operation of the built-in refueling water tank, and continuously executing the steps of diagnosing and treating the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor after the temperature of the outlet of the reactor core is recovered to be normal.
In this embodiment, the executing the heat removal function procedure specifically includes:
checking whether the configuration of the heat extraction system is perfect, if not, turning to the next step after the configuration of the heat extraction system is perfect, if so, turning to the next step,
checking the availability of the steam generator, if not, changing or repairing the steam generator, and then turning to the next step, if so,
and successively executing water supply operation of the steam generator and valve operation of the steam system, and continuously executing the steps of diagnosing and treating the accident of the small pressurized water reactor and monitoring the safety function parameters of the small pressurized water reactor after the heat rejection flow is recovered to be normal.
In this embodiment, the containment function procedure is executed, specifically including:
Checking whether the safety shell isolating valve is damaged, if so, turning to the next step after replacing the safety shell isolating valve, if not, turning to the next step,
detecting whether the containment pressure is abnormal, if so, turning to the next step, if not, ending executing the core cooling function procedure, continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor,
and successively executing the containment ventilation operation and the containment cooling operation, and continuing to execute the steps of diagnosing and treating the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor after the containment pressure is recovered to be normal.
In summary, the accident handling procedures of the small and medium-sized pressurized water reactor comprise diagnosis and monitoring procedures, a plurality of event procedures and a plurality of functional procedures.
The event procedure takes typical transient events in a small pressurized water reactor as a basic sequence, and rapid monitoring and recovery actions are designed in a targeted manner. The event regulation takes the automatic response of the monitoring and correcting unit as a main body, and is designed with the control and relief operation of the running state of the system and the unit. According to different accident phenomena and grades, the accident procedures are divided into a shutdown protection procedure, a primary loop coolant loss procedure, a secondary loop cooling loss procedure and a steam generator heat transfer tube rupture procedure.
The functional rules are mainly used for monitoring and controlling safety functions and are used for coping with the situation of functional degradation caused by possible multiple faults. The functional protocol is designed with a recovery operation for performing the function. According to the importance and grade of the safety function, the functional regulations are divided into a reactor core cooling functional regulation, a heat exhausting functional regulation and a containment functional regulation. There is a sequential relationship between these functional protocols, guided by diagnostic and monitoring protocols.
The accident handling procedure method and system of the small pressurized water reactor will be specifically described with respect to procedure composition in the accident handling procedure.
1) Diagnostic and monitoring protocol
The diagnosis and monitoring procedure comprises a diagnosis sub-procedure and a monitoring sub-procedure, which respectively consist of diagnosis logic and monitoring logic. After the accident, the diagnosis logic is executed first to conduct the guidance of the accident procedure.
After the diagnosis of the sub-protocol is completed, the accident type and the coping strategy are identified, at this time, the sub-protocol can be monitored simultaneously to take effect, the monitoring logic is started to be executed circularly, and the safety function parameters are checked to find out the superposition faults. Faults generated by superposition can be of the types of equipment faults, human errors and the like, and can be applied to the reactor and the safety system and reflected as insufficient cooling of the reactor core, abnormal waste heat discharge and abnormal containment state. And if the safety function parameter is found to exceed the limit value, executing the function procedure according to the priority relation to perform the function recovery operation.
As shown in fig. 2, the diagnostic information includes: shutdown signal, safety signal, primary loop pressure, secondary loop pressure, steam generator radioactivity.
As shown in fig. 7, the monitoring information includes: core outlet temperature, heat rejection flow, containment pressure.
The diagnosis and monitoring procedure is an entry procedure of the accident handling procedure of the small pressurized water reactor, is a guiding procedure of the accident handling procedure, and is used for guiding to an event procedure and a functional procedure corresponding to the accident situation. That is, the diagnosis can be performed through the basic phenomena of the accident type, and the appropriate event rules are led in, wherein the phenomena or symptoms comprise emergency shutdown, safety signals and system state characteristics; and the safety function parameters can be used as continuous monitoring objects, and the safety function parameters are guided into proper functional regulations according to the importance degree to perform function recovery, wherein the functional parameters comprise core temperature, heat extraction flow, containment pressure and the like.
After the accident happens, a diagnosis sub-rule is firstly entered to carry out automatic action check, accident diagnosis and accident guidance of the unit. The automatic action check of the unit comprises a reactor check, a steam turbine check, a primary loop operation check, a secondary loop operation check and a safety system check. The accident diagnosis is firstly two-loop pressure and radioactivity state diagnosis, and secondly one-loop water level and pressure state diagnosis. Based on the combination of the automatic action check result and the diagnostic signal, the accident is identified and directed to the appropriate incident procedure.
The monitoring sub-routine takes effect in the execution of the event routine after the diagnostic sub-routine is completed. If the continuously monitored function parameter exceeds the limit value, the method is preferentially guided to the function procedure, the investigation is carried out according to the function procedure, the abnormal function is recovered, and then the method returns to the executing event procedure.
2) Shutdown protection protocol
The shutdown protection protocol is one of the event protocols, and provides operation guidance for an operator for automatic emergency shutdown action confirmation, stable operation of a nuclear steam supply system and failure of an emergency shutdown transient state. The procedure mainly aims at various second-class events caused by faults of various systems of the small pressurized water reactor nuclear power plant, and mainly comprises shutdown state inspection, primary loop, secondary loop and auxiliary system inspection, and stable operation and withdrawal operation of a unit. The protocol also envelopes incidents that respond to reactive anomalies, as well as anticipated transient incidents that fail to scram.
As shown in fig. 3, the shutdown protection procedure is a shutdown state check, a loop system state check, an auxiliary system operation check, a two loop system operation check, a unit steady operation, and an operation of reducing the temperature and the pressure to the cold shutdown.
Shutdown status checks, including control rod status checks, neutron flux checks, and reactive function checks.
A loop system status check comprising: checking the normal pressure water level of the pressure stabilizer, checking the normal operation of the main pump, and checking the integrity of a loop boundary. If a circuit boundary condition is abnormal, then the process is directed to a "circuit coolant loss routine".
Auxiliary system operation checking, comprising: checking a factory power system, adjusting a chemical and volume control system and operating a device cooling water system.
A two-loop system operation check comprising: and (5) checking a passive redundant array system, operating a main water supply system and a steam system, and checking faults of a two-loop system. Wherein the two-circuit system failure check includes content directed to a two-circuit breach or steam generator heat transfer tube rupture protocol.
If a fault or accident has been ascertained, the unit condition allows continued operation, the unit is stabilized in a hot shut down condition. If the faults or accidents still affect the safety of the unit, the unit is withdrawn to the cold shutdown stack for power plant recovery.
3) One-circuit coolant loss protocol
The loop coolant loss procedure serves as an incident procedure and provides an operator with an operation guidance for emergency cooling of the reactor after loop breach, safety system response and withdrawal of the reactor system to a safe state. The procedure aims at coping with primary loop boundary breakage accidents such as coolant leakage, small break and medium break accidents of a small pressurized water reactor, and mainly comprises core safety monitoring, safety system optimization operation, system isolation, primary loop cooling and secondary loop depressurization operation and long-term operation after the accidents.
The one-circuit coolant loss protocol is used to cope with various types of one-circuit boundary breach incidents, different types of leakage or breach incidents, and different treatment strategies, as shown in fig. 4. The procedure includes checking the fault or rupture of the two-loop system, regulating the charging flow, safe injection, cooling and depressurization of the loop, checking the pressure relief system of the loop, low-pressure injection, circulation and other operations.
