CN113963822A - Loop radioactive anomaly monitoring method and device, storage medium and electronic equipment - Google Patents
Loop radioactive anomaly monitoring method and device, storage medium and electronic equipment Download PDFInfo
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- 230000002285 radioactive effect Effects 0.000 title claims abstract description 63
- 238000012544 monitoring process Methods 0.000 title claims abstract description 41
- 238000000034 method Methods 0.000 title claims abstract description 35
- 238000003860 storage Methods 0.000 title claims abstract description 13
- 230000002159 abnormal effect Effects 0.000 claims abstract description 56
- 230000004044 response Effects 0.000 claims abstract description 8
- 230000001052 transient effect Effects 0.000 claims description 27
- 238000002955 isolation Methods 0.000 claims description 18
- 230000009467 reduction Effects 0.000 claims description 18
- 238000004590 computer program Methods 0.000 claims description 17
- 238000012546 transfer Methods 0.000 claims description 16
- 239000002826 coolant Substances 0.000 claims description 15
- 238000002347 injection Methods 0.000 claims description 8
- 239000007924 injection Substances 0.000 claims description 8
- 238000012806 monitoring device Methods 0.000 claims description 8
- 238000001514 detection method Methods 0.000 claims description 5
- 238000005070 sampling Methods 0.000 claims description 5
- 239000007788 liquid Substances 0.000 claims description 4
- 239000002699 waste material Substances 0.000 claims description 4
- 230000005856 abnormality Effects 0.000 abstract description 13
- 230000009471 action Effects 0.000 abstract description 4
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 16
- 229910052740 iodine Inorganic materials 0.000 description 16
- 239000011630 iodine Substances 0.000 description 16
- 239000000446 fuel Substances 0.000 description 10
- 230000000694 effects Effects 0.000 description 8
- 238000005253 cladding Methods 0.000 description 7
- 238000010586 diagram Methods 0.000 description 6
- 230000004888 barrier function Effects 0.000 description 5
- 230000006870 function Effects 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 239000000243 solution Substances 0.000 description 4
- 239000012857 radioactive material Substances 0.000 description 3
- 239000008188 pellet Substances 0.000 description 2
- 230000033228 biological regulation Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
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- 238000012986 modification Methods 0.000 description 1
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- 230000003287 optical effect Effects 0.000 description 1
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- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a method and a device for monitoring a loop radioactive anomaly, a storage medium and electronic equipment, wherein the method comprises the steps of detecting a loop radioactive value; determining the operation condition of the unit and an abnormal threshold corresponding to the operation condition; and acquiring the loop radioactivity value and the abnormal threshold, and comparing the loop radioactivity value with the abnormal threshold to determine whether the loop radioactivity is abnormal. According to the method, the radioactive value of the primary circuit is compared with the abnormal threshold value under the corresponding working condition, so that the radioactive abnormality of the primary circuit is accurately judged, reasonable response of automatic actions of the radioactive abnormality of the primary circuit is ensured, operating personnel can accurately judge the radioactive level of the primary circuit, and important support is provided for reasonably taking treatment measures.
Description
Technical Field
The invention relates to the technical field of radioactivity monitoring of nuclear power plants, in particular to a method and a device for monitoring a loop radioactivity anomaly, a storage medium and electronic equipment.
Background
The nuclear regime differs from other regimes in that it may lead to an unacceptable release of radioactive material. In order to prevent the release of radioactive materials into the environment, nuclear power plants are generally provided with a plurality of safety barriers, and if the integrity of the safety barriers can be ensured, the radioactive consequences of the working conditions can be effectively limited. For a pressurized water reactor nuclear power plant, three safety barriers are generally arranged: fuel cladding, primary circuit pressure boundary, containment. The fuel clad acts as a first safety barrier, the importance of which is self evident. The damage of the fuel cladding can cause radioactive substances in a fuel gap to leak to a primary circuit coolant, in order to find out possible damage of the fuel cladding in time, a pressurized water reactor nuclear power plant generally judges whether the fuel cladding is damaged by monitoring whether the radioactivity of the primary circuit coolant is abnormal, and a primary circuit coolant radioactivity monitoring channel is connected with a primary circuit main pipeline through a sampling pipeline or is arranged on a downward leakage loop of a chemical and volume control system.
