CN106529834B - Assessment method and system for safety state of nuclear power station and nuclear power station equipment - Google Patents
Assessment method and system for safety state of nuclear power station and nuclear power station equipment Download PDFInfo
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Abstract
The invention relates to the technical field of nuclear power station safety, and discloses a method and a system for evaluating the safety state of a nuclear power station and nuclear power station equipment. The assessment method of the safety state of the nuclear power station comprises the following steps: acquiring the running states of all nuclear power station safety parameters in a pre-established nuclear power station safety parameter logical relation model; performing safety level evaluation on the obtained running states of all the safety parameters of the nuclear power station according to preset safety evaluation rules and safety levels of the safety parameters of the nuclear power station so as to obtain the safety levels of all the safety parameters of the nuclear power station; and performing logical operation processing on the obtained safety levels of all the nuclear power station safety parameters according to the safety parameter logical relation in the established nuclear power station safety parameter logical relation model so as to obtain the safety level of the whole safety state of the nuclear power station. Compared with the prior art, the method and the device improve the convenience, accuracy and reliability of the safety state evaluation of the nuclear power station, and improve the safety and reliability of the nuclear power station.
Description
Technical Field
The invention relates to the technical field of nuclear power station safety, in particular to a method and a system for evaluating the safety state of a nuclear power station and nuclear power station equipment.
Background
In the field of nuclear power plant safety analysis, generally, a Real-time Information Monitoring System (Real-time Information Monitoring System) is used to obtain the operation data of a nuclear power plant in Real time, and a cai (clip-orientation-event, point-Argument) System Argument structure is used to perform Argument analysis on the operation data of the nuclear power plant obtained in Real time, so as to deduce the overall safety state of the nuclear power plant. Because the nuclear power plant system is a system with large scale, numerous devices and complex internal structure relationship, the safety state of the nuclear power plant cannot be directly detected, and the operation state can be systematically inferred and evaluated only by monitoring operation data.
According to the conventional nuclear power station safety state evaluation method, a safety threshold is set for safety parameters, when the condition that the safety parameters exceed the safety threshold and are evaluated as equipment faults or system failures and alarms is detected, normal operation parameter fluctuation easily triggers the alarm, and the accuracy and the reliability of the nuclear power station safety state evaluation are low. In addition, the safety state evaluation of the existing nuclear power plant mainly focuses on the safety state evaluation of individual key equipment, a specific subsystem or performance of a certain aspect, and the safety logic relationship of all safety parameters of the system nuclear power plant cannot be grasped on the whole, so that the accuracy and reliability of the safety state evaluation of the existing nuclear power plant are low.
Disclosure of Invention
In view of this, the invention provides a method and a system for evaluating a safety state of a nuclear power plant, and a nuclear power plant device, which solve the technical problems of low accuracy and reliability of safety state evaluation of the existing nuclear power plant.
According to an embodiment of the present invention, there is provided a method for evaluating a safety state of a nuclear power plant, including: acquiring the running states of all nuclear power station safety parameters in a pre-established nuclear power station safety parameter logical relation model; according to a preset safety assessment rule and a preset safety level of the nuclear power station safety parameters, carrying out safety level assessment on the operation states of all the nuclear power station safety parameters in the pre-established nuclear power station safety parameter logical relationship model so as to obtain the safety levels of all the nuclear power station safety parameters; and performing logical operation processing on the obtained safety levels of all the safety parameters of the nuclear power station according to the safety parameter logical relation in the pre-established nuclear power station safety parameter logical relation model so as to obtain the safety level of the whole safety state of the nuclear power station.
Preferably, the method for evaluating the safety state of the nuclear power plant further includes: establishing a nuclear power station safety parameter logical relationship model, wherein the establishing of the nuclear power station safety parameter logical relationship model further comprises the following steps: acquiring a logic relation between a safety parameter of a nuclear power station and the safety parameter; classifying the acquired nuclear power station safety parameters into overall state parameters, functional state parameters and process state parameters; and acquiring the logic relationship among the classified overall state parameter, the function state parameter and the process state parameter according to the acquired logic relationship among the safety parameters.
Preferably, the performing logic operation processing on the obtained safety levels of all the safety parameters of the nuclear power plant according to the safety parameter logic relationship in the pre-established nuclear power plant safety parameter logic relationship model to obtain the safety level of the whole safety state of the nuclear power plant includes: performing logic and operation processing on the obtained safety level of the process state parameter according to the logic relation between the process state parameter and the function state parameter to obtain the safety level of the function state parameter; and performing logic and operation processing on the obtained safety level of the functional state parameter according to the logic relation between the functional state parameter and the overall state parameter so as to obtain the safety level of the overall state parameter.
Preferably, the method for evaluating the safety state of the nuclear power plant further includes: setting safety assessment rules and safety levels of safety parameters of the nuclear power station, wherein the setting of the safety assessment rules and the safety levels of the safety parameters of the nuclear power station further comprises the following steps: setting a safety evaluation rule according to the functional requirements and the performance level of the safety parameters of the nuclear power station; and correspondingly setting a plurality of safety levels according to the set safety evaluation rule.
Preferably, after the logic operation processing is performed on the obtained safety levels of all the safety parameters of the nuclear power plant according to the safety parameter logic relationship in the pre-established nuclear power plant safety parameter logic relationship model to obtain the safety level of the overall safety state of the nuclear power plant, the method further includes: storing the obtained safety level data of the whole safety state of the nuclear power station and the obtained safety level data of all the safety parameters of the nuclear power station; and analyzing the stored safety level data of the whole safety state of the nuclear power station and the corresponding safety level data of all the safety parameters of the nuclear power station to extract the lowest safety level data and the corresponding safety parameters.
