CN108470592B - Post-accident expansion application method for nuclear power plant system - Google Patents
Post-accident expansion application method for nuclear power plant system Download PDFInfo
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Abstract
The invention provides a post-accident expansion application method of a nuclear power plant system, which comprises the following steps: analyzing to obtain an interface of a working condition requirement-system expansion use function; based on the interface of the working condition requirement-system expansion use function, screening an expansion application system matched with the working condition requirement according to the screening principle of the expansion application system to obtain an expansion application system list under the accident working condition; and aiming at the expansion application system list under the accident condition, according to the system expansion application principle, carrying out analysis on the expansion application method so as to obtain the post-accident expansion application method of the nuclear power plant system and form an optimization treatment strategy aiming at the specific or emergency accident condition. The post-accident system expansion application method makes up the limitation of the design of special safety facilities and related systems, expands the system application range and method, perfects the accident handling strategy and achieves the purposes of controlling the accident development to the maximum extent and lightening the accident consequence.
Description
Technical Field
The invention relates to the technical field of nuclear power plant accident handling, in particular to a nuclear power plant system post-accident expansion application method.
Background
To ensure safe operation of a nuclear power plant, nuclear power plant conditions are defined into four categories according to the design safety regulations for nuclear power plants (HAF 102): normal operation, predicted operation events, accident conditions and serious accidents. For accident conditions, a reactivity control system, a reactor protection system, a safety injection system, a containment spraying system, a steam generator auxiliary water supply system and other special safety facilities are designed in the pressurized water reactor nuclear power plant, so that the nuclear power plant can realize safety functions of effectively controlling reactor core reactivity, ensuring effective cooling of the reactor core and ensuring containment of radioactivity without outward release under all operation conditions.
However, for some specific or urgent accident conditions considered for the operation of the pressurized water reactor nuclear power plant, if the accident conditions are dealt with only by the reactivity control system, the reactor protection system and the special safety facilities, the operation effect of the nuclear power plant under the accident conditions and the safety under the special conditions are limited and incomplete.
These specific or emergency accident conditions typically present the following characteristics:
1) the possibility of generating bad influence due to evolution exists in the condition of bad working condition or the condition that a relieving measure is not taken in time;
2) the working condition is complex, a plurality of aspects to be controlled or relieved exist, the complex working condition generates various accident process control requirements, and compared with various accident treatment requirements, the special safety facilities cannot timely and perfectly cover each aspect to be treated;
3) the influence of the working condition on the special safety facility and the safety shell, namely the function damage to be generated or caused;
4) the fault or accident condition is special, the accident handling requirement is clear and relatively single, but the fault or accident handling requirement does not belong to the working condition of special safety facility design and coping, and the special safety facility cannot be effectively handled.
The limitations or incompleteness are caused by the mismatch between the specific or emergency accident condition and the design function of the reactivity control system, the reactor protection system or the special safety facility, such as the complex accident situation that the special safety facility cannot be controlled completely, the condition of damaging the special safety facility, and the like, specifically, the containment is used as the last barrier of the pressurized water reactor nuclear power plant for preventing the radioactive substance from diffusing outwards, the integrity of the containment is threatened in the high-pressure condition of the containment, and the integrity of the containment is ensured to be a basic requirement of accident treatment, under the severe condition of the high-pressure condition of the containment, the reason of causing the high-pressure condition of the containment is complex, the possible conditions of radioactive pollution in the containment, slow leakage of the inner containment, hydrogen accumulation, pressure or temperature in the containment exceeding the design permission and the like exist, if only depending on the containment spraying system, under complex conditions, the effect of the method is single, and the coping strategy is insufficient and not optimized.
In the above-mentioned limited or incomplete places, there is a great potential hazard to the safety of the nuclear power plant, and the development and evolution cannot be left uncontrolled in the aspect of the accident handling strategy, and further consideration must be given to the compensation measures.
Disclosure of Invention
The technical problem to be solved by the invention is to provide a post-accident expansion application method of a nuclear power plant system, which is applied to a relevant nuclear power plant system under a specific or emergency accident condition, aiming at the defects in the prior art.