For pressurized water reactor nuclear power plants, iodine I131 equivalents are typically used to characterize the primary circuit radioactivity level, considering that volatile iodine is a good nuclide for characterizing cladding integrity. Meanwhile, the nuclear power plant can observe an iodine peak phenomenon under the transient operation working condition such as load reduction or shutdown period: the sudden pressure drop in the interstices of the fuel pellets increases the coolant flow into the interstices, and a large amount of the iodine isotope will leak with the coolant into the primary coolant. Therefore, it is critical that the primary circuit radioactive anomaly reasonably reflect the presence of a fuel clad failure.
At present, the iodine peak phenomenon is not considered in primary circuit radioactive anomaly monitoring of domestic in-service pressurized water reactor nuclear power plants, a normalized primary circuit steady state radioactive threshold (such as 1 mu Ci/g) given in a safety analysis report is directly used as a criterion of primary circuit radioactive anomaly, if the primary circuit radioactivity exceeds the threshold, the primary circuit radioactive anomaly is considered, and all primary circuit coolant outlet pipelines including a downward-discharging loop are automatically isolated. However, even if the damage degree of the cladding does not exceed the allowable limit value by using the normalized steady-state radioactivity threshold value of the primary circuit, misjudgment as the radioactive abnormality of the primary circuit due to the iodine peak during transient operation can be caused, and the automatic isolation of a leakage circuit and the like can cause the water level regulation of the voltage stabilizer to lose an effective control means, thereby bringing difficulty to an operator for controlling the reactor.
Disclosure of Invention
The embodiment of the invention provides a method and a system for monitoring a loop radioactive anomaly, which are used for solving the problem of misjudging the loop radioactive anomaly due to an iodine peak.
The embodiment of the invention provides a method for monitoring a loop radioactive anomaly, which comprises the following steps: detecting a loop radioactivity value; determining the operation condition of the unit and an abnormal threshold corresponding to the operation condition; and acquiring the loop radioactivity value and the abnormal threshold, and comparing the loop radioactivity value with the abnormal threshold to determine whether the loop radioactivity is abnormal.
Further, the method further comprises: and when the loop radioactivity value is larger than the abnormal threshold value and the loop radioactivity is abnormal, controlling to execute response.
Further, the determining the operation condition of the unit includes: detecting pressure values at two sides of the steam generator; when the pressure difference between two sides of the steam generator is larger than a first preset threshold value, determining that the operation working condition of the unit is that the main steam pipeline is broken; determining an abnormal threshold corresponding to the operation condition, including: obtaining nuclear reactor power, and determining a main steam pipeline fracture threshold according to the nuclear reactor power.
Further, the determining the operation condition of the unit includes: detecting the leakage rate of the steam generator; when the leakage rate is larger than a second preset threshold value, determining that the operation working condition of the unit is that a steam generator heat transfer pipe is broken; determining an abnormal threshold corresponding to the operation condition, including: acquiring nuclear reactor power, and determining a steam generator heat transfer tube rupture threshold value according to the nuclear reactor power.
Further, the determining the operation condition of the unit includes: when a shutdown signal is received, and/or a safety injection system trigger signal is received, and/or the load reduction of a steam turbine is detected to exceed 25%, and/or the load reduction of a reactor is detected to exceed 25%, determining the operation working condition of the unit to be a major transient working condition; determining an abnormal threshold corresponding to the operation condition, including: and acquiring a transient source item value which is a transient threshold value.
Further, the determining the operation condition of the unit includes: when the pressure difference between two sides of the steam generator is smaller than a first preset threshold value, the leakage rate is smaller than a second preset threshold value, a shutdown signal is not received, a trigger signal of a safety injection system is not received, the load reduction of a steam turbine is not detected to exceed 25%, and the load reduction of a reactor is not detected to exceed 25%, the operation working condition of the unit is a steady-state operation working condition; determining an abnormal threshold corresponding to the operation condition, including: and acquiring a steady-state source item value which is a steady-state threshold value.