According to another embodiment of the present invention, there is provided a system for evaluating a safety state of a nuclear power plant, including: the operation state acquisition module is used for acquiring the operation states of all the nuclear power station safety parameters in the nuclear power station safety parameter logical relation model established by the preset model establishment module; the safety level evaluation module is used for evaluating the safety levels of the running states of all the nuclear power station safety parameters in the nuclear power station safety parameter logic relation model established by the preset model establishing module and acquired by the running state acquisition module according to the safety evaluation rules and the safety levels of the nuclear power station safety parameters set by the preset evaluation setting module so as to acquire the safety levels of all the nuclear power station safety parameters; and the safety level processing module is used for carrying out logical operation processing on the safety levels of all the nuclear power station safety parameters acquired by the safety level evaluation module according to the safety parameter logical relationship in the nuclear power station safety parameter logical relationship model established by the preset model establishing module so as to acquire the safety level of the whole safety state of the nuclear power station.
Preferably, the evaluation system for the safety state of the nuclear power plant further includes a model building module, and the model building module includes: the first acquisition unit is used for acquiring the safety parameters of the nuclear power station and the logic relation of the safety parameters; the classification unit is used for classifying the acquired nuclear power station safety parameters into overall state parameters, functional state parameters and process state parameters; and the second acquisition unit is used for acquiring the logic relationship among the whole state parameter, the functional state parameter and the process state parameter classified by the classification unit according to the logic relationship among the safety parameters acquired by the first acquisition unit.
Preferably, the security level processing module includes: the first processing unit is used for carrying out logic and operation processing on the safety level of the process state parameter acquired by the safety level evaluation module according to the logic relation between the process state parameter and the function state parameter acquired by the second acquisition unit so as to acquire the safety level of the function state parameter; and the second processing unit is used for carrying out logic and operation processing on the safety level of the functional state parameter acquired by the first processing unit according to the logic relation between the functional state parameter acquired by the second acquiring unit and the overall state parameter so as to acquire the safety level of the overall state parameter.
Preferably, the evaluation system for the safety state of the nuclear power plant further includes: the storage module is used for storing the safety level data of the whole safety state of the nuclear power station acquired by the safety level processing module and the safety level data of all the safety parameters of the nuclear power station acquired by the safety level evaluation module; and the analysis module is used for analyzing the safety level data of the whole safety state of the nuclear power station and the corresponding safety level data of all the safety parameters of the nuclear power station, which are stored by the storage module, so as to extract the lowest safety level data and the corresponding safety parameters.
According to still another embodiment of the present invention, there is provided a nuclear power plant equipment including the above-described evaluation system of a nuclear power plant safety state.
The invention provides an assessment method, a system and nuclear power station equipment for the safety state of a nuclear power station, which are characterized in that the running states of all nuclear power station safety parameters in a pre-established nuclear power station safety parameter logical relationship model are obtained, the safety level assessment is carried out on the running states of all nuclear power station safety parameters in the obtained pre-established nuclear power station safety parameter logical relationship model according to the safety assessment rules and the safety levels of the pre-established nuclear power station safety parameters to obtain the safety levels of all nuclear power station safety parameters, the logic operation processing is carried out on the obtained safety levels of all nuclear power station safety parameters according to the safety parameter logical relationship in the pre-established nuclear power station safety parameter logical relationship model to obtain the safety levels of the whole safety state of the nuclear power station, and the safety levels of the whole state parameters at the top layer are deduced upwards step by step through the safety levels of the state parameters at the bottom layer, the safety management personnel of the nuclear power station can accurately evaluate the safety state of the current nuclear power station according to the safety level of the whole state parameters, so that the early functional degradation and equipment failure of the nuclear power station can be found in time and the nuclear power station can be maintained and checked emergently, the convenience, the accuracy and the reliability of the safety state evaluation of the nuclear power station are improved, and the safety and the reliability of the nuclear power station are improved.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings used in the description of the embodiments will be briefly introduced below. It is obvious that the drawings in the following description are only some embodiments of the invention, and that for a person skilled in the art, other drawings can be derived from them without inventive effort.
Fig. 1 is a schematic flow chart of a method for evaluating the safety state of a nuclear power plant according to an embodiment of the present invention.
Fig. 2 is a schematic flow chart illustrating the process of establishing a nuclear power plant safety parameter logical relationship model according to an embodiment of the present invention.
Fig. 3 is a schematic flow chart illustrating setting of safety evaluation rules and safety levels of safety parameters of a nuclear power plant according to an embodiment of the present invention.
FIG. 4 is a diagram illustrating security evaluation rules and security levels in one embodiment of the invention.
Fig. 5 is a schematic flow chart illustrating a logic operation process to obtain a safety level of an overall safety state of a nuclear power plant according to an embodiment of the present invention.
FIG. 6 is a schematic diagram of the logical relationship of safety parameters of a nuclear power plant according to an embodiment of the present invention.
Fig. 7 is a flowchart illustrating a method for evaluating a safety state of a nuclear power plant according to another embodiment of the present invention.
Fig. 8 is a schematic structural diagram of a system for evaluating the safety state of a nuclear power plant according to an embodiment of the present invention.
FIG. 9 is a block diagram of a model building module according to an embodiment of the present invention.
Fig. 10 is a schematic structural diagram of a security level processing module according to an embodiment of the present invention.
Fig. 11 is a schematic structural diagram of a system for evaluating the safety state of a nuclear power plant according to another embodiment of the present invention.
Fig. 12 is a schematic diagram showing the structure of a nuclear power plant according to still another embodiment of the present invention.