The technical scheme adopted for solving the technical problem of the invention is as follows:
the invention provides a post-accident expansion application method of a nuclear power plant system, which comprises the following steps:
analyzing to obtain an interface of a working condition requirement-system expansion use function;
based on the interface of the working condition requirement-system expansion use function, screening an expansion application system matched with the working condition requirement according to the screening principle of the expansion application system to obtain an expansion application system list under the accident working condition;
and aiming at the expansion application system list under the accident condition, according to the system expansion application principle, carrying out analysis on the expansion application method so as to obtain the post-accident expansion application method of the nuclear power plant system and form an optimization treatment strategy aiming at the specific or emergency accident condition.
Optionally, the step of analyzing the interface for obtaining the working condition requirement-system extended use function specifically includes:
based on the processing requirement condition of the accident condition, the functional limitations of the special safety facilities and the safety shell are analyzed in the specific accident condition processing, the special condition requirements are analyzed, and the requirement key points existing in the accident condition processing are classified and combined to form an interface of the working condition requirement-system expansion use function.
Optionally, the method for analyzing the functional limitations of the special safety facility and the containment vessel in the specific accident condition processing and analyzing the special condition requirements specifically includes:
if the accident condition treatment is related to the function of the special safety facility, analyzing whether the accident treatment requirements of containment spraying, auxiliary water supply and safe injection exist;
if the accident condition processing is related to the containment function, analyzing whether the accident processing requirements of containment integrity maintenance, containment tightness, containment air circulation and containment long-term heat extraction exist;
and if the special working condition requirements exist, specifically analyzing and determining the special accident handling requirements of the working conditions.
Optionally, the analyzing whether there is an accident handling requirement for spraying containment vessel specifically includes: analyzing whether partial or total loss of the containment spraying exists or not and whether the containment spraying function is influenced by the loss of the support system exists or not;
the analysis of whether the accident treatment requirement of auxiliary water supply exists is specifically as follows: analyzing whether auxiliary water supply cannot meet the accident handling requirement or not and whether the auxiliary water supply function is influenced by losing a support system or not;
the analysis of whether the accident handling requirement of safe injection exists is specifically as follows: analyzing whether partial or total loss of safety injection exists or not, and whether the safety injection function is influenced by the loss of a support system exists or not;
the analysis of whether the accident handling requirement for maintaining the integrity of the containment vessel exists is specifically as follows: and analyzing whether the pressure and the temperature in the containment vessel exceed the design permission conditions in the accident condition.
Optionally, the extended application system may conform to one of the following screening principles 1 to 3 according to applicable working condition classification:
the screening principle 1 is that the system is used as a direct replacement or low-quality replacement system of a support system of the special safety facility in function or is used as a functional replacement of the special safety facility in function;
the screening principle 2 is a system related to the air circulation, filtering ventilation, sealing or heat removal and pressure reduction functions of the containment;
the screening principle 3 is that for special working conditions which do not belong to the design and response of the special safety facilities, a system or equipment with strong function pertinence and relatively low operation cost is selected.
Optionally, in the step of developing an analysis of the extended application method according to a system extended application principle in the extended application system list under the accident condition, the adopted analysis items include: the system expands the working condition that the application is suitable for; the system expansion application principle to be adopted; analyzing the necessity of expanding the application of the system; the specific method of the system expansion application; the system extends the intended effect of the application.
Optionally, the system extended application principles include extended application principles 1 through 6, wherein,
the extended application principle 1 is that in an emergency or severe accident condition, a relevant system is used in a working condition of a non-design operation condition on the basis of necessity analysis and expected effect evaluation;
the expanded application principle 2 is that under the accident condition, aiming at the emergency situation that the support system of the special safety facility fails, the support system with the quality lower than the design standard is used to provide support for the operation of the special safety facility;
the expansion application principle 3 is that under the accident condition, aiming at the condition that the special safety facilities fail, other related systems with overlapped or similar functions are used to achieve the effect of temporarily replacing the execution function;
the application principle 4 is expanded, for the severe working condition threatening the function of the containment vessel, the radioactive leakage is prevented and controlled to the maximum extent, the integrity of the last barrier is protected, and the related system is put into operation in the working condition exceeding the designed use condition according to the operation working condition;
the application principle 5 is expanded, for the severe working condition threatening the function of the containment vessel, the radioactive leakage is prevented and controlled to the maximum extent, the integrity of the last barrier is protected, and the related system is manually put into operation according to the operation working condition before reaching the starting threshold;
the extended application principle 6 is that for the severe working conditions threatening the function of the containment, radioactive leakage should be prevented and controlled to the maximum extent, the integrity of the last barrier is protected, and a system which is overlapped with the function of the related special safety facilities is considered to be put into operation with the special safety facilities in parallel according to the operation working conditions so as to functionally cooperate with or reserve the special safety facilities.