After entering the procedure, firstly checking whether a two-circuit superposition accident exists, if the two-circuit water supply is lost or broken, switching to a two-circuit cooling loss procedure, and if the two-circuit radioactivity exists, switching to a steam generator heat transfer tube breaking procedure.
Secondly, performing safety injection operation inspection, stopping safety injection if the safety state of the reactor core is restored, performing loop cooling and depressurization through the passive residual row, and transitioning to cold shutdown.
And (3) according to the automatic action condition of the primary circuit pressure relief system, carrying out low-pressure safety injection of the residual pump or opening the built-in refueling water tank for injection, and transiting to long-term cooling.
4) Two-circuit cooling loss protocol
The two-loop cooling loss procedure is used as an event procedure to provide operation guidance for the fault isolation and operation of the two-loop system after the two-loop cooling loss or boundary breach, the response of the safety system and the back-off of the reactor system to a safe state for an operator. The procedure aims at coping with two-loop water supply faults and break-open accidents of a small pressurized water reactor, and two-loop steam faults and break-open accidents. The protocol also envelopes the handling of passive waste heat removal system failure incidents.
The procedure includes fault steam generator isolation, steam generator integrity check, check of passive redundant array system operation, maintenance of primary loop water level, stopping safety injection, primary loop cooling and depressurization, and transition to cold shutdown. As shown in fig. 5.
In this procedure, the steam generator with water supply lost or broken pipeline is isolated first, and the water supply valve and the steam valve are closed. And secondly, checking the integrity of the heat transfer pipe of the steam valve generator to check the superposition fault of the two loops.
Further, the operation of the passive redundancy system is checked based on the failure condition of the steam generator. And under the condition that the heat removal is ensured, the charging and filling operation is performed according to the water level of the primary circuit. And then, continuously cooling and depressurizing to bring the reactor into a cold shutdown reactor.
5) Steam generator heat transfer tube rupture protocol
The steam generator heat transfer tube rupture protocol serves as an incident protocol to provide operator operational guidance for faulty steam generator isolation, two-circuit radioactive leak limiting, safety system response, and reactor system back-off to a safe state. The procedure aims at coping with the rupture of the heat transfer tube of the modular direct current steam generator and the superposition accident thereof.
The steam generator heat transfer tube rupture protocol is used to address steam generator heat transfer tube rupture accidents. As shown in fig. 6, the protocol includes fault steam generator isolation, loop water level control, loop depressurization to equalize pressure, stop safe injection, loop depressurization, and transition to cold shut down.
In this procedure, the broken steam generator is first identified and isolated based on the two-circuit radioactivity parameter. And secondly, adjusting the charging flow to maintain the primary circuit water filling quantity. The most important depressurization operation is performed by spraying to depressurize the first loop so as to reduce leakage to the second loop. Further, the safety injection operation, the temperature reduction and the pressure reduction operation are carried out according to the condition of a loop so as to transition to the cold shutdown.
6) Reactor core cooling function protocol
The core cooling function rule is used as a function rule of a first priority, takes abnormal core coolant temperature in the monitoring sub-rule as an entering parameter, and takes emergency cooling multiple faults during accidents as main targets. The emergency cooling multiple faults comprise safe driving logic faults, valve faults, misoperation and the like. The functional code provides the recovery operation guidance of the potential emergency cooling system fault or personnel error situation, and comprises the operations of recovering the core water supplementing tank injection, recovering the safe injection tank injection, recovering the built-in refueling water tank injection and the like, and recovering the core cooling function so as to assist the incident code to continuously process the accident.
In the cycle monitoring of the diagnostic and monitoring protocol, if the core outlet temperature is found to be abnormally high, the core cooling function protocol is entered. The core cooling function protocol includes emergency core cooling configuration checking, core outlet temperature checking, primary circuit pressure relief operation, built-in refueling water tank injection operation. After the core cooling function schedule is completed, if the core outlet temperature is reduced, the original event schedule is returned to, for example, a shutdown protection schedule, a loop coolant loss schedule, a secondary loop cooling loss schedule and a steam generator heat transfer tube rupture schedule. If the core outlet temperature is still high, the guidance is to the severe accident management guidance.
7) Heat removal function protocol
The heat removal function rule is used as a function rule of a second priority, the abnormal flow and pressure of the heat removal system in the monitoring sub-rule is used as an entering parameter, and the multiple faults of the heat removal system during the accident are used as main targets. The functional regulation provides a recovery operation guidance of passive heat removal, secondary side heat removal of a direct-current evaporator and other means, and comprises the operations of recovering passive valves, recovering water supply system configuration, recovering steam system configuration and the like, recovering waste heat leading-out functions, and specially coping with multiple faults possibly occurring in a series of heat removal and cooling systems in the event regulation.
In the cycle monitoring of the diagnosis and monitoring procedure, if the flow rate and the pressure of the heat extraction system are abnormal, the heat extraction function procedure is entered. The heat rejection function protocol includes heat rejection system configuration checks, steam generator availability checks, steam generator feedwater operation, steam system valve operation. After the heat rejection function protocol is completed, if the heat rejection system flow or pressure is restored, the process returns to the ongoing event protocol, such as shutdown protection protocol, loop coolant loss protocol, two-loop cooling loss protocol, steam generator heat transfer tube rupture protocol.
8) Containment function protocol
The containment function rule is used as a function rule with a third priority, the abnormal containment state of the monitoring sub-rule is used as an entry parameter, and the pressure and radioactivity abnormality of the containment during an accident are used as main targets. The functional code provides operational guidance for containment isolation, containment mixing, containment cooling, etc. to independently address containment barrier threats caused by loss of primary and secondary coolant.
In the cyclic monitoring of the diagnostic and monitoring protocol, if a containment pressure anomaly is found, the containment function protocol is entered. The containment function protocol includes containment isolation valve inspection, containment atmospheric monitoring, containment venting operations, containment cooling operations. After the containment function protocol is completed, if the containment pressure drops, the process returns to the event protocol being performed, such as shutdown protection protocol, primary loop coolant loss protocol, secondary loop cooling loss protocol, steam generator heat transfer tube rupture protocol.
Execution sequence of functional procedure
Due to uncertainty and complexity of multiple faults during an accident, two or three of the core cooling function, the heat rejection function and the containment function may be challenged at the same time, and then the two or three functions are executed sequentially according to the sequence specified in the diagnosis and monitoring rules. If the function parameter with higher priority is abnormal when executing a certain function procedure, executing the function procedure first to finish, and then executing other function procedures.
The invention has the following application effects:
1. the conventional accident handling regulation method of the nuclear power plant is mainly applied to a large pressurized water reactor with complex system composition, and fills the gap of the simplified accident handling regulation method and system in the field for a small pressurized water reactor integrating passive safety and an integrated reactor.
2. The accident handling rules combining events and functions are closely combined with the safety characteristics of the small pressurized water reactor, cover all accident working conditions of the small pressurized water reactor, provide a set of programming method for ensuring the running safety of the small pressurized water reactor, provide a matched solution for popularization and application of the small pressurized water reactor, and promote the safety and advancement of the small pressurized water reactor.
3. The accident handling procedure method and the system adopt a method combining event guidance and function recovery, refer to the experience of the accident handling procedure of the nuclear power plant at home and abroad, provide a perfect solution, not only can rapidly cope with the accident, but also can cope with the superposition working condition, ensure the safety of the reactor at multiple levels, meet the completeness requirement of the modern accident procedure of the nuclear power plant, and solve the limitations of the accident guidance method and the system complexity problem of the symptom guidance method.