Detailed Description
The technical scheme of the invention is further described in more detail by combining the attached drawings and the detailed description. It is to be understood that the described embodiments are merely a few embodiments of the invention, and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
In the description of the present invention, it is to be understood that the terms "first," "second," and the like 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 is to be noted that, unless otherwise explicitly specified or limited, the terms "connected" and "connected" are to be interpreted broadly, e.g., as being fixed or detachable or integrally connected; can be mechanically or electrically connected; may be directly connected or indirectly connected through an intermediate. To those of ordinary skill in the art, the specific meanings of the above terms in the present invention can be understood in conjunction with specific situations. In addition, in the description of the present invention, "a plurality" means two or more unless otherwise specified.
Any process or method descriptions in flow charts or otherwise described herein may be understood as representing modules, segments, or portions of code which include one or more executable instructions for implementing specific logical functions or steps of the process, and alternate implementations are included within the scope of the preferred embodiment of the present invention in which functions may be executed out of order from that shown or discussed, including substantially concurrently or in reverse order, depending on the functionality involved, as would be understood by those reasonably skilled in the art of the present invention.
Fig. 1 is a schematic flow chart of a method for evaluating a safety state of a nuclear power plant according to an embodiment of the present invention.
As shown in the figure, the method for evaluating the safety state of the nuclear power plant includes:
step S101: and acquiring the running states of all the safety parameters of the nuclear power station in the pre-established logical relation model of the safety parameters of the nuclear power station.
In this embodiment, a nuclear power plant safety parameter logical relationship model is first established based on the system structure and the operating characteristics of the nuclear power plant. Referring to fig. 2, the establishing a nuclear power plant safety parameter logical relationship model includes:
step S201: and acquiring the safety parameters of the nuclear power station and the logic relation of the safety parameters.
Step S202: the acquired nuclear power station safety parameters are classified into overall state parameters, functional state parameters and process state parameters.
Step S203: and acquiring the logic relation among the classified overall state parameters, the classified functional state parameters and the classified process state parameters according to the acquired logic relation among the safety parameters.
In this embodiment, safety parameters affecting the safety of the nuclear power plant are classified into three types according to their hierarchical characteristics: global state parameters, functional state parameters, and process state parameters. The overall state parameter characterizes an overall operating state of the nuclear power plant, such as reactor power. The functional state parameter characterizes a maintenance state of an important function or sub-function in an overall state of different levels, such as a steam generator water level of a steam generator operating state or the like. The process state parameters are parameter information which can be directly obtained or determined by field operation and experimenters, such as equipment operation monitoring parameters, the availability of a certain system of redundancy or protection systems and the like. After the logical relationship of the safety parameters is obtained based on the system structure and the operating characteristics of the nuclear power station, the logical relationships of the classified overall state parameters, the classified functional state parameters and the classified process state parameters are further obtained, and finally a three-layer nuclear power station safety parameter logical relationship model structure is formed.
In this embodiment, after the nuclear power plant safety parameter logical relationship model is established, the actual operation conditions of the nuclear power plant are detected on site and monitored remotely, and the actual operation states of all the bottom layer process state parameters that can affect the overall safety of the nuclear power plant are obtained to be used as the basis for subsequent overall safety state evaluation.
Step S102: and evaluating the safety levels of the running states of all the safety parameters of the nuclear power station in the pre-established nuclear power station safety parameter logic relation model according to the preset safety evaluation rules and safety levels of the safety parameters of the nuclear power station so as to obtain the safety levels of all the safety parameters of the nuclear power station.
Before the safety state of the nuclear power plant is evaluated, safety evaluation rules and safety levels of safety parameters of the nuclear power plant are preset. Referring to fig. 3, the setting of the safety assessment rules and the safety levels of the safety parameters of the nuclear power plant includes:
step S301: and setting safety evaluation rules according to the functional requirements and the performance level of the safety parameters of the nuclear power station.
Specifically, safety evaluation rules of the safety parameters of the nuclear power plant can be set according to the requirements of the functions or sub-functions of the nuclear power plant, the characteristics of the operation parameters, the realization and guarantee capabilities of the function targets, the operation range of the key parameters, the equipment operation performance degradation and state degradation caused by the degradation degree and other factors.
Step S302: and correspondingly setting a plurality of safety levels according to the set safety evaluation rule.
Referring to fig. 4, for convenience of evaluation, A, B, C, D four security levels from high to low are set according to the set security evaluation rule. Wherein, the safety evaluation rule of the safety level A is as follows: the method can meet the specified functional requirements, has good operation performance level and has no obviously increased risk; the security evaluation rule of the security level B is as follows: the method can meet the specified functional requirements, the running performance is slightly degraded, the local part of the running performance possibly exceeds the normal range, but the realization of the target function is not obviously influenced; the security evaluation rule of the security level C is as follows: basically meeting the specified functional requirements, but obviously deteriorating the running performance, having obvious threat to the realization of the functional target, needing to pay attention, and taking measures to recover the state in time if necessary; the safety evaluation rule of the safety level D is as follows: the functional objective is significantly affected or performance degraded to an unacceptable level and needs to be immediately addressed. By setting the safety assessment rules and the safety levels of the safety parameters of the nuclear power station, the safety parameters of the nuclear power station in the nuclear power station safety parameter logical relationship model can be quantified through the safety levels, and the accuracy and the reliability of the safety state assessment of the nuclear power station are improved.