Further, the controlling performs a response including: triggering a loop radioactive abnormity alarm signal; closing the isolation valves on all coolant outlet lines; closing a primary circuit sampling pipeline isolation valve; closing the isolating valve of the lower discharge pipeline; closing a main pump shaft seal high-pressure leakage pipeline isolation valve; and closing the waste liquid treatment channel isolation valve.
The invention also provides a loop radioactive anomaly monitoring device, which is characterized by comprising: the detection module is used for detecting a loop radioactivity value; the determining module is used for determining the operation condition of the unit and the abnormal threshold corresponding to the operation condition; and the judging module is used for acquiring the loop radioactivity value and the abnormal threshold value, and comparing the loop radioactivity value with the abnormal threshold value to determine whether the loop radioactivity is abnormal.
The invention further provides a computer-readable storage medium, which stores a computer program, and the computer program, when executed by a processor, implements a loop radioactive anomaly monitoring method as described above.
The invention also provides a computer device, which comprises a memory, a processor and a computer program stored in the memory and capable of running on the processor, wherein the processor executes the computer program to realize the loop radioactive anomaly monitoring method.
According to the method for monitoring the primary circuit radioactive abnormality, provided by the embodiment of the invention, the criterion of the primary circuit radioactive abnormality threshold under different operation conditions is formulated by introducing the steady state threshold, the transient state threshold, the SGTR threshold and the MSLB threshold, so that misjudgment of the primary circuit radioactive abnormality caused by an iodine peak effect during MSLB, SGTR or transient operation is avoided. Therefore, operators can accurately judge the radioactivity level of the primary loop, and important support is provided for reasonably taking treatment measures.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings needed to be used in the description of the embodiments of the present invention will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art that other drawings can be obtained according to these drawings without inventive labor.
FIG. 1 is a flow chart of a method for monitoring a loop radioactive anomaly according to an embodiment of the present invention;
FIG. 2 is a flow chart of a method for monitoring a loop radioactive anomaly according to an embodiment of the present invention;
FIG. 3 is a flow diagram of exception threshold selection logic provided by an embodiment of the present invention;
FIG. 4 is a graphical illustration of the relationship between MSLB thresholds and nuclear reactor power as provided by an embodiment of the present invention;
FIG. 5 is a graphical illustration of the relationship between SGTR threshold and nuclear reactor power provided by an embodiment of the present invention;
fig. 6 is a schematic structural diagram of a loop radioactive anomaly monitoring device according to an embodiment of the present invention;
fig. 7 is a schematic diagram of a computer device provided by an embodiment of the invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, not all, embodiments of the present invention. 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.
The following describes a method, an apparatus, a storage medium, and an electronic device for monitoring a loop radioactive anomaly according to an embodiment of the present invention in detail with reference to fig. 1 to 7 of the specification and a specific embodiment.
Before describing the embodiments of the present application in detail, common technical terms are first introduced for ease of understanding.
A safety barrier: a closed enclosure between the nuclear fuel and the public containing the radioactive products, having in sequence from the inside to the outside: fuel cladding, primary circuit pressure boundary, containment.
Source item: form, quantity, composition, and other release characteristics of radioactive material released into the environment over time during normal or operating conditions of a nuclear power plant
Iodine peak: during load shedding or shutdown, the temperature and pressure of the fuel pellets and the gaps are reduced, the coolant entering the gaps is increased, and a large amount of iodine isotopes enter the primary coolant along with the coolant vapor. This phenomenon is commonly referred to as iodine spike or spike release. This phenomenon can also be tracked when the loop system is depressurized.
Fig. 1 is a flowchart of a method for monitoring a loop radioactive anomaly according to an embodiment of the present invention. As shown in fig. 1, a method for monitoring a loop radioactive anomaly includes:
and S1, detecting a circuit radioactivity value.
Specifically, a reactor coolant activity monitoring instrument may be utilized to detect a primary circuit activity value.
And S2, determining the operation condition of the unit and the abnormal threshold corresponding to the operation condition.