Optionally, before the step of analyzing the interface of the operating condition requirement-system expansion use function, the method further includes the following steps:
and judging whether the accident condition is suitable for the post-accident expanded application of the nuclear power plant system according to an applicable condition principle, if so, executing the step of analyzing to obtain a condition requirement-system expanded use function interface, and if not, using a corresponding special safety facility, a reactivity control system or a reactor protection system according to the design condition of the nuclear power plant system to deal with the accident.
Optionally, the step of judging whether the accident condition is applicable to the post-accident extended application of the nuclear power plant system according to the applicable condition principle specifically includes:
when the accident working condition conforms to the applicable working condition principle 1 and the applicable working condition principle 2, judging that the accident working condition is suitable for extended application, otherwise, judging that the accident working condition is not suitable for extended application;
the principle 1 of the applicable working condition is a severe working condition, and the principle 2 of the applicable working condition is any one of a complex working condition, the influence of the working condition on the function damage to the special safety facility and the safety shell, and a special working condition.
Optionally, for the applicable working condition principle 1, the severe working condition refers to that the accident working condition already causes a severe influence, or if a mitigating measure is not taken in time, there is a possibility that the evolution generates the severe influence, where the severe influence refers to a degree of harm reaching or exceeding a design reference accident; for the applicable working condition principle 2, the complex working condition refers to the fact that multiple aspects to be urgently controlled or relieved exist in the accident working condition, and the special working condition refers to the fact that the accident working condition does not belong to the working condition of special safety facility design coping, and the special safety facility cannot be effectively processed.
Has the advantages that:
1) the invention is matched with the function of the specially-designed safety facilities of the nuclear power plant, increases the means of accident handling, optimizes and perfects the accident handling strategy from the aspects of measure diversity and depth defense, thereby achieving the effects of controlling the development of accident conditions to the maximum extent and lightening the accident consequences.
2) The invention can be used for guiding the design and optimization of the accident handling rule file, and can improve the accident rule from the strategy and measure, in particular to the accident rule for handling the superposed complex accident condition.
Drawings
Fig. 1 is a flowchart of an extended application method after a nuclear power plant system accident according to an embodiment of the present invention.
Detailed Description
In order to make the technical solutions of the present invention better understood, the present invention is further described in detail below with reference to the accompanying drawings and examples.
The invention aims to solve the problems existing in the current accident handling, and provides a method adopted by post-accident system expansion application under the non-design operation condition, namely a post-accident expansion application method of a nuclear power plant system, aiming at relevant nuclear power plant systems under certain specific or emergent important accident working conditions, regardless of the safety-related or non-safety-related systems, so as to make up the limitation of the design of special safety facilities and relevant systems, expand the application range and the method of the system, perfect accident handling strategies and achieve the purposes of controlling the accident development to the maximum extent and lightening the accident consequences.
The following is a detailed description by way of specific examples.
As shown in fig. 1, the method for expanding the application of the nuclear power plant system after the accident provided by the embodiment of the invention includes the following steps S101 to S105.
S101, judging whether the accident condition is suitable for expanding application after the nuclear power plant system accident according to an applicable condition principle, if so, executing a step S103, and if not, executing a step S102.
The step S101 is specifically: and when the accident condition accords with the applicable condition principle 1 and the applicable condition principle 2, judging that the accident condition is suitable for extended application, otherwise, judging that the accident condition is not suitable for extended application.
The principle 1 of the applicable working condition is a severe working condition, and the principle 2 of the applicable working condition is any one of a complex working condition, the influence of the working condition on the function damage to the special safety facility and the safety shell, and a special working condition.