In this embodiment, after the safety evaluation rule and the safety level of the safety parameter of the nuclear power station are preset and the operation state of the safety parameter during actual operation of the nuclear power station is obtained, the obtained operation state of the safety parameter of the nuclear power station may be matched with the preset functional requirement, performance level and other factors of the corresponding safety parameter, so as to obtain the safety level of the process state parameter of the current bottom layer of the nuclear power station. For example, in the logic relationship diagram of the three-layer safety parameters in fig. 6, the operation states of the process safety parameters E1 and E2 … En are obtained, and are matched with the preset safety evaluation rules and safety levels of the power station safety parameters, and finally the safety levels corresponding to the process safety parameters E1 and E2 … En are obtained, for example, E1 is the a safety level, and E2 is the B safety level.
Step S103: and performing logical operation processing on the obtained safety levels of all the safety parameters of the nuclear power station according to the safety parameter logical relation in the pre-established nuclear power station safety parameter logical relation model so as to obtain the safety level of the whole safety state of the nuclear power station.
After the safety levels of the process state parameters of all the nuclear power station bottom layers are obtained, logic operation processing is carried out on the obtained safety levels of all the nuclear power station safety parameters according to the safety parameter logic relation in the pre-established nuclear power station safety parameter logic relation model, so that the safety level of the whole safety state of the nuclear power station is obtained. Referring to fig. 5, the performing logic operation processing to obtain the safety level of the overall safety state of the nuclear power plant includes:
step S401: and carrying out logic and operation processing on the obtained safety level of the process state parameter according to the logic relation between the process state parameter and the function state parameter so as to obtain the safety level of the function state parameter.
Referring to fig. 6, in the logical relationship diagram of the three-layer security parameters, a plurality of bottom-layer process state parameters E1 and E2 … En support a top-layer functional state parameter C1 as evidence, a plurality of middle-layer functional state parameters C1 and C2 … Cn support a top-layer global state parameter C as an argument, and the security level of the top-layer global state parameter is derived by gradually demonstrating upwards from the security level of the bottom-layer process state parameter. For example, assuming that the bottom-layer process status parameter E1 is a security level a, and E2 is a security level B, the security level of the function status parameter C1 corresponding to the upper layer thereof can be processed by the logical and operation of the two parameters: e1(a) & E2(B) ═ C1(B), that is, the security level to the upper layer function status parameter C1 is B.
Step S402: and performing logic and operation processing on the obtained safety level of the functional state parameter according to the logic relation between the functional state parameter and the overall state parameter so as to obtain the safety level of the overall state parameter.
Similarly, assuming that the security level of the obtained middle-layer functional state parameter C1 is B, the security level of C2 is a, the security level of Cn is D, and the other security levels are C, the logical and operation of the security level of the whole state parameter of the top-layer C derived by upward demonstration from the security level of the middle-layer process state parameter is: c1(B) & C2(a) & … cn (D) ═ C (D), that is, the security level of the acquired top-level overall state parameter C is D. In the embodiment, the safety level of the whole state parameter of the top layer is deduced and deduced upwards step by step through the safety level of the state parameter of the bottom layer process, so that the safety management personnel of the nuclear power station can accurately evaluate the safety state of the current nuclear power station according to the safety level of the whole state parameter, the early function degradation and equipment failure of the nuclear power station can be conveniently found in time and emergently maintained and checked, the convenience, the accuracy and the reliability of the evaluation of the safety state of the nuclear power station are improved, and the safety and the reliability of the nuclear power station are improved.
In the method for evaluating the safety state of the nuclear power plant of this embodiment, the operation states of all the safety parameters of the nuclear power plant in the pre-established nuclear power plant safety parameter logical relationship model are obtained, the safety levels of all the safety parameters of the nuclear power plant in the pre-established nuclear power plant safety parameter logical relationship model are evaluated according to the safety evaluation rules and the safety levels of the pre-established nuclear power plant safety parameters to obtain the safety levels of all the safety parameters of the nuclear power plant, the safety levels of all the safety parameters of the nuclear power plant are processed by logical operations according to the safety parameter logical relationship in the pre-established nuclear power plant safety parameter logical relationship model to obtain the safety levels of the whole safety state of the nuclear power plant, the safety levels of the bottom layer process state parameters are used for upwards demonstrating and deducing the safety levels of the top layer whole state parameters step by step, the safety management personnel of the nuclear power station can accurately evaluate the safety state of the current nuclear power station according to the safety level of the whole state parameters, so that the early functional degradation and equipment failure of the nuclear power station can be found in time and the emergency maintenance and troubleshooting are facilitated, the convenience, the accuracy and the reliability of the evaluation of the safety state of the nuclear power station are improved, and the safety and the reliability of the nuclear power station are improved.
Fig. 7 is a flowchart illustrating a method for evaluating a safety state of a nuclear power plant according to another embodiment of the present invention. As shown in the figure, the method for evaluating the safety state of the nuclear power plant includes:
step S501: and acquiring the running states of all the safety parameters of the nuclear power station in the pre-established logical relation model of the safety parameters of the nuclear power station.
Step S502: and evaluating the safety levels of the running states of all the safety parameters of the nuclear power station in the pre-established nuclear power station safety parameter logic relation model according to the preset safety evaluation rules and safety levels of the safety parameters of the nuclear power station so as to obtain the safety levels of all the safety parameters of the nuclear power station.
Step S503: and performing logical operation processing on the obtained safety levels of all the safety parameters of the nuclear power station according to the safety parameter logical relation in the pre-established nuclear power station safety parameter logical relation model so as to obtain the safety level of the whole safety state of the nuclear power station.
Step S504: and storing the obtained safety level data of the whole safety state of the nuclear power station and the obtained safety level data of all the safety parameters of the nuclear power station.
Step S505: and analyzing the stored safety level data of the whole safety state of the nuclear power station and the corresponding safety level data of all the safety parameters of the nuclear power station to extract the lowest safety level data and the corresponding safety parameters.