Specifically, the operation condition of the unit is determined, the current abnormal threshold value of the primary circuit radioactivity value is determined according to the operation condition of the unit, whether the primary circuit radioactivity value is abnormal or not is judged, so that misjudgment of primary circuit radioactivity due to an iodine peak effect is avoided, reasonable response of automatic action can be realized when the primary circuit radioactivity is abnormal, meanwhile, operators can be ensured to accurately judge the primary circuit radioactivity level, and important support is provided for reasonably taking treatment measures.
In an embodiment of the present invention, as shown in fig. 2, the determining the operation condition of the unit includes: detecting pressure values at two sides of the steam generator; and when the pressure difference between two sides of the steam generator is greater than a first preset threshold value, determining that the operation working condition of the unit is that the main steam pipeline is broken. In this embodiment, determining the abnormal threshold corresponding to the operating condition includes: obtaining nuclear reactor power, and determining a main steam pipeline fracture threshold according to the nuclear reactor power.
Specifically, whether the operation condition of the unit is the main steam pipeline cracking state or not can be judged by monitoring the pressure on two sides of the steam generator. Further, can set up steam generator pressure instrument in steam generator both sides, detect the pressure value of steam generator both sides, detect steam generator differential pressure height, work as the operating condition of unit can be confirmed and main steam pipe rupture state is greater than first preset threshold value to the pressure difference of steam generator both sides. When the operation working condition of the unit is the main steam pipeline fracture state, the main steam pipeline fracture threshold value under the main steam pipeline fracture working condition is compared with the detected primary loop radioactivity value, and whether the primary loop radioactivity is abnormal or not is judged. Therefore, it is desirable to determine a main steam line rupture threshold for a current main steam line rupture condition.
In the embodiment of the present invention, the first preset threshold may be set according to specific situations.
Specifically, under the working condition of main steam pipeline breakage, the excessive cooling of the secondary loop can suddenly reduce the temperature and the pressure of the primary loop, and the positive reaction caused by temperature reduction obviously increases the nuclear power of the reactor core, considering the power effect of an iodine peak. The current MSLB threshold may be determined based on a relationship between the MSLB threshold and the nuclear reactor power.
As shown in fig. 4, as the nuclear reactor power decreased, the MSLB threshold linearly increased under the power effect of the iodine spike. Specifically, the MSLB threshold is up to 500 times 1. mu. Ci/g. The MSLB threshold may be 60 times 1. mu. Ci/g for a nuclear reactor power level of 80% to 100%, when the MSLB threshold corresponds to the transient threshold. After the MSLB threshold is determined, the detected primary loop radioactivity value is compared with the MSLB threshold to determine whether the primary loop radioactivity is abnormal.
In an embodiment of the present invention, as shown in fig. 2, the determining the operation condition of the unit includes: detecting the leakage rate of the steam generator; and when the leakage rate is larger than a second preset threshold value, determining that the operation working condition of the unit is that the heat transfer pipe of the steam generator is broken. In this embodiment, determining the abnormal threshold corresponding to the operating condition includes: acquiring nuclear reactor power, and determining a steam generator heat transfer tube rupture threshold value according to the nuclear reactor power.
Specifically, whether the operation condition of the unit is the rupture of the heat transfer pipe of the steam generator can be judged through the leakage rate of the steam generator. Specifically, a steam generator leakage monitoring instrument may be disposed at one side of at least one steam generator to monitor whether the leakage rate of at least one steam generator exceeds a second preset threshold. And when the leakage rate of any one steam generator is greater than a second preset threshold value, determining that the operation condition of the unit is that the heat transfer pipe of the steam generator is broken.
When the operating condition of the unit is that the steam generator heat transfer tube is broken, comparing the breakage threshold of the steam generator heat transfer tube under the steam generator heat transfer tube breakage condition with the detected primary loop radioactivity value to judge whether the primary loop radioactivity is abnormal or not. Therefore, it is desirable to determine a main steam line rupture threshold for a current steam generator heat transfer tube rupture condition.
In the embodiment of the present invention, the second preset threshold may be set according to specific situations. As an example, the second preset threshold may be 70L/h. And when the leakage rate of one steam generator exceeds 70L/h, the steam generator is considered to be in a steam generator heat transfer pipe rupture working condition.