4. The accident handling procedure method is simplified, the concept meaning is clear, the logic is clear, the procedure composition is simple, the procedure number is simple, the operability is good, and the operator friendliness advantage is outstanding.
5. By the application of the method, personnel tasks of the small pressurized water reactor nuclear power plant can be reduced, the pressure of operators is reduced, the configuration and the team of the operators are improved, and the running economy of the small pressurized water reactor is improved.
6. The method is very favorable for further developing the digital accident handling rules and improving the digital and intelligent operation level of the small pressurized water reactor.
Example 2:
as shown in fig. 8, the present embodiment provides an accident handling system for a small pressurized water reactor, including:
a diagnosis subsystem 1 for receiving the emergency shutdown signal, diagnosing and treating the small pressurized water reactor accident,
the monitoring subsystem 2 is used for monitoring safety function parameters of the small pressurized water reactor while the diagnosis subsystem 1 works, triggering the diagnosis subsystem 1 to interrupt the step of diagnosing and processing the small pressurized water reactor accident after an abnormality occurs in a certain safety function parameter, stopping the step of monitoring the safety function parameter of the small pressurized water reactor, processing the safety function parameter abnormality phenomenon, triggering the diagnosis subsystem 1 to continuously execute the step of diagnosing and processing the small pressurized water reactor accident until the safety function parameter is recovered to be normal, and simultaneously starting the step of monitoring the safety function parameter of the small pressurized water reactor.
As shown in fig. 9, in the present embodiment, the diagnostic subsystem 1 includes:
a monitoring module 11 for monitoring whether a safety signal is present,
the first execution module 12 is electrically connected with the monitoring module 11 and is used for executing the shutdown protection procedure when the monitoring sub-module monitors that no safety signal exists,
a first judging module 13 electrically connected with the monitoring module 11 for judging whether the pressure of the steam generator is abnormal when the monitoring module 11 detects the occurrence of the safety signal,
the second execution module 14 is electrically connected with the first judgment module 13 and is used for executing a two-loop cooling loss procedure when the first judgment module 13 judges that the pressure of the steam generator is abnormal,
a second judging module 15 electrically connected to the first judging module 13 for judging whether the radioactivity of the secondary side of the SG is abnormal or not when the first judging module 13 judges that the pressure of the steam generator is normal,
a third execution module 16 electrically connected with the second judgment module 15 for executing a steam generator heat transfer tube rupture procedure when the second judgment module 15 judges that the SG secondary side radioactivity is abnormal,
a third judging module 17 electrically connected to the second judging module 15 for judging whether the primary circuit pressure is abnormal when the second judging module 15 judges that the radioactivity of the secondary side of the SG is normal,
The fourth execution module 18 is electrically connected to the third judgment module 17, and is configured to execute a loop coolant loss procedure when the third judgment module 17 judges that the loop pressure is abnormal.
As shown in fig. 10, in this embodiment, the first execution module 12 specifically includes:
a shutdown checking sub-module 121 for starting a shutdown status check, and judging whether the shutdown status is abnormal,
a reactive operation sub-module 122 electrically connected to the shutdown checking sub-module 121 for performing a reactive abnormal operation when the shutdown status determination sub-module determines that the shutdown status is abnormal,
a loop checking sub-module 123 electrically connected to the shutdown checking sub-module 121 and the reactive operation sub-module 122, respectively, for starting a loop system status check to determine whether a loop status is abnormal when the shutdown status is determined to be normal by the shutdown checking sub-module 121 or after the reactive operation sub-module 122 performs the reactive abnormal operation,
the fourth execution module 18 is also electrically connected to a circuit check sub-module 123 for executing a circuit coolant loss procedure when the circuit check sub-module 123 determines that a circuit condition is abnormal,
the second loop checking sub-module 124 is electrically connected to the loop checking sub-module 123 and the fourth executing module 18, respectively, and is configured to start the operation check of the two loop system to determine whether the operation of the two loop system is abnormal when the loop checking sub-module 123 determines that the loop state is normal, or when the loop checking sub-module 123 determines that the loop state is abnormal, and the fourth executing module 18 completes the procedure of losing the loop coolant,
The second execution module 14 is further electrically connected to the two-circuit inspection sub-module 124 for executing a two-circuit cooling loss procedure when the two-circuit inspection sub-module 124 determines that the two-circuit system is operating abnormally, or the third execution module 16 is further electrically connected to the two-circuit inspection sub-module 124 for executing a steam generator heat transfer tube rupture procedure when the two-circuit inspection sub-module 124 determines that the two-circuit system is operating abnormally,
the evaluation sub-module 125 is electrically connected to the two-loop checking sub-module 124, the second execution module 14 and the third execution module 16, and is configured to evaluate the state of the small pressurized water reactor unit to determine whether to allow the unit to continue to operate when the two-loop checking sub-module 124 determines that the two-loop system is operating normally or when the two-loop checking sub-module 124 determines that the two-loop system is operating abnormally, and the second execution module 14 performs the two-loop cooling loss procedure or the third execution module 16 performs the steam generator heat transfer tube rupture procedure,
the first cold shutdown execution sub-module 126 is electrically connected with the evaluation sub-module 125, and is configured to stop the injection when the evaluation sub-module 125 determines that the unit is not allowed to run continuously, and perform the cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shutdown.
As shown in fig. 11, in this embodiment, the fourth execution module 18 specifically includes:
a two-circuit judging sub-module 181 for judging whether the two-circuit system is faulty or broken,
the second execution module 14 is further electrically connected to the two-circuit determination sub-module 181 for executing a two-circuit cooling loss procedure when the two-circuit determination sub-module 181 determines that the two-circuit system is faulty or broken, or the third execution module 16 is further electrically connected to the two-circuit determination sub-module 181 for executing a steam generator heat transfer tube breaking procedure when the two-circuit determination sub-module 181 determines that the two-circuit system is faulty or broken,
the first adjusting sub-module 182 is electrically connected to the two-circuit judging sub-module 181, and is used for adjusting the charging flow when the two-circuit judging sub-module 181 judges that the two-circuit system is not failed or broken,
the first safety injection judging sub-module 183 is electrically connected to the first adjusting sub-module 182, and is configured to judge whether the safety injection stopping condition is satisfied after the first adjusting sub-module 182 adjusts the charging amount,
the second cold shut-down execution sub-module 184 is electrically connected with the first safety injection judgment sub-module 183, and is used for stopping safety injection when the first safety injection judgment sub-module 183 judges that the safety injection stopping condition is met, executing the cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shut down,
The pressure release valve partial opening judging sub-module 185 is electrically connected with the second cold shut down executing sub-module 184 and is used for judging whether the loop pressure release valve is partially opened or not when the second cold shut down executing sub-module 184 judges that the safety injection stopping condition is not satisfied,
the second cold shutdown execution submodule 184 is further electrically connected to a pressure release valve partial opening determination submodule 185, and is configured to stop injection when the pressure release valve partial opening determination submodule 185 determines that the primary circuit pressure release valve is partially opened, perform a cooling and depressurization operation on the small pressurized water reactor to a cold shutdown thereof,
a low pressure safety injection operation judging sub-module 186 electrically connected with the pressure release valve partial opening judging sub-module 185 for executing low pressure safety injection operation and judging whether the pressure release valve of the loop is fully opened when the pressure release valve partial opening judging sub-module 185 judges that the pressure release valve of the loop is not partially opened,
the built-in heat exchange water tank injection opening sub-module 187 is electrically connected with the low-pressure safety injection operation judging sub-module 186 and is used for opening the built-in heat exchange water tank injection when the low-pressure safety injection operation judging sub-module 186 judges that the primary circuit pressure release valve is completely opened,
a circuit cooling operation sub-module 188 electrically connected to the low pressure safety injection operation determination sub-module 186 for sequentially performing the following operations when the low pressure safety injection operation determination sub-module 186 determines that the circuit relief valve is fully closed: and cooling and depressurizing the first loop, isolating the reactor core water supplementing tank and starting the residual row system.