In this embodiment, on the basis of obtaining the safety level of the overall safety state of the nuclear power plant in the above embodiment, the obtained safety level data of the overall safety state of the nuclear power plant and the obtained safety level data of all safety parameters of the nuclear power plant are further stored, and the stored safety level data of the overall safety state of the nuclear power plant and the safety level data of all corresponding safety parameters of the nuclear power plant are analyzed to extract the lowest safety level data and the corresponding safety parameters thereof, and when the obtained safety level of the overall safety state of the nuclear power plant is lower, the lowest safety level data and the corresponding safety parameters thereof are automatically analyzed and extracted, so that a safety manager of the nuclear power plant can quickly find the safety parameters causing the lower safety level of the overall safety state, quickly detect and maintain the safety parameters and timely remove equipment faults, thereby improving convenience, safety state evaluation, and the like of the nuclear power plant, Accuracy and reliability, the security and the reliability of nuclear power station have been promoted.
Fig. 8 is a schematic structural diagram of a system for evaluating the safety state of a nuclear power plant according to an embodiment of the present invention. As shown, the evaluation system 100 for the safety state of the nuclear power plant includes an operation state obtaining module 10, a safety level evaluation module 20, and a safety level processing module 30.
In this embodiment, a nuclear power plant safety parameter logical relationship model is first established by a model establishing module based on the system structure and the operating characteristics of the nuclear power plant. Referring to fig. 9, the model building module 40 includes a first obtaining unit 401, a classifying unit 402, and a second obtaining unit 403.
In this embodiment, the classifying unit 402 classifies the safety parameters affecting the safety of the nuclear power plant into three types according to the hierarchical characteristics of the safety parameters: global state parameters, functional state parameters, and process state parameters. The overall state parameter characterizes an overall operating state of the nuclear power plant, such as reactor power. The functional state parameter characterizes a maintenance state of an important function or sub-function in an overall state of different levels, such as a steam generator water level of a steam generator operating state or the like. The process state parameters are parameter information which can be directly obtained or determined by field operation and experimenters, such as equipment operation monitoring parameters, the availability of a certain system of redundancy or protection systems and the like. After the first obtaining unit 401 obtains the logical relationship of the safety parameters based on the system structure and the operating characteristics of the nuclear power plant, the second obtaining unit 403 further obtains the logical relationship of the overall state parameters, the functional state parameters and the process state parameters classified by the classifying unit 402, and finally forms a three-layer nuclear power plant safety parameter logical relationship model structure.
Before the safety level evaluation module 20 evaluates the safety state of the nuclear power plant, safety evaluation rules and safety levels of safety parameters of the nuclear power plant need to be preset through an evaluation setting module. Specifically, the evaluation setting module may set a safety evaluation rule of the safety parameters of the nuclear power plant according to the requirements of the functions or sub-functions of the nuclear power plant, the characteristics of the operation parameters, the realization and guarantee capability of the function targets, the operation range of the key parameters, the equipment operation performance degradation and state degradation caused by the degradation degree, and other factors. For evaluation, the evaluation setting module also correspondingly sets A, B, C, D four security levels from high to low according to the set security evaluation rules. Wherein, the safety evaluation rule of the safety level A is as follows: the method can meet the specified functional requirements, has good operation performance level and has no obviously increased risk; the safety evaluation rule of the B safety level is as follows: the method can meet the specified functional requirements, the running performance is slightly degraded, the local part of the running performance possibly exceeds the normal range, but the realization of the target function is not obviously influenced; the security evaluation rule of the security level C is as follows: basically meeting the specified functional requirements, but obviously deteriorating the running performance, having obvious threat to the realization of the functional target, needing to pay attention, and taking measures to recover the state in time if necessary; the safety evaluation rule of the safety level D is as follows: the functional objective is significantly affected or performance degraded to an unacceptable level and needs to be immediately addressed. Safety assessment rules and safety levels of the safety parameters of the nuclear power station are preset through the assessment setting module, so that the safety parameters of the nuclear power station in the nuclear power station safety parameter logic relation model can be quantified through the safety levels, and the accuracy and reliability of the assessment of the safety state of the nuclear power station are improved.
In this embodiment, after the model building module 40 builds the nuclear power plant safety parameter logical relationship model, the operation state obtaining module 10 obtains the actual operation states of all the bottom layer process state parameters that may affect the overall safety of the nuclear power plant by detecting and remotely monitoring the actual operation conditions of the nuclear power plant on site, so as to be used as the basis for subsequent overall safety state evaluation.
In this embodiment, after the evaluation setting module sets the safety evaluation rule and the safety level of the safety parameter of the nuclear power plant and the operation state obtaining module 10 obtains the operation state of the safety parameter during the actual operation of the nuclear power plant, the safety level evaluation module 20 may match the operation state of the safety parameter of the nuclear power plant obtained by the operation state obtaining module 10 with the functional requirement, the performance level and other factors of the corresponding safety parameter preset by the evaluation setting module, so as to obtain the safety level of the process state parameter of the current bottom layer of the nuclear power plant. For example, in a logic relationship diagram of three-layer safety parameters, the operation state obtaining module 10 obtains the operation states of the process safety parameters E1 and E2 … En, the safety level evaluating module 20 matches the operation states with the safety evaluation rules and the safety levels of the power station safety parameters preset by the evaluation setting module, and finally the safety level evaluating module 20 obtains the safety levels corresponding to the process safety parameters E1 and E2 … En, for example, E1 is a safety level and E2 is a B safety level.