Specifically, the applicable operating condition principle 1 is used to identify the severity of the accident operating condition, if the accident operating condition is not very severe in practice, or the development and evolution thereof is slow and there is no possibility of causing adverse effects on the operation of the unit, that is, the applicable operating condition principle 1 is not met, then the accident should be dealt with by using other systems such as corresponding special safety facilities or reactivity control systems, reactor protection systems, etc. as far as possible according to the design conditions of the nuclear power plant system (i.e., step S102). On the basis of conforming to the applicable working condition principle 1, if the accident working condition conforms to any one of the applicable working condition principles 2, the accident working condition can be determined to be applicable to post-accident expanded application of the nuclear power plant system, and the design of perfect measures is developed according to the invention.
In this embodiment, as for the applicable working condition principle 1, the severe working condition refers to that the accident working condition has caused a severe influence, or if a mitigating measure is not taken in time, there is a possibility that the evolution generates the severe influence, and the severe influence refers to that the degree of damage of the design basis accident is reached or exceeded. For the applicable working condition principle 2, the complex working condition refers to that there are multiple aspects to be urgently controlled or alleviated in the accident working condition, such as the accident process control requirements of different aspects of operation support, heat removal, ventilation, air circulation, air suspended matter settlement and the like of the active equipment, and the special safety facility cannot timely and perfectly cover each aspect to be processed in the working condition; the special working condition refers to that the accident working condition does not belong to the working condition of the special safety facility design and coping, and the special safety facility cannot be effectively processed.
The above applicable working condition principle is used as a standard for working condition identification and is used for analyzing and evaluating whether an accident working condition belongs to an applicable working condition of an extended use method after a nuclear power plant system accident.
S102, corresponding special safety facilities, a reactivity control system or a reactor protection system are used for dealing with accidents according to the design conditions of the nuclear power plant system.
And S103, analyzing to obtain an interface of the working condition requirement and the system expansion use function.
The step S103 is specifically: based on the processing requirement condition of the accident condition, the functional limitations of the special safety facilities and the safety shell are analyzed in the specific accident condition processing, the special condition requirements are analyzed, and the requirement key points existing in the accident condition processing are classified and combined to form an interface of the working condition requirement-system expansion use function.
Further, the method for analyzing the functional limitations of the special safety facilities and the containment vessel and analyzing the requirements of the special working conditions in the specific accident working condition treatment specifically comprises the following steps:
if the accident condition treatment is related to the function of the special safety facility, analyzing whether the accident treatment requirements of containment spraying, auxiliary water supply and safe injection exist;
if the accident condition processing is related to the containment function, analyzing whether the accident processing requirements of containment integrity maintenance, containment tightness, containment air circulation and containment long-term heat extraction exist;
and if the special working condition requirements exist, specifically analyzing and determining the special accident handling requirements of the working conditions.
And classifying and combining the essential points of the requirements in the accident condition processing according to the three analysis results to form a compensation measure requirement list, namely a condition requirement-system expansion use function interface, which is used as an input item of the step S104.
Wherein the analyzing whether the accident handling requirement of containment spraying exists is specifically as follows: analyzing whether partial or total loss of spraying of the containment vessel exists or not, and whether the spraying function of the containment vessel is influenced by loss of a cooling or electrical support system or the like exists or not;
the analysis of whether the accident treatment requirement of auxiliary water supply exists is specifically as follows: analyzing whether auxiliary water supply cannot meet the requirement of accident treatment and whether the auxiliary water supply function is influenced by the loss of electric, compressed air, a desalination and oxygen removal water source and other support systems;
the analysis of whether the accident handling requirement of safe injection exists is specifically as follows: analyzing whether partial or total loss of safety injection exists or not, and whether the safety injection function is influenced by the loss of a support system exists or not;
the analysis of whether the accident handling requirement for maintaining the integrity of the containment vessel exists is specifically as follows: and analyzing whether the pressure and the temperature in the containment vessel exceed the design permission conditions in the accident condition, wherein the requirements of emergency pressure relief and emergency heat removal of the containment vessel are included.
And S104, screening the extended application system matched with the working condition requirement based on the working condition requirement-system extended use function interface according to the screening principle of the extended application system to obtain an extended application system list under the accident working condition.