Specifically, similar to MSLB, the SGTR threshold varies in relation to nuclear reactor power, as shown in fig. 5. Referring to fig. 5, as the nuclear reactor power decreases, the SGTR threshold will become linearly larger, taking into account the power effect of the iodine spike. The SGTR threshold is up to 335 times 1 mu Ci/g, when the nuclear reactor power is 80% to 100%, the SGTR threshold is 60 times 1 mu Ci/g, and the SGTR threshold corresponds to a transient threshold. After the SGTR threshold is determined, the detected primary circuit radioactivity value is compared with the SGTR threshold to determine whether the primary circuit radioactivity is abnormal.
In an embodiment of the present invention, as shown in fig. 2, the determining the operation condition of the unit includes: and when a shutdown signal is received, and/or a safety injection system trigger signal is received, and/or the load reduction of a steam turbine is detected to exceed 25%, and/or the load reduction of a reactor is detected to exceed 25%, determining the operation working condition of the unit to be a major transient working condition. In this embodiment, determining the abnormal threshold corresponding to the operating condition includes: and acquiring a transient source item value which is a transient threshold value.
In particular, one of the following situations occurs, namely during major transients considered, such as: and receiving a shutdown signal and a trigger signal of the safety injection system, detecting that the load reduction of the steam turbine exceeds 25 percent, and detecting that the load reduction of the reactor exceeds 25 percent. And in the major transient process of the unit, selecting a transient threshold value to judge the radioactive abnormality of the primary loop.
Further specifically, the transient source item value given in the safety analysis report may be used as the transient threshold value by obtaining the transient source item value given in the safety analysis report. Typically the transient threshold is about several tens of times the steady state threshold. For example, if the steady state threshold is 1 μ Ci/g, the transient threshold may be 60 μ Ci/g.
In an embodiment of the present invention, as shown in fig. 3, the determining the operation condition of the unit includes: and when the pressure difference between two sides of the steam generator is smaller than a first preset threshold value, the leakage rate is smaller than a second preset threshold value, a shutdown signal is not received, a trigger signal of a safety injection system is not received, the load reduction of the steam turbine is not detected to exceed 25%, and the load reduction of the reactor is not detected to exceed 25%, the operation working condition of the unit is a steady-state operation working condition. In this embodiment, determining the abnormal threshold corresponding to the operating condition includes: and acquiring a steady-state source item value which is a steady-state threshold value.
Specifically, when the pressure difference between the two sides of the steam generator is smaller than a first preset threshold value, and the operation condition of the unit is not the main steam pipeline fracture condition, the leakage rate is smaller than a second preset threshold value, when the operation condition of the unit is not the steam generator heat transfer pipe fracture, a shutdown signal is not received, a safety injection system trigger signal is not received, the load reduction of the steam turbine is not detected to exceed 25%, and when the load reduction of the reactor is not detected to exceed 25%, the operation condition of the unit is not a major transient condition. The unit can be considered to be in a steady state working condition, and a steady state threshold value is selected to judge the radioactive abnormality of the primary loop under the condition.
Further specifically, the steady-state source item value given in the safety analysis report may be used as the steady-state threshold value by obtaining the steady-state source item value given in the safety analysis report. The steady state threshold may take 1. mu. Ci/g.
S3, obtaining the loop radioactivity value and the anomaly threshold, and comparing the loop radioactivity value with the anomaly threshold to determine whether the loop radioactivity is abnormal.
Specifically, when the operation condition of the unit and the corresponding abnormal threshold value of the unit are determined, the detected loop radioactivity value is compared with the corresponding abnormal threshold value. To determine whether the radioactivity of the primary circuit is abnormal.
In an embodiment of the present invention, the method for monitoring a loop radioactive anomaly further includes: and when the loop radioactivity value is larger than the abnormal threshold value and the loop radioactivity is abnormal, controlling to execute response.