After the safety level evaluation module 20 obtains the safety levels of the process state parameters of all the bottom layers of the nuclear power plants, the safety level processing module 30 performs logical operation processing on the safety levels of all the nuclear power plant safety parameters obtained by the safety level evaluation module 20 according to the safety parameter logical relationship in the nuclear power plant safety parameter logical relationship model established by the model establishing module 40, so as to obtain the safety level of the whole safety state of the nuclear power plant. Referring to fig. 10, the security level processing module 30 includes a first processing unit 301 and a second processing unit 302.
The first processing unit 301 is configured to perform a logical and operation process on the security level of the process status parameter acquired by the security level evaluation module 20 according to the logical relationship between the process status parameter and the function status parameter acquired by the second acquiring unit 403, so as to acquire the security level of the function status parameter; the second processing unit 302 is configured to perform a logical and operation on the security level of the functional status parameter obtained by the first processing unit 301 according to the logical relationship between the functional status parameter obtained by the second obtaining unit 403 and the overall status parameter, so as to obtain the security level of the overall status parameter.
In the logical relationship diagram of the three-layer security parameters, the plurality of bottom-layer process state parameters E1, E2 … En support the upper-layer functional state parameter C1 as evidence, and the plurality of middle-layer functional state parameters C1, C2 … Cn support the top-layer global state parameter C as evidence, and the first processing unit 301 and the second processing unit 302 derive the security level of the top-layer global state parameter by gradually demonstrating upwards from the security level of the bottom-layer process state parameter. For example, assuming that the bottom-layer process status parameter E1 is a security level a and the bottom-layer process status parameter E2 is a security level B, the security level of the functional status parameter C1 corresponding to the upper layer by the first processing unit 301 can be processed by the logical and operation of the two levels: e1(a) & E2(B) ═ C1(B), that is, the security level of the upper layer function state parameter C1 acquired by the first processing unit 301 is B.
Similarly, assuming that the first processing unit 301 deduces that the security level of the acquired middle layer functional state parameter C1 is B, the security level of C2 is a, the security level of Cn is D, and the other security levels are C, the logical and operation of the second processing unit 302 deducing the security level of the whole state parameter of the top layer C from the security level of the middle layer process state parameter through upward demonstration is as follows: c1(B) & C2(a) & … cn (D) ═ C (D), that is, the security level of the top-level overall state parameter C obtained by the second processing unit 302 is D. In this embodiment, the safety level processing module 30 gradually and upwards demonstrates and deduces the safety level of the top-layer overall state parameter according to the safety level of the bottom-layer process state parameter, so that a safety manager of the nuclear power plant can accurately evaluate the safety state of the current nuclear power plant according to the safety level of the overall state parameter, thereby being convenient for timely finding early functional degradation and equipment failure of the nuclear power plant and carrying out emergency maintenance and troubleshooting, improving the convenience, accuracy and reliability of evaluation of the safety state of the nuclear power plant, and improving the safety and reliability of the nuclear power plant.
In the system 100 for evaluating the safety state of a nuclear power plant of this embodiment, the operation state obtaining module 10 obtains the operation states of all the safety parameters of the nuclear power plant in the logical relationship model of the safety parameters of the nuclear power plant established by the preset model establishing module, the safety level evaluating module 20 evaluates the safety levels of the operation states of all the safety parameters of the nuclear power plant in the logical relationship model of the safety parameters of the nuclear power plant established in advance by the operation state obtaining module 10 according to the safety evaluation rules and the safety levels of the safety parameters of the nuclear power plant set by the preset evaluation setting module to obtain the safety levels of all the safety parameters of the nuclear power plant, the safety level processing module 30 performs logical operation processing on the safety levels of all the safety parameters of the nuclear power plant obtained by the safety level evaluating module 20 according to the safety parameter logical relationship in the logical relationship model of the safety parameters of the nuclear power plant established by the preset model establishing module to obtain the safety levels of the overall safety state of the nuclear power plant, the safety level of the whole state parameter of the top layer is deduced and deduced upwards step by step through the safety level of the state parameter of the bottom layer process, so that the safety management personnel of the nuclear power station can accurately evaluate the safety state of the current nuclear power station according to the safety level of the whole state parameter, the early function degradation and equipment failure of the nuclear power station can be conveniently found in time and emergently maintained and checked, the convenience, the accuracy and the reliability of the evaluation of the safety state of the nuclear power station are improved, and the safety and the reliability of the nuclear power station are improved.
Fig. 11 is a schematic structural diagram of a system for evaluating the safety state of a nuclear power plant according to another embodiment of the present invention. As shown in the figure, the evaluation system 100 for the safety state of the nuclear power plant includes an operation state obtaining module 10, a safety level evaluation module 20, a safety level processing module 30, a saving module 50, and an analysis module 60.
In this embodiment, on the basis that the safety level processing module 30 acquires the safety level of the overall safety state of the nuclear power plant in the above embodiment, the storage module 50 further stores the safety level data of the overall safety state of the nuclear power plant acquired by the safety level processing module 30 and the safety level data of all the safety parameters of the nuclear power plant acquired by the safety level evaluation module 20, the analysis module 60 analyzes the safety level data of the overall safety state of the nuclear power plant stored by the storage module 50 and the safety level data of all the corresponding safety parameters of the nuclear power plant to extract the lowest safety level data and the corresponding safety parameters, and when the safety level of the overall safety state of the nuclear power plant acquired by the safety level processing module 30 is lower, the analysis module 60 automatically analyzes and extracts the lowest safety level data and the corresponding safety parameters in the storage data of the storage module 50, the safety parameter that leads to the lower safety rating of whole safe state is found fast to nuclear power station safety control personnel of being convenient for and carry out quick detection and maintenance and get rid of equipment trouble in time, has improved the convenience, accuracy and the reliability of nuclear power station safe state aassessment, has promoted the security and the reliability of nuclear power station.