Wherein, according to the classification of applicable working conditions, the extended application system should accord with one of the following screening principles 1 to 3:
the screening principle 1 is that the system is used as a direct replacement or low-quality replacement system of a support system of the special safety facility in function or is used as a functional replacement of the special safety facility in function;
the screening principle 2 is a system related to the air circulation, filtering ventilation, sealing or heat removal and pressure reduction functions of the containment;
the screening principle 3 is that for special working conditions which do not belong to the design and response of the special safety facilities, a system or equipment with strong function pertinence and relatively low operation cost is selected.
Table 1 shows an example of extending the application system inventory under a particular or emergency condition.
TABLE 1
In this embodiment, when the extended application system is screened, the security-related attributes of the system or whether the system bears the security function are not used as important bases for screening.
And S105, aiming at the expansion application system list under the accident working condition, carrying out analysis on an expansion application method according to a system expansion application principle to obtain a post-accident expansion application method of the nuclear power plant system, and forming an optimization treatment strategy aiming at a specific or emergency accident working condition.
In this step, the analysis items used when the extended application method is developed include: the system expands the working condition that the application is suitable for; the system expansion application principle to be adopted; analyzing the necessity of expanding the application of the system; the specific method of the system expansion application; the system extends the intended effect of the application.
Wherein the system extended application principle comprises the following extended application principles 1 to 6:
the extended application principle 1 is that in an emergency or severe accident condition, a related system can be used in a working condition of an off-design operation condition on the basis of necessity analysis and expected effect evaluation;
the expanded application principle 2 is that under the accident condition, aiming at the emergency situation that the support system of the special safety facility fails, the support system with the quality lower than the design standard can be used to provide support for the operation of the special safety facility;
the expansion application principle 3 is that under the accident condition, aiming at the condition that the special safety facilities fail, other related systems with overlapped or similar functions are tried to be used so as to achieve the effect of temporarily replacing and executing the functions;
the application principle 4 is expanded, for the severe working condition threatening the function of the containment vessel, the radioactive leakage is prevented and controlled to the maximum extent, the integrity of the last barrier is protected, and the related system can be put into operation in the working condition exceeding the designed use condition according to the operation working condition;
the application principle 5 is expanded, for the severe working condition threatening the function of the containment vessel, the radioactive leakage is prevented and controlled to the maximum extent, the integrity of the last barrier is protected, and the related system can be manually put into operation according to the operation working condition before reaching the starting threshold;
the extended application principle 6 is that for the severe working conditions threatening the function of the containment, the radioactive leakage is prevented and controlled to the maximum extent, the integrity of the last barrier is protected, and a system which is overlapped with the function of the related special safety facilities can be considered to be put into operation with the special safety facilities in parallel according to the operation working conditions so as to functionally cooperate with or reserve the special safety facilities.
The method for expanding the application of the nuclear power plant system after the accident is determined based on the expansion application principles 1 to 6.
Taking a passive containment heat export system as an example, the following extended application analysis is carried out:
a. the system expands and applies the applicable working condition, namely the containment high-pressure working condition.
b. The system expansion application principle to be adopted-expansion application principles 1, 6.
The design function of the passive containment heat exporting system is used for long-term heat removal of the containment under the over-design basis accident, including accidents related to the power failure of a whole plant and the fault of a spraying system. According to the expansion application principles 1 and 6, the use condition of the safety shell is expanded to the treatment of high-pressure working conditions of all safety shells.
c. Necessity analysis of system expansion application
The containment vessel is a barrier for preventing radioactivity from being dissipated outside in the last process of a pressurized water reactor nuclear power plant, and effective measures must be made to timely process the high-pressure working condition of the containment vessel so as to avoid the integrity damage of the containment vessel. The passive containment heat exporting system is designed to reduce the pressure and the temperature of the containment to acceptable levels in a passive mode in the case of over-design quasi-accident, so as to maintain the integrity of the containment.
d. Concrete method for expanding application of system
The working condition in the containment vessel is deteriorated or continuously and effectively improved after the accident, when the manual starting criterion (high pressure) of the containment vessel spraying is reached, the passive containment vessel heat exporting system is taken into consideration in advance or in parallel, the high-pressure working condition or the high-temperature working condition is relieved for the containment vessel, or the containment vessel heat is exported when the safety spraying is failed.
e. Expected effect of system expansion application
Before the pressure of the containment vessel reaches the safety action fixed value, the passive containment vessel heat exporting system is started, so that the containment vessel can be cooled and depressurized more favorably, and the operation of a containment vessel spraying system (a special safety facility) is not influenced. Even if the pressure peak value of the containment vessel is lower than the design pressure under the worst working condition (the main steam pipeline in the shell is large in break and cannot be isolated, the superposition blowout failure and the safety injection failure), the pressure in the containment vessel can still be maintained at a more favorable acceptable level in the long-term process after the accident, and the temperature is maintained below the design temperature of the containment vessel.