As shown in fig. 12, in this embodiment, the second execution module 14 specifically includes:
an isolation judging sub-module 141 for isolating the faulty steam generator, judging whether the faulty steam generator is complete,
the third execution module 16 is also electrically connected to the isolation judgment sub-module 141 for executing a steam generator heat transfer tube rupture protocol when the isolation judgment sub-module 141 judges that the faulty steam generator is incomplete,
the second adjusting sub-module 142 is electrically connected with the isolation judging sub-module 141, and is used for adjusting the charging flow when the isolation judging sub-module 141 judges that the fault steam generator is complete,
a second safety injection judging sub-module 143 electrically connected with the second adjusting sub-module 142 for judging whether the safety injection stopping condition is satisfied after the adjusting module adjusts the charging flow,
a third cold shut down execution sub-module 144 electrically connected with the second safety injection judgment sub-module 143 for stopping safety injection when the second safety injection judgment sub-module 143 judges that the safety injection stop condition is satisfied, executing the cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shut down,
the second adjustment sub-module 142 is further configured to adjust the charging flow when the second safety injection determination sub-module 143 determines that the safety injection stop condition is not satisfied.
As shown in fig. 13, in this embodiment, the third execution module 16 specifically includes:
an identification isolator sub-module 161, for identifying and isolating a faulty steam generator,
a third regulating sub-module 162 electrically connected to the identification and isolation sub-module 161 for regulating the charging flow rate to control the water level of the primary circuit within a preset range after the identification and isolation sub-module 161 identifies and isolates the faulty steam generator,
the spraying opening sub-module 163 is electrically connected to the third adjusting sub-module 162, and is configured to open the spraying system after the third adjusting sub-module 162 adjusts the charging rate, so as to reduce the pressure of the primary circuit,
a loop cooling sub-module 164 electrically connected with the spray opening sub-module 163 for cooling the loop after the spray opening sub-module 163 opens the spray system,
the pressure balance judging sub-module 165 is electrically connected to the loop cooling sub-module 164, and is configured to judge whether a loop pressure and a fault steam generator pressure are balanced after the loop cooling sub-module 164 performs a cooling operation on the loop,
a spray stopping sub-module 166 electrically connected to the pressure balance judging sub-module 165 for turning off the spray system when the pressure balance judging sub-module 165 judges that the loop pressure is balanced with the pressure of the failed steam generator,
The third regulation sub-module 162 is also electrically connected to the spray-stop sub-module 166 for regulating the charging flow rate when the spray-stop sub-module 166 turns off the spray system, so as to control the primary circuit water level within a preset range,
the third safety injection judging sub-module 167 is electrically connected with the third adjusting sub-module 162 and is used for judging whether the safety injection stopping condition is met after the third adjusting sub-module 162 controls the primary circuit water level within the preset range, if not, triggering the third adjusting sub-module 162 to continuously adjust the charging flow,
the fourth cold shutdown execution sub-module 168 is electrically connected to the third safety injection judgment sub-module 167, and is configured to stop safety injection when the third safety injection judgment sub-module 167 judges that the safety injection stop condition is satisfied, and execute the cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shutdown.
As shown in fig. 14, in this embodiment, the monitoring subsystem 2 specifically includes:
a core outlet temperature judgment module 21 for judging whether the core outlet temperature is abnormal,
the reactor core cooling function execution module 22 is respectively and electrically connected with the reactor core outlet temperature judgment module 21 and the diagnosis subsystem 1, and is used for executing reactor core cooling function rules when the reactor core outlet temperature judgment module 21 judges that the reactor core outlet temperature is abnormal, triggering the diagnosis subsystem 1 to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the reactor core outlet temperature is recovered to be normal, triggering the reactor core outlet temperature judgment module 21 to start,
A heat discharge flow rate judging module 23 electrically connected to the core outlet temperature judging module 21 for judging whether the heat discharge flow rate is abnormal or not when the core outlet temperature judging module 21 judges that the core outlet temperature is normal,
the heat rejection function execution module 24 is electrically connected with the heat rejection flow judgment module 23, the reactor core outlet temperature judgment module 21 and the diagnosis subsystem 1 respectively, and is used for executing the heat rejection function procedure when the heat rejection flow judgment module 23 judges that the heat rejection flow is abnormal, triggering the diagnosis subsystem 1 to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the heat rejection flow is recovered to be normal, triggering the reactor core outlet temperature judgment module 21 to start,
a containment pressure judging module 25 electrically connected to the heat discharge flow judging module 23 for judging whether the containment pressure is abnormal or not when the heat discharge flow judging module 23 judges that the heat discharge flow is normal,
the containment function execution module 26 is electrically connected with the containment pressure judgment module 25, the reactor core outlet temperature judgment module 21 and the diagnosis subsystem 1 respectively, and is used for executing containment function rules when the containment pressure judgment module 25 judges that the containment pressure is abnormal, triggering the diagnosis subsystem 1 to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the containment pressure is recovered to be normal, triggering the reactor core outlet temperature judgment module 21 to start,
The core outlet temperature determination module 21 is also electrically connected to the containment pressure determination module 25 for activation when the containment pressure determination module 25 determines that the containment pressure is normal.
As shown in fig. 15, in the present embodiment, the core cooling function execution module 22 specifically includes:
a core cooling configuration checking module 221 for checking whether the emergency core cooling configuration is complete,
a core cooling configuration perfection module 222 electrically connected to the core cooling configuration checking module 221 for perfecting the core cooling configuration when the core cooling configuration checking module 221 checks that the emergency core cooling configuration is not perfect,
a core outlet temperature checking module 223 electrically connected to the core cooling configuration checking module 221 and the core cooling configuration completing module 222, respectively, for detecting whether the core outlet temperature is abnormal when the core cooling configuration checking module 221 checks the completion of the emergency core cooling configuration, or after the core cooling configuration completing module 222 completes the core cooling configuration,
the core outlet temperature inspection module 223 is also electrically connected with the diagnosis subsystem 1 and the core outlet temperature judgment module 21, respectively, for triggering the diagnosis subsystem 1 to continue to perform the steps of diagnosing and treating the small pressurized water reactor accident when the detected core outlet temperature is normal, and triggering the core outlet temperature judgment module 21 to start,
The outlet temperature recovery module 224 is electrically connected with the core outlet temperature inspection module 223, the diagnosis subsystem 1 and the core outlet temperature judgment module 21, and is used for sequentially executing a loop pressure relief operation and a built-in refueling water tank injection operation when the core outlet temperature inspection module 223 detects that the core outlet temperature is abnormal, triggering the diagnosis subsystem 1 to continuously execute the steps of diagnosing and treating the small-sized pressurized water reactor accident after the core outlet temperature is recovered to be normal, and triggering the core outlet temperature judgment module 21 to start.