Fig. 12 is a schematic structural diagram of nuclear power plant equipment according to still another embodiment of the present invention. As shown in the figure, the nuclear power plant equipment 200 includes the evaluation system 100 for the safety state of the nuclear power plant described in the above embodiment, and the safety level of the overall state parameter at the top level of the nuclear power plant equipment 200 is derived by gradually demonstrating upwards through the safety level of the process state parameter at the bottom level of the nuclear power plant equipment 200, so that a safety manager of the nuclear power plant can accurately evaluate the safety state of the current nuclear power plant equipment 200 according to the safety level of the overall state parameter, thereby facilitating timely discovery of early functional degradation and equipment failure of the nuclear power plant equipment 200 and emergency maintenance and troubleshooting, improving the convenience, accuracy and reliability of the evaluation of the safety state of the nuclear power plant equipment 200, and improving the safety and reliability of the nuclear power plant equipment 200.
It should be understood that portions of the present invention may be implemented in hardware, software, firmware, or a combination thereof. In the above embodiments, the various steps or methods may be implemented in software or firmware stored in memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, any one or combination of the following techniques, which are known in the art, may be used: a discrete logic circuit having a logic gate circuit for implementing a logic function on a data signal, an application specific integrated circuit having an appropriate combinational logic gate circuit, a Programmable Gate Array (PGA), a Field Programmable Gate Array (FPGA), or the like.
In the description herein, references to the terms "one embodiment," "some embodiments," "an example," "a specific example," or "some examples" or the like, mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, the schematic representations of the terms used above do not necessarily refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples.
While embodiments of the invention have been shown and described, it will be understood by those of ordinary skill in the art that: various changes, modifications, substitutions and alterations can be made to the embodiments without departing from the principles and spirit of the invention, the scope of which is defined by the claims and their equivalents.
Claims (8)
1. A method for evaluating the safety state of a nuclear power plant is characterized by comprising the following steps:
acquiring the running states of all nuclear power station safety parameters in a pre-established nuclear power station safety parameter logic relation model;
according to a preset safety assessment rule and a preset safety level of the nuclear power station safety parameters, carrying out safety level assessment on the operation states of all the nuclear power station safety parameters in the pre-established nuclear power station safety parameter logical relationship model so as to obtain the safety levels of all the nuclear power station safety parameters; and
performing logical operation processing on the obtained safety levels of all the safety parameters of the nuclear power station according to the safety parameter logical relationship in the pre-established nuclear power station safety parameter logical relationship model to obtain the safety level of the whole safety state of the nuclear power station, wherein the logical operation processing method comprises the following steps: performing logic and operation processing on the obtained safety level of the process state parameter according to the logic relation between the process state parameter and the function state parameter to obtain the safety level of the function state parameter; and performing logic and operation processing on the security level of the acquired functional state parameter according to the logic relationship between the functional state parameter and the overall state parameter to acquire the security level of the overall state parameter.
2. The method for assessing the safety state of a nuclear power plant as recited in claim 1, further comprising: establishing a nuclear power station safety parameter logical relationship model, wherein the establishing of the nuclear power station safety parameter logical relationship model further comprises the following steps:
acquiring a safety parameter of a nuclear power station and a logic relation of the safety parameter;
classifying the acquired nuclear power station safety parameters into overall state parameters, functional state parameters and process state parameters; and
and acquiring the logic relation among the classified overall state parameters, the classified functional state parameters and the classified process state parameters according to the acquired logic relation among the safety parameters.
3. The method for assessing the safety state of a nuclear power plant as recited in claim 1, further comprising: setting safety assessment rules and safety levels of safety parameters of the nuclear power station, wherein the setting of the safety assessment rules and the safety levels of the safety parameters of the nuclear power station further comprises the following steps:
setting a safety evaluation rule according to the functional requirements and the performance level of the safety parameters of the nuclear power station; and
and correspondingly setting a plurality of safety levels according to the set safety evaluation rule.
4. The method for evaluating the safety state of the nuclear power plant according to claim 1, wherein after the logic operation processing is performed on the safety levels of all the acquired safety parameters of the nuclear power plant according to the safety parameter logic relationship in the established nuclear power plant safety parameter logic relationship model to acquire the safety level of the overall safety state of the nuclear power plant, the method further comprises:
storing the obtained safety level data of the whole safety state of the nuclear power station and the obtained safety level data of all the safety parameters of the nuclear power station;
and analyzing the stored safety level data of the whole safety state of the nuclear power station and the corresponding safety level data of all the safety parameters of the nuclear power station to extract the lowest safety level data and the corresponding safety parameters.
5. A system for evaluating the safety state of a nuclear power plant, comprising:
the operation state acquisition module is used for acquiring the operation states of all the nuclear power station safety parameters in the nuclear power station safety parameter logical relation model established by the preset model establishment module;
the safety level evaluation module is used for carrying out safety level evaluation on the running states of all the nuclear power station safety parameters in the nuclear power station safety parameter logical relation model established by the preset model establishing module and acquired by the running state acquisition module according to the safety evaluation rules and the safety levels of the nuclear power station safety parameters set by the preset evaluation setting module so as to acquire the safety levels of all the nuclear power station safety parameters; and
the safety level processing module is used for carrying out logical operation processing on the safety levels of all the safety parameters of the nuclear power station acquired by the safety level evaluation module according to the safety parameter logical relationship in the nuclear power station safety parameter logical relationship model established by the preset model establishing module so as to acquire the safety level of the whole safety state of the nuclear power station;
the security level processing module comprises:
the first processing unit is used for carrying out logic and operation processing on the safety level of the process state parameter acquired by the safety level evaluation module according to the logic relation between the process state parameter and the function state parameter acquired by the second acquisition unit so as to acquire the safety level of the function state parameter; and
and the second processing unit is used for carrying out logic and operation processing on the safety level of the functional state parameter acquired by the first processing unit according to the logic relation between the functional state parameter acquired by the second acquiring unit and the overall state parameter so as to acquire the safety level of the overall state parameter.