In summary, the post-accident extended application method of the nuclear power plant system specifically analyzes the post-accident extended application method of the nuclear power plant system from four aspects, namely an applicable working condition principle, a special safety facility limitation compensation measure requirement analysis method, a screening principle of an extended application system and a system extended application principle, so as to compensate the limitation of the special safety facility and perfect an accident handling strategy.
(1) The working condition principle is applied.
The post-accident expansion application method for the nuclear power plant system is suitable for accident handling of working conditions which simultaneously accord with the working condition application principle 1 and the working condition application principle 2, and analysis and design of limitation compensation measures of specially-designed safety facilities are developed.
(2) The method for analyzing the requirement of measures is compensated by the limitation of specially-designed safety facilities.
For the accident condition meeting the applicability of the post-accident expanded use method of the nuclear power plant system, the limitation of special safety facilities in the specific accident condition treatment is analyzed based on the method in the step S103, and an interface of the working condition requirement-system expanded use function is set for the expanded use of the nuclear power plant system.
(3) And expanding the screening principle of the application system.
And searching for the extended application system with matched functions according to the specific working condition requirements and the screening principle of the extended application system one by one based on the interface of the system extended use function, which is obtained by analysis, so as to obtain an extended application system list through screening.
(4) And determining a method for expanding the application of the nuclear power plant system after the accident according to the principle of the system expansion application.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (6)
1. A nuclear power plant system post-accident expansion application method is characterized by comprising the following steps:
analyzing to obtain an interface of a working condition requirement-system expansion use function;
based on the interface of the working condition requirement-system expansion use function, screening an expansion application system matched with the working condition requirement according to the screening principle of the expansion application system to obtain an expansion application system list under the accident working condition;
aiming at an extended application system list under an accident condition, according to a system extended application principle, carrying out analysis on an extended application method to obtain a post-accident extended application method of a nuclear power plant system, and forming an optimization treatment strategy aiming at a specific or emergency accident condition;
before the step of analyzing the interface of the working condition requirement-system expansion use function, the method further comprises the following steps:
judging whether the accident condition is suitable for post-accident expanded application of the nuclear power plant system according to an applicable condition principle, if so, executing the step of analyzing to obtain a condition requirement-system expanded use function interface, and if not, using a corresponding special safety facility, a reactivity control system or a reactor protection system according to the design condition of the nuclear power plant system to deal with the accident;
the method comprises the following steps of judging whether the accident condition is suitable for the post-accident expansion application of the nuclear power plant system according to an applicable condition principle:
when the accident working condition conforms to the applicable working condition principle 1 and the applicable working condition principle 2, judging that the accident working condition is suitable for extended application, otherwise, judging that the accident working condition is not suitable for extended application;
the principle 1 of the applicable working condition is a severe working condition, the principle 2 of the applicable working condition is a complex working condition, the influence of the working condition on the function damage to the special safety facility and the safety shell is about to occur or is caused, and the principle is any one of special working conditions;
according to the classification of the applicable working conditions, the extended application system is in accordance with one of the following screening principles 1 to 3:
the screening principle 1 is that the system is used as a direct replacement or low-quality replacement system of a support system of the special safety facility in function or is used as a functional replacement of the special safety facility in function;
the screening principle 2 is a system related to the air circulation, filtering ventilation, sealing or heat removal and pressure reduction functions of the containment;
the screening principle 3 is that for special working conditions which do not belong to the design and the response of the special safety facilities, a system or equipment with strong function pertinence and relatively low operation cost is selected;
the system expansion application principle comprises expansion application principles 1 to 6:
the extended application principle 1 is that in an emergency or severe accident condition, a relevant system is used in a working condition of a non-design operation condition on the basis of necessity analysis and expected effect evaluation;
the expanded application principle 2 is that under the accident condition, aiming at the emergency situation that the support system of the special safety facility fails, the support system with the quality lower than the design standard is used to provide support for the operation of the special safety facility;