As shown in fig. 16, in the present embodiment, the heat removal function execution module 24 specifically includes:
a heat extraction system configuration checking module 241 for checking whether the heat extraction system configuration is perfect,
a heat extraction system configuration perfecting module 242 electrically connected with the heat extraction system configuration checking module 241 for perfecting the heat extraction system configuration when the heat extraction system configuration checking module 241 checks that the heat extraction system configuration is imperfect,
a steam generator checking module 243 electrically connected to the heat extraction system configuration checking module 241 and the heat extraction system configuration perfecting module 242, respectively, for checking the availability of the steam generator when the heat extraction system configuration checking module 241 checks the heat extraction system configuration perfecting, or after the heat extraction system configuration perfecting module 242 perfects the heat extraction system configuration,
A steam generator recovery module 244, electrically connected to the steam generator inspection module 243, for replacing or repairing the steam generator when the steam generator inspection module 243 inspects that the steam generator is not available,
the heat rejection flow recovery module 245 is electrically connected to the steam generator inspection module 243, the steam generator recovery module 244, the diagnostic subsystem 1 and the core outlet temperature determination module 21, respectively, and is configured to, when the steam generator inspection module 243 inspects that the steam generator is available, or after the steam generator recovery module 244 changes or repairs the steam generator, sequentially perform a steam generator water supply operation and a steam system valve operation, until the heat rejection flow is recovered to be normal, trigger the diagnostic subsystem 1 to continue to perform the steps of diagnosing and treating the small-sized pressurized water reactor accident, and trigger the core outlet temperature determination module 21 to start.
As shown in fig. 17, in the present embodiment, the containment function execution module 26 specifically includes:
an isolation valve inspection module 261 for inspecting whether the containment isolation valve is damaged,
an isolation valve replacement module 262 for replacing the containment isolation valve when the isolation valve inspection module 261 inspects the containment isolation valve for damage,
a containment pressure detecting module 263 electrically connected to the isolation valve checking module 261 and the isolation valve replacing module 262, respectively, for detecting whether the containment pressure is abnormal when the isolation valve checking module 261 checks that the containment isolation valve is not damaged, or after the isolation valve replacing module 262 replaces the containment isolation valve,
The containment pressure detection module 263 is further electrically connected to the diagnostic subsystem 1 and the core outlet temperature determination module 21, respectively, for triggering the diagnostic subsystem 1 to continue performing the steps of diagnosing and treating the small pressurized water reactor accident when it detects that the containment pressure is normal, while triggering the core outlet temperature determination module 21 to start,
the containment pressure recovery module 264 is electrically connected to the containment pressure detection module 263, the diagnosis subsystem 1 and the core outlet temperature determination module 21, and is configured to, when the containment pressure detection module 263 detects that the containment pressure is abnormal, sequentially perform a containment ventilation operation and a containment cooling operation, and after the containment pressure is recovered to be normal, trigger the diagnosis subsystem 1 to continue to perform the steps of diagnosing and processing the small-sized pressurized water reactor accident, and trigger the core outlet temperature determination module 21 to start.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.

Claims (20)

1. An accident handling method for a small pressurized water reactor, comprising:
receiving the emergency shutdown signal, diagnosing and treating the small pressurized water reactor accident,
and after the safety function parameters are recovered to be normal, the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor are continuously executed.
2. The method for handling small pressurized water reactor accidents according to claim 1, characterized in that said diagnosing and handling small pressurized water reactor accidents comprises:
monitoring whether a safety signal appears, if so, turning to the next step, and if not, executing a shutdown protection procedure;
judging whether the pressure of the steam generator is abnormal, if so, executing a two-loop cooling loss procedure, and if not, turning to the next step;
judging whether the radioactivity of the secondary side of the SG is abnormal, if so, executing a steam generator heat transfer tube cracking procedure, and if not, turning to the next step;
Judging whether the pressure of a loop is abnormal, and if so, executing a loop coolant loss procedure.
3. The method for handling accidents of small pressurized water reactor according to claim 2, wherein said executing shutdown protection protocol specifically comprises:
starting a shutdown state check to judge whether the shutdown state is abnormal, if so, executing a reactive abnormal operation, and turning to the next step after finishing, if not, turning to the next step;
starting a loop system state check to judge whether a loop state is abnormal, if so, executing a loop coolant loss procedure, and turning to the next step if not;
starting a two-loop system operation check to judge whether the two-loop system operation is abnormal, if so, executing a two-loop cooling loss procedure or a steam generator heat transfer tube rupture procedure, and turning to the next step if not;
and (3) evaluating the state of the small pressurized water reactor unit, judging whether the unit is allowed to continue to operate, and if not, executing cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is stopped.
4. A method of handling an accident in a small pressurized water reactor according to claim 3, wherein said performing a loop coolant loss procedure comprises:
Judging whether the two-loop system is faulty or broken, if yes, executing two-loop cooling loss procedure or steam generator heat transfer tube breaking procedure, if no, turning to the next step,
regulating the charging flow, judging whether the safety injection stopping condition is met, if yes, stopping safety injection, and performing cooling and depressurization operation on a loop until the small pressurized water reactor enters a cold stop reactor, if not, turning to the next step,
judging whether a loop pressure release valve is partially opened, if so, performing cooling and depressurization operation on a loop until the small pressurized water reactor enters a cold shutdown reactor, if not, turning to the next step,
executing low-pressure safety injection operation, judging whether a loop pressure release valve is completely opened, if yes, opening the built-in heat exchange water tank for injection, and if no, executing the following operations in sequence: and cooling and depressurizing the first loop, isolating the reactor core water supplementing tank and starting the residual row system.
5. The method for handling accidents in small pressurized water reactors according to claim 3, characterized in that said performing a two-circuit cooling loss procedure comprises in particular:
isolating the fault steam generator, judging whether the fault steam generator is complete, if not, executing a steam generator heat transfer tube rupture procedure, and if so, turning to the next step;
adjusting the charging flow;
And judging whether the safety injection stopping condition is met, if so, stopping safety injection, and performing cooling and depressurization operation on a loop until the small pressurized water reactor enters a cold stop reactor, and if not, turning to the previous step.
6. A method of handling incidents in a small pressurized water reactor as claimed in claim 3, wherein said performing a steam generator heat transfer tube rupture protocol comprises, in particular:
s1: a faulty steam generator is identified and isolated,
s2: the charging flow is regulated to control the water level of the primary circuit within a preset range,
s3: the spraying system is started to reduce the pressure of a loop,
s4: the temperature of the first loop is reduced,
s5: judging whether the pressure of the loop and the pressure of the fault steam generator are balanced, if not, turning to the step S3, if yes, turning to the step S6,
s6: the spraying system is stopped,
s7: the charging flow is regulated to control the water level of the primary circuit within a preset range,
s8: and judging whether the safety injection stopping condition is met, if so, stopping safety injection, and continuing to perform cooling and depressurization operation on the first loop until the small pressurized water reactor enters the cold stop reactor, and if not, turning to the step S7.
7. The method for handling accidents in small pressurized water reactors according to any of claims 1-6, characterized in that said monitoring of safety function parameters of small pressurized water reactors comprises:
a: judging whether the temperature of the outlet of the reactor core is abnormal, if so, executing a reactor core cooling function rule, and continuing to execute the steps of diagnosing and treating the accident of the small pressurized water reactor and monitoring the safety function parameter of the small pressurized water reactor until the temperature of the outlet of the reactor core is recovered to be normal, if not, turning to the step b;
b: judging whether the heat rejection flow is abnormal, if so, executing a heat rejection function rule, and continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor until the heat rejection flow is recovered to be normal, if not, turning to the step c;
c: and c, judging whether the containment pressure is abnormal, if so, executing a containment function rule, and continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor until the containment pressure is recovered to be normal, otherwise, turning to the step a.