6. The system for assessing the safety state of a nuclear power plant according to claim 5, further comprising a model building module, said model building module comprising:
the first acquisition unit is used for acquiring the safety parameters of the nuclear power station and the logic relation of the safety parameters;
the classification unit is used for classifying the acquired nuclear power station safety parameters into overall state parameters, functional state parameters and process state parameters; and
and the second acquisition unit is used for acquiring the logic relationship among the whole state parameter, the functional state parameter and the process state parameter classified by the classification unit according to the logic relationship among the safety parameters acquired by the first acquisition unit.
7. The system for assessing the safety state of a nuclear power plant according to claim 5, further comprising:
the storage module is used for storing the safety level data of the whole safety state of the nuclear power station acquired by the safety level processing module and the safety level data of all the safety parameters of the nuclear power station acquired by the safety level evaluation module; and
and the analysis module is used for analyzing the safety level data of the whole safety state of the nuclear power station and the corresponding safety level data of all the safety parameters of the nuclear power station, which are stored by the storage module, so as to extract the lowest safety level data and the corresponding safety parameters.
8. Nuclear power plant equipment, characterized in that it comprises a system for assessing the safety status of a nuclear power plant as claimed in any one of claims 5 to 7.
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| PCT/CN2017/115056 WO2018103705A1 (en) | 2016-12-07 | 2017-12-07 | Method and system for evaluating safety state of nuclear power plant, and nuclear power plant device |
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| CN106529834B (en) * | 2016-12-07 | 2022-09-06 | 深圳中广核工程设计有限公司 | Assessment method and system for safety state of nuclear power station and nuclear power station equipment |
| CN107910086A (en) * | 2017-11-23 | 2018-04-13 | 中广核工程有限公司 | One kind is based on nuclear plant safety abnormal parameters condition adjudgement system and method |
| CN107808263B (en) * | 2017-12-01 | 2021-10-29 | 安徽中科超安科技有限公司 | Nuclear power station multi-risk comprehensive evaluation system and method based on information fusion |
| CN110766255B (en) * | 2018-07-27 | 2022-08-12 | 华龙国际核电技术有限公司 | Method and device for determining security level of item |
| CN111126810B (en) * | 2019-12-16 | 2023-08-22 | 国网河北省电力有限公司电力科学研究院 | Method for evaluating operation safety of source side generator set |
| CN112395744B (en) * | 2020-10-29 | 2023-12-05 | 华能国际电力股份有限公司玉环电厂 | Equipment safety online evaluation method and system for thermal power plant |
| CN114496325A (en) * | 2020-11-11 | 2022-05-13 | 中核核电运行管理有限公司 | Nuclear power plant field device state tracking control method |
| CN113110284B (en) * | 2021-04-30 | 2022-03-25 | 赵英田 | Integrated real-time operation monitoring method for hydrogen energy station |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1838161A (en) * | 2005-03-23 | 2006-09-27 | 大亚湾核电运营管理有限责任公司 | Method and apparatus for nuclear power station equipment risk evaluation by computer |
| CN101710400A (en) * | 2009-12-15 | 2010-05-19 | 中科华核电技术研究院有限公司 | Method and device for evaluating risk of nuclear power station |
| CN104425046A (en) * | 2013-08-31 | 2015-03-18 | 中广核工程有限公司 | Method and system for quantizing operation security indexes of nuclear power station |
| CN105955069A (en) * | 2016-06-12 | 2016-09-21 | 哈尔滨工程大学 | On-line-simulated-based nuclear power plant system level state monitoring method |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP1918869A1 (en) * | 2006-11-02 | 2008-05-07 | Abb Research Ltd. | Dynamic safety balance monitoring |
| CN103685490A (en) * | 2013-12-03 | 2014-03-26 | 中国核电工程有限公司 | Nuclear plant safety evaluating system and method |
| CN105425772B (en) * | 2014-11-28 | 2018-10-12 | 上海核工程研究设计院 | Nuclear power plant's methods of risk assessment of the failure tree reduction of logic-based equivalence |
| CN106529834B (en) * | 2016-12-07 | 2022-09-06 | 深圳中广核工程设计有限公司 | Assessment method and system for safety state of nuclear power station and nuclear power station equipment |
-
2016
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-
2017
- 2017-12-07 WO PCT/CN2017/115056 patent/WO2018103705A1/en active Application Filing
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1838161A (en) * | 2005-03-23 | 2006-09-27 | 大亚湾核电运营管理有限责任公司 | Method and apparatus for nuclear power station equipment risk evaluation by computer |
| CN101710400A (en) * | 2009-12-15 | 2010-05-19 | 中科华核电技术研究院有限公司 | Method and device for evaluating risk of nuclear power station |
| CN104425046A (en) * | 2013-08-31 | 2015-03-18 | 中广核工程有限公司 | Method and system for quantizing operation security indexes of nuclear power station |
| CN105955069A (en) * | 2016-06-12 | 2016-09-21 | 哈尔滨工程大学 | On-line-simulated-based nuclear power plant system level state monitoring method |
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