Specifically, under the working condition of main steam pipeline breakage, when the detected primary circuit radioactivity value is larger than the current main steam pipeline breakage threshold value, primary circuit radioactivity abnormity is determined. And under the steam generator heat transfer pipe rupture working condition, when the detected primary circuit radioactivity value is larger than the current steam generator heat transfer pipe rupture threshold value, the primary circuit radioactivity abnormity is determined. And under the condition of major transient state, when the detected primary circuit radioactivity value is larger than the current transient state threshold value, the primary circuit radioactivity abnormity is determined. And under the steady-state operation condition, when the detected primary circuit radioactivity value is larger than the current steady-state threshold value, a primary circuit radioactivity abnormity is determined.
In an embodiment of the present invention, the controlling performs the response, including: triggering a loop radioactive abnormity alarm signal; closing the isolation valves on all coolant outlet lines; closing a primary circuit sampling pipeline isolation valve; closing the isolating valve of the lower discharge pipeline; closing a main pump shaft seal high-pressure leakage pipeline isolation valve; and closing the waste liquid treatment channel isolation valve.
Specifically, after a primary circuit radioactive anomaly is determined, a primary circuit radioactive anomaly alarm signal is reported and automatic action is linked. Namely, a primary circuit radioactive abnormity alarm signal is triggered, and simultaneously, the automatic action is linked, so that the isolation valves on all coolant outlet pipelines are closed, including the closing of a primary circuit sampling pipeline isolation valve, the closing of a lower discharge pipeline isolation valve, the closing of a main pump shaft seal high-pressure leakage pipeline isolation valve, the closing of a waste liquid treatment channel isolation valve and the like.
According to the method for monitoring the radioactive abnormality of the primary circuit, provided by the embodiment of the invention, the criterion of the radioactive abnormality threshold of the primary circuit under different operation conditions is formulated by introducing the steady state threshold, the transient state threshold, the SGTR threshold and the MSLB threshold, so that misjudgment of the radioactive abnormality of the primary circuit caused by the iodine peak effect during MSLB, SGTR or transient operation is avoided. Therefore, operators can accurately judge the radioactivity level of the primary loop, and important support is provided for reasonably taking treatment measures.
The invention also provides a device for monitoring the radioactive anomaly of the primary loop. The primary loop radioactive anomaly monitoring device 10 provided by the embodiment of the invention is in communication connection with each service system.
Fig. 6 is a schematic structural diagram of a primary radioactive anomaly monitoring device according to an embodiment of the present invention, and as shown in fig. 6, a primary radioactive anomaly monitoring device 10 includes a detection module 11, a determination module 12, and a determination module 13.
The detection module 11 is used for detecting a loop radioactivity value. The determining module 12 is configured to determine an operation condition of the unit and an abnormal threshold corresponding to the operation condition. The determining module 13 is configured to obtain the loop radioactivity value and the abnormal threshold, and compare the loop radioactivity value with the abnormal threshold to determine whether the loop radioactivity is abnormal.
For specific limitations of the primary circuit radioactive anomaly monitoring apparatus, reference may be made to the above limitations of the primary circuit radioactive anomaly monitoring method, which are not described herein again. All or part of the modules in the loop radioactive anomaly monitoring device can be realized by software, hardware and a combination thereof. The modules can be embedded in a hardware form or independent from a processor in the computer device, and can also be stored in a memory in the computer device in a software form, so that the processor can call and execute operations corresponding to the modules.
Fig. 7 is a schematic diagram of a computer device provided by an embodiment of the invention. The computer device may be a server and its internal structure diagram may be as shown in fig. 7. The computer device includes a processor, a memory, a network interface, and a database connected by a system bus. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device comprises a nonvolatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, a computer program, and a database. The internal memory provides an environment for the operation of an operating system and computer programs in the non-volatile storage medium. The database of the computer equipment is used for storing the loop radioactive anomaly monitoring method. The network interface of the computer device is used for communicating with an external terminal through a network connection. The computer program is executed by a processor to implement a loop radiological anomaly monitoring method.