8. The method for handling accidents in small pressurized water reactors according to claim 7, characterized in that said execution of the core cooling function protocol comprises in particular:
checking whether the emergency core cooling configuration is perfect, if not, turning to the next step after the emergency core cooling configuration is perfect, if so, turning to the next step,
Detecting whether the outlet temperature of the reactor core is abnormal, if so, turning to the next step, if not, ending executing the reactor core cooling function procedure, continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor,
and (3) sequentially executing a loop pressure relief operation and an injection operation of the built-in refueling water tank, and continuously executing the steps of diagnosing and treating the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor after the temperature of the outlet of the reactor core is recovered to be normal.
9. The method for handling accidents in small pressurized water reactors according to claim 7, characterized in that said execution of the heat rejection function protocol comprises in particular:
checking whether the configuration of the heat extraction system is perfect, if not, turning to the next step after the configuration of the heat extraction system is perfect, if so, turning to the next step,
checking the availability of the steam generator, if not, changing or repairing the steam generator, and then turning to the next step, if so,
and successively executing water supply operation of the steam generator and valve operation of the steam system, and continuously executing the steps of diagnosing and treating the accident of the small pressurized water reactor and monitoring the safety function parameters of the small pressurized water reactor after the heat rejection flow is recovered to be normal.
10. The method for handling accidents in small pressurized water reactors according to claim 7, characterized in that said execution of containment function regulations comprises in particular:
checking whether the safety shell isolating valve is damaged, if so, turning to the next step after replacing the safety shell isolating valve, if not, turning to the next step,
detecting whether the containment pressure is abnormal, if so, turning to the next step, if not, ending executing the core cooling function procedure, continuing to execute the steps of diagnosing and processing the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor,
and successively executing the containment ventilation operation and the containment cooling operation, and continuing to execute the steps of diagnosing and treating the small pressurized water reactor accident and monitoring the safety function parameters of the small pressurized water reactor after the containment pressure is recovered to be normal.
11. An accident handling system for a small pressurized water reactor, comprising:
a diagnosis subsystem (1) for receiving the emergency shutdown signal, diagnosing and treating the small pressurized water reactor accident,
the monitoring subsystem (2) is used for monitoring safety function parameters of the small pressurized water reactor while the diagnosis subsystem (1) works, triggering the diagnosis subsystem (1) to interrupt the step of diagnosing and processing the small pressurized water reactor accident after an abnormality occurs in a certain safety function parameter, stopping the step of monitoring the safety function parameter of the small pressurized water reactor, processing the safety function parameter abnormality, triggering the diagnosis subsystem (1) to continuously execute the step of diagnosing and processing the small pressurized water reactor accident after the safety function parameter is recovered to be normal, and starting the step of monitoring the safety function parameter of the small pressurized water reactor.
12. The accident handling system of a small pressurized water reactor according to claim 11, characterized in that the diagnostic subsystem (1) comprises:
a monitoring module (11) for monitoring whether a safety signal is present,
the first execution module (12) is electrically connected with the monitoring module (11) and is used for executing the shutdown protection procedure when the monitoring sub-module monitors that no safety signal exists,
a first judging module (13) electrically connected with the monitoring module (11) and used for judging whether the pressure of the steam generator is abnormal when the monitoring module (11) monitors the occurrence of a safety signal,
the second execution module (14) is electrically connected with the first judgment module (13) and is used for executing a two-loop cooling loss procedure when the first judgment module (13) judges that the pressure of the steam generator is abnormal,
a second judging module (15) electrically connected with the first judging module (13) for judging whether the radioactivity of the secondary side of the SG is abnormal or not when the first judging module (13) judges that the pressure of the steam generator is normal,
a third execution module (16) electrically connected with the second judgment module (15) and used for executing the steam generator heat transfer tube rupture procedure when the second judgment module (15) judges that the radioactivity of the secondary side of the SG is abnormal,
a third judging module (17) electrically connected with the second judging module (15) and used for judging whether the loop pressure is abnormal or not when the second judging module (15) judges that the radioactivity of the secondary side of the SG is normal,
And the fourth execution module (18) is electrically connected with the third judgment module (17) and is used for executing a loop coolant loss procedure when the third judgment module (17) judges that the loop pressure is abnormal.
13. The system for handling incidents of a small pressurized water reactor as claimed in claim 12, wherein the first execution module (12) comprises in particular:
a shutdown checking sub-module (121) for starting a shutdown state check and judging whether the shutdown state is abnormal,
a reactive operation sub-module (122) electrically connected with the shutdown checking sub-module (121) for executing a reactive abnormal operation when the shutdown state judging sub-module judges that the shutdown state is abnormal,
a loop checking sub-module (123) electrically connected with the shutdown checking sub-module (121) and the reactive operation sub-module (122) respectively, for starting a loop system state check to determine whether a loop state is abnormal when the shutdown checking sub-module (121) determines that the shutdown state is normal or after the reactive operation sub-module (122) performs the reactive abnormal operation,
the fourth execution module (18) is also electrically connected with a loop checking sub-module (123) for executing a loop coolant loss procedure when the loop checking sub-module (123) determines that a loop condition is abnormal,
The two loop checking sub-modules (124) are respectively and electrically connected with the loop checking sub-module (123) and the fourth execution module (18) and are used for starting the two loop system operation check to judge whether the two loop system operation is abnormal when the loop checking sub-module (123) judges that the loop state is normal or when the loop checking sub-module (123) judges that the loop state is abnormal and the fourth execution module (18) starts the two loop system operation check after the loop coolant loss procedure is executed,
the second execution module (14) is also electrically connected with the two-loop inspection sub-module (124) for executing the two-loop cooling loss procedure when the two-loop inspection sub-module (124) judges that the two-loop system is abnormal in operation, or the third execution module (16) is also electrically connected with the two-loop inspection sub-module (124) for executing the steam generator heat transfer tube rupture procedure when the two-loop inspection sub-module (124) judges that the two-loop system is abnormal in operation,
the evaluation sub-module (125) is respectively and electrically connected with the two-loop checking sub-module (124), the second execution module (14) and the third execution module (16) and is used for evaluating the state of the small pressurized water reactor unit to judge whether the unit is allowed to continue to run when the two-loop checking sub-module (124) judges that the two-loop system is normal or when the two-loop checking sub-module (124) judges that the two-loop system is abnormal, and the second execution module (14) executes the two-loop cooling loss procedure or the third execution module (16) executes the steam generator heat transfer tube rupture procedure,
The first cold shutdown execution sub-module (126) is electrically connected with the evaluation sub-module (125) and is used for stopping safety injection when the evaluation sub-module (125) judges that the unit is not allowed to run continuously, and executing cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shutdown.