the expansion application principle 3 is that under the accident condition, aiming at the condition that the special safety facilities fail, other related systems with overlapped or similar functions are used to achieve the effect of temporarily replacing the execution function;
the application principle 4 is expanded, for the severe working condition threatening the function of the containment vessel, the radioactive leakage is prevented and controlled to the maximum extent, the integrity of the last barrier is protected, and the related system is put into operation in the working condition exceeding the designed use condition according to the operation working condition;
the application principle 5 is expanded, for the severe working condition threatening the function of the containment vessel, the radioactive leakage is prevented and controlled to the maximum extent, the integrity of the last barrier is protected, and the related system is manually put into operation according to the operation working condition before reaching the starting threshold;
the extended application principle 6 is that for the severe working conditions threatening the function of the containment, radioactive leakage should be prevented and controlled to the maximum extent, the integrity of the last barrier is protected, and a system which is overlapped with the function of the related special safety facilities is considered to be put into operation with the special safety facilities in parallel according to the operation working conditions so as to functionally cooperate with or reserve the special safety facilities.
2. The extended application method according to claim 1, wherein the step of analyzing the interface of the working condition requirement-system extended use function is specifically:
based on the processing requirement condition of the accident condition, the functional limitations of the special safety facilities and the safety shell are analyzed in the specific accident condition processing, the special condition requirements are analyzed, and the requirement key points existing in the accident condition processing are classified and combined to form an interface of the working condition requirement-system expansion use function.
3. The extended application method according to claim 2, wherein the method for analyzing the functional limitations of the special safety facilities and the safety shell in the specific accident condition treatment and analyzing the special condition requirements specifically comprises the following steps:
if the accident condition treatment is related to the function of the special safety facility, analyzing whether the accident treatment requirements of containment spraying, auxiliary water supply and safe injection exist;
if the accident condition processing is related to the containment function, analyzing whether the accident processing requirements of containment integrity maintenance, containment tightness, containment air circulation and containment long-term heat extraction exist;
and if the special working condition requirements exist, specifically analyzing and determining the special accident handling requirements of the working conditions.
4. The extended application method of claim 3,
the analysis of whether accident handling requirements of containment spraying exist specifically comprises the following steps: analyzing whether partial or total loss of the containment spraying exists or not and whether the containment spraying function is influenced by the loss of the support system exists or not;
the analysis of whether the accident treatment requirement of auxiliary water supply exists is specifically as follows: analyzing whether auxiliary water supply cannot meet the accident handling requirement or not and whether the auxiliary water supply function is influenced by losing a support system or not;
the analysis of whether the accident handling requirement of safe injection exists is specifically as follows: analyzing whether partial or total loss of safety injection exists or not, and whether the safety injection function is influenced by the loss of a support system exists or not;
the analysis of whether the accident handling requirement for maintaining the integrity of the containment vessel exists is specifically as follows: and analyzing whether the pressure and the temperature in the containment vessel exceed the design permission conditions in the accident condition.
5. The extended application method according to claim 1, wherein in the step of performing the analysis of the extended application method according to the system extended application principle on the extended application system list under the accident condition, the adopted analysis items include: the system expands the working condition that the application is suitable for; the system expansion application principle to be adopted; analyzing the necessity of expanding the application of the system; the specific method of the system expansion application; the system extends the intended effect of the application.
6. The extended application method of claim 1, wherein for the applicable condition principle 1, the severe condition means that the accident condition has caused a severe influence, or if a mitigating measure is not taken in time, the possibility of developing the severe influence is existed, and the severe influence means that the damage degree of the accident reaches or exceeds the design reference; for the applicable working condition principle 2, the complex working condition refers to the fact that multiple aspects to be urgently controlled or relieved exist in the accident working condition, and the special working condition refers to the fact that the accident working condition does not belong to the working condition of special safety facility design coping, and the special safety facility cannot be effectively processed.
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