14. The accident handling system of a small pressurized water reactor according to claim 13, characterized in that the fourth execution module (18) comprises in particular:
a two-circuit judging sub-module (181) for judging whether the two-circuit system is faulty or broken,
the second execution module (14) is also electrically connected with the two-loop judging sub-module (181) for executing the two-loop cooling loss procedure when the two-loop judging sub-module (181) judges that the two-loop system is faulty or broken, or the third execution module (16) is also electrically connected with the two-loop judging sub-module (181) for executing the steam generator heat transfer tube breaking procedure when the two-loop judging sub-module (181) judges that the two-loop system is faulty or broken,
a first regulating sub-module (182) electrically connected with the two-loop judging sub-module (181) for regulating the charging flow when the two-loop judging sub-module (181) judges that the two-loop system is not failed or broken,
the first safety injection judging sub-module (183) is electrically connected with the first adjusting sub-module (182) and is used for judging whether the safety injection stopping condition is met after the first adjusting sub-module (182) adjusts the charging flow,
The second cold shut-down execution sub-module (184) is electrically connected with the first safety injection judgment sub-module (183) and is used for stopping safety injection when the safety injection judgment sub-module (183) judges that the safety injection stopping condition is met, executing the cooling and pressure reducing operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shut down,
a pressure release valve partial opening judging sub-module (185) electrically connected with the second cold shut-down executing sub-module (184) and used for judging whether the loop pressure release valve is partially opened or not when the second cold shut-down executing sub-module (184) judges that the safety injection stopping condition is not met,
the second cold shut-down execution sub-module (184) is further electrically connected with the pressure release valve partial opening judging sub-module (185) and is used for stopping injection when the pressure release valve partial opening judging sub-module (185) judges that the pressure release valve of the primary loop is partially opened, executing the cooling and depressurization operation on the small-sized pressurized water reactor until the small-sized pressurized water reactor is cooled and shut down,
a low-pressure safety injection operation judging sub-module (186) electrically connected with the pressure release valve partial opening judging sub-module (185) and used for executing low-pressure safety injection operation and judging whether the pressure release valve of the loop is completely opened when the pressure release valve partial opening judging sub-module (185) judges that the pressure release valve of the loop is not partially opened,
an injection opening sub-module (187) of the built-in heat exchange water tank is electrically connected with the low-pressure safety injection operation judging sub-module (186) and is used for opening the injection of the built-in heat exchange water tank when the low-pressure safety injection operation judging sub-module (186) judges that the loop relief valve is completely opened,
A loop cooling operation sub-module (188) electrically connected with the low-pressure safety injection operation judging sub-module (186) and used for executing the following operations in sequence when the low-pressure safety injection operation judging sub-module (186) judges that the loop pressure release valve is closed completely: and cooling and depressurizing the first loop, isolating the reactor core water supplementing tank and starting the residual row system.
15. The method for handling accidents in small pressurized water reactors according to claim 13, characterized in that the second execution module (14) comprises in particular:
an isolation judging sub-module (141) for isolating the faulty steam generator, judging whether the faulty steam generator is complete,
the third execution module (16) is also electrically connected with the isolation judgment sub-module (141) and is used for executing the steam generator heat transfer tube rupture procedure when the isolation judgment sub-module (141) judges that the fault steam generator is incomplete,
a second regulation sub-module (142) electrically connected with the isolation judgment sub-module (141) for regulating the charging flow rate when the isolation judgment sub-module (141) judges that the fault steam generator is complete,
a second safety injection judging sub-module (143) electrically connected with the second adjusting sub-module (142) for judging whether the safety injection stopping condition is satisfied after the adjusting module adjusts the charging flow,
A third cold shut-down execution sub-module (144) electrically connected with the second safety injection judgment sub-module (143) and used for stopping safety injection when the safety injection judgment sub-module (143) judges that the safety injection stopping condition is met, executing the cooling and pressure reducing operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shut down,
the second regulation sub-module (142) is further configured to regulate the charging flow rate when the second safety injection judgment sub-module (143) judges that the safety injection stop condition is not satisfied.
16. The method for handling accidents in small pressurized water reactors according to claim 13, characterized in that said third execution module (16) comprises in particular:
an identification isolation sub-module (161) for identifying and isolating a faulty steam generator,
a third regulation sub-module (162) electrically connected with the identification and isolation sub-module (161) for regulating the charging flow rate after the identification and isolation sub-module (161) identifies and isolates the fault steam generator so as to control the water level of the first circuit within a preset range,
a spray opening sub-module (163) electrically connected with the third regulating sub-module (162) for opening the spray system after the third regulating sub-module (162) regulates the charging flow to reduce the pressure of the primary circuit,
a loop cooling sub-module (164) electrically connected with the spraying start sub-module (163) for cooling the loop after the spraying start sub-module (163) starts the spraying system,
A pressure balance judging sub-module (165) electrically connected with the loop cooling sub-module (164) for judging whether the loop pressure and the fault steam generator pressure are balanced or not after the loop cooling sub-module (164) cools the loop,
a spraying stopping sub-module (166) electrically connected with the pressure balance judging sub-module (165) and used for closing the spraying system when the pressure balance judging sub-module (165) judges that the pressure of the primary circuit is balanced with the pressure of the fault steam generator,
the third regulating sub-module (162) is also electrically connected with the spraying stopping sub-module (166) and is used for regulating the charging flow when the spraying stopping sub-module (166) closes the spraying system so as to control the water level of the first circuit within a preset range,
a third safety injection judging sub-module (167) electrically connected with the third regulating sub-module (162) and used for judging whether the safety injection stopping condition is met after the third regulating sub-module (162) controls the primary circuit water level within a preset range, if not, triggering the third regulating sub-module (162) to continuously regulate the charging flow,
and the fourth cold shut-down execution sub-module (168) is electrically connected with the third safety injection judgment sub-module (167) and is used for stopping safety injection when the third safety injection judgment sub-module (167) judges that the safety injection stopping condition is met, and executing cooling and depressurization operation on the small pressurized water reactor until the small pressurized water reactor is cooled and shut down.
17. The method for handling incidents of a small pressurized water reactor according to any one of claims 11 to 16, wherein said monitoring subsystem (2) comprises in particular:
a core outlet temperature judgment module (21) for judging whether the core outlet temperature is abnormal,
the reactor core cooling function execution module (22) is respectively and electrically connected with the reactor core outlet temperature judgment module (21) and the diagnosis subsystem (1) and is used for executing the reactor core cooling function rule when the reactor core outlet temperature judgment module (21) judges that the reactor core outlet temperature is abnormal, triggering the diagnosis subsystem (1) to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the reactor core outlet temperature is recovered to be normal, triggering the reactor core outlet temperature judgment module (21) to start,
a heat discharge flow rate judgment module (23) electrically connected to the core outlet temperature judgment module (21) for judging whether the heat discharge flow rate is abnormal when the core outlet temperature judgment module (21) judges that the core outlet temperature is normal,
the heat rejection function execution module (24) is respectively and electrically connected with the heat rejection flow judgment module (23), the reactor core outlet temperature judgment module (21) and the diagnosis subsystem (1) and is used for executing the heat rejection function rule when the heat rejection flow judgment module (23) judges that the heat rejection flow is abnormal, triggering the diagnosis subsystem (1) to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the heat rejection flow is recovered to be normal, triggering the reactor core outlet temperature judgment module (21) to start,
A containment pressure judging module (25) electrically connected with the heat discharge flow judging module (23) for judging whether the containment pressure is abnormal or not when the heat discharge flow judging module (23) judges that the heat discharge flow is normal,
the containment function execution module (26) is respectively and electrically connected with the containment pressure judgment module (25), the reactor core outlet temperature judgment module (21) and the diagnosis subsystem (1) and is used for executing containment function rules when the containment pressure judgment module (25) judges that the containment pressure is abnormal, triggering the diagnosis subsystem (1) to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the containment pressure is recovered to be normal, triggering the reactor core outlet temperature judgment module (21) to start,
the reactor core outlet temperature judging module (21) is also electrically connected with the containment pressure judging module (25) and is used for starting when the containment pressure judging module (25) judges that the containment pressure is normal.
18. The accident handling system of a small pressurized water reactor as set forth in claim 17, wherein said core cooling function execution module (22) specifically includes:
a core cooling configuration checking module (221) for checking whether the emergency core cooling configuration is complete,
a core cooling configuration perfecting module (222) electrically connected with the core cooling configuration checking module (221) for perfecting the core cooling configuration when the core cooling configuration checking module (221) checks that the emergency core cooling configuration is imperfect,
A core outlet temperature checking module (223) electrically connected with the core cooling configuration checking module (221) and the core cooling configuration perfecting module (222) respectively, for detecting whether the core outlet temperature is abnormal when the core cooling configuration checking module (221) checks the emergency core cooling configuration perfecting or after the core cooling configuration perfecting module (222) perfects the core cooling configuration,
the reactor core outlet temperature checking module (223) is also respectively and electrically connected with the diagnosis subsystem (1) and the reactor core outlet temperature judging module (21) and is used for triggering the diagnosis subsystem (1) to continuously execute the steps of diagnosing and treating the small pressurized water reactor accident and triggering the reactor core outlet temperature judging module (21) to start when the detected reactor core outlet temperature is normal,
the outlet temperature recovery module (224) is respectively and electrically connected with the reactor core outlet temperature inspection module (223), the diagnosis subsystem (1) and the reactor core outlet temperature judgment module (21) and is used for sequentially executing a loop pressure relief operation and a built-in material changing water tank injection operation when the reactor core outlet temperature inspection module (223) detects the reactor core outlet temperature abnormality, triggering the diagnosis subsystem (1) to continuously execute the steps of diagnosing and treating the small-sized pressurized water reactor accident after the reactor core outlet temperature is recovered to be normal, and triggering the reactor core outlet temperature judgment module (21) to start.
19. The method of accident handling for a small pressurized water reactor according to claim 17, wherein said heat rejection function execution module (24) comprises:
a heat extraction system configuration checking module (241) for checking whether the heat extraction system configuration is perfect,
a heat extraction system configuration perfecting module (242) electrically connected with the heat extraction system configuration checking module (241) for perfecting the heat extraction system configuration when the heat extraction system configuration checking module (241) checks that the heat extraction system configuration is imperfect,
a steam generator checking module (243) electrically connected with the heat extraction system configuration checking module (241) and the heat extraction system configuration perfecting module (242) respectively, for checking the availability of the steam generator when the heat extraction system configuration checking module (241) checks the heat extraction system configuration perfecting or after the heat extraction system configuration perfecting module (242) perfects the heat extraction system configuration,
a steam generator recovery module (244) electrically connected to the steam generator inspection module (243) for replacing or repairing the steam generator when the steam generator inspection module (243) inspects that the steam generator is not available,
the heat rejection flow recovery module (245) is electrically connected with the steam generator checking module (243), the steam generator recovery module (244), the diagnosis subsystem (1) and the reactor core outlet temperature judging module (21) respectively, and is used for sequentially executing the steam generator water supply operation and the steam system valve operation when the steam generator checking module (243) checks that the steam generator is available or after the steam generator is replaced or repaired by the steam generator recovery module (244), triggering the diagnosis subsystem (1) to continuously execute the steps of diagnosing and treating the small-sized pressurized water reactor accident after the heat rejection flow is recovered to be normal, and triggering the reactor core outlet temperature judging module (21) to start.
20. The method of accident handling for small pressurized water reactors according to claim 17, characterized in that said containment function execution module (26) comprises in particular:
an isolation valve inspection module (261) for inspecting whether the containment isolation valve is damaged,
an isolation valve replacement module (262) for replacing the containment isolation valve when the isolation valve inspection module (261) inspects the containment isolation valve for damage,
a containment pressure detection module (263) electrically connected to the isolation valve inspection module (261) and the isolation valve replacement module (262), respectively, for detecting whether the containment pressure is abnormal when the isolation valve inspection module (261) inspects that the containment isolation valve is not damaged or after the isolation valve replacement module (262) replaces the containment isolation valve,
the containment pressure detection module (263) is also respectively and electrically connected with the diagnosis subsystem (1) and the reactor core outlet temperature judgment module (21) and is used for triggering the diagnosis subsystem (1) to continuously execute the steps of diagnosing and treating the small-sized pressurized water reactor accident and triggering the reactor core outlet temperature judgment module (21) to start when the containment pressure is detected to be normal,
the containment pressure recovery module (264) is respectively and electrically connected with the containment pressure detection module (263), the diagnosis subsystem (1) and the reactor core outlet temperature judgment module (21) and is used for sequentially executing containment ventilation operation and containment cooling operation when the containment pressure detection module (263) detects that the containment pressure is abnormal, triggering the diagnosis subsystem (1) to continuously execute the steps of diagnosing and processing the small-sized pressurized water reactor accident after the containment pressure is recovered to be normal, and triggering the reactor core outlet temperature judgment module (21) to start.
CN202310154551.2A 2023-02-23 2023-02-23 Accident handling method and system for small pressurized water reactor Pending CN116110631A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202310154551.2A CN116110631A (en) 2023-02-23 2023-02-23 Accident handling method and system for small pressurized water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202310154551.2A CN116110631A (en) 2023-02-23 2023-02-23 Accident handling method and system for small pressurized water reactor

Publications (1)

Publication Number Publication Date
CN116110631A true CN116110631A (en) 2023-05-12

Family

ID=86261514

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202310154551.2A Pending CN116110631A (en) 2023-02-23 2023-02-23 Accident handling method and system for small pressurized water reactor

Country Status (1)

Country Link
CN (1) CN116110631A (en)

Similar Documents

Publication Publication Date Title
US5621776A (en) Fault-tolerant reactor protection system
EP3090433B1 (en) Nuclear reactor protection systems and methods
EP3563391A1 (en) Nuclear reactor protection systems and methods
CN111540487A (en) Cooling treatment method for reactor after steam generator heat transfer pipe failure accident
CN111681794B (en) Full-range SGTR accident handling method and system for pressurized water reactor nuclear power plant
KR100875467B1 (en) Digital Reactor Protection System with Independent Redundancy Structure Redundancy
US10504627B2 (en) Method for managing stoppage of a pressurised-water nuclear reactor
CN116110631A (en) Accident handling method and system for small pressurized water reactor
CN109087721B (en) Fault diagnosis method for pressurized water reactor nuclear power plant
CN113972016A (en) Method, device, equipment and medium for coping loss of coolant accident outside containment of nuclear power plant
CN114694858A (en) Automatic low-pressure full-speed cooling method and system for nuclear power plant unit
JP2009176205A (en) Primary risk factor analysis device by sequence tree
Husseiny et al. Operating procedure automation to enhance safety of nuclear power plants
KR20210039782A (en) Emergency operation guide method for nuclear power plant
Liu et al. RESEARCH ON SYSTEM STRUCTURE IMPROVEMENT OF HPR1000 SYMPTOM BASED EMERGENCY OPERATING PROCEDURES
CN113777976B (en) Nuclear power plant isolation valve control circuit
Qian et al. STUDY ON CLASSIFICATION METHOD OF EQUIPMENT BASED ON AVAILABILITY OF NUCLEAR POWER PLANT
Wenhui et al. PSA Application in the Diverse Actuation System Design
Solovjanov et al. Implementation of Severe Accident Management Guidelines to Shutdown and Low-Power Modes for VVER and PWR Plants
Plan et al. Based on these occurrences how will RCS flow in the 1B Loop respond?
CN112700898A (en) Spraying method for shutdown containment after accident of advanced pressurized water reactor nuclear power plant
Xie et al. Research on periodic test scheme of safety digital control system for nuclear power plant
CN113936821A (en) Diagnostic method, recovery method, diagnostic device and recovery device for sub-criticality key safety function
Shin et al. DIVERSITY AND DEFENSE-IN-DEPTH ANALYSIS FOR I&C SYSTEMS OF RESEARCH REACTORS: A CASE STUDY ON TWO RESEARCH REACTORS
KOEBERLE1N LESSONS LEARNED FROM PSA'S FOR GERMAN NPP'S

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