In one embodiment, a computer device is provided, which includes a memory, a processor and a computer program stored in the memory and executable on the processor, and the processor executes the computer program to implement the steps of the loop radioactive anomaly monitoring method of the above embodiments, such as the steps S1 to S3 shown in fig. 1. Alternatively, the processor executes a computer program to implement the functions of the modules/units of the loop radioactive abnormality monitoring apparatus according to the above-mentioned embodiment, such as the functions of the detection module 11, the determination module 12 and the judgment module 13 shown in fig. 6. To avoid repetition, further description is omitted here.
It is obvious to those skilled in the art that, for convenience and simplicity of description, the foregoing division of the functional units and modules is merely used as an example, and in practical applications, the above function distribution may be performed by different functional units and modules as needed, that is, the internal structure of the primary circuit radioactive abnormality monitoring apparatus is divided into different functional units or modules to perform all or part of the above described functions.
In an embodiment, a computer-readable storage medium is provided, and the computer-readable storage medium stores a computer program, and the computer program is executed by a processor to implement the steps of the loop radioactive anomaly monitoring method according to the above embodiment, or the computer program is executed by the processor to implement the functions of the modules/units in the loop radioactive anomaly monitoring device according to the above embodiment. To avoid repetition, further description is omitted here.
It is to be understood that the computer-readable storage medium may include: any entity or device capable of carrying the computer program code, recording medium, usb disk, removable hard disk, magnetic disk, optical disk, computer Memory, Read-Only Memory (ROM), Random Access Memory (RAM), electrical carrier wave signals, telecommunications signals, and the like.
The above-mentioned embodiments are only used for illustrating the technical solutions of the present invention, and not for limiting the same; although the present invention has been described in detail with reference to the foregoing embodiments, it will be understood by those of ordinary skill in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some technical features may be equivalently replaced; such modifications and substitutions do not substantially depart from the spirit and scope of the embodiments of the present invention, and are intended to be included within the scope of the present invention.
Claims (10)
1. A method for monitoring a primary circuit radioactive anomaly, the method comprising:
detecting a loop radioactivity value;
determining the operation condition of the unit and an abnormal threshold corresponding to the operation condition;
and acquiring the loop radioactivity value and the abnormal threshold, and comparing the loop radioactivity value with the abnormal threshold to determine whether the loop radioactivity is abnormal.
2. A primary circuit radioactive anomaly monitoring method as set forth in claim 1, further comprising:
and when the loop radioactivity value is larger than the abnormal threshold value and the loop radioactivity is abnormal, controlling to execute response.
3. A primary loop radioactive anomaly monitoring method as claimed in claim 1, wherein said determining operating conditions of said unit comprises:
detecting pressure values at two sides of the steam generator;
when the pressure difference between two sides of the steam generator is larger than a first preset threshold value, determining that the operation working condition of the unit is that the main steam pipeline is broken;
determining an abnormal threshold corresponding to the operation condition, including:
obtaining nuclear reactor power, and determining a main steam pipeline fracture threshold according to the nuclear reactor power.
4. A primary loop radioactive anomaly monitoring method as claimed in claim 1, wherein said determining operating conditions of said unit comprises:
detecting the leakage rate of the steam generator;
when the leakage rate is larger than a second preset threshold value, determining that the operation working condition of the unit is that a steam generator heat transfer pipe is broken;
determining an abnormal threshold corresponding to the operation condition, including:
acquiring nuclear reactor power, and determining a steam generator heat transfer tube rupture threshold value according to the nuclear reactor power.
5. A primary loop radioactive anomaly monitoring method as claimed in claim 1, wherein said determining operating conditions of said unit comprises:
when a shutdown signal is received, and/or
Receiving a safety injection system trigger signal, and/or
Detecting a turbine load reduction of more than 25%, and/or
When the reactor load reduction is detected to exceed 25%, determining the operation working condition of the unit to be a major transient working condition;
determining an abnormal threshold corresponding to the operation condition, including:
and acquiring a transient source item value which is a transient threshold value.
6. A primary loop radioactive anomaly monitoring method as claimed in claim 1, wherein said determining operating conditions of said unit comprises:
when the pressure difference between two sides of the steam generator is smaller than a first preset threshold value, the leakage rate is smaller than a second preset threshold value, a shutdown signal is not received, a trigger signal of a safety injection system is not received, the load reduction of a steam turbine is not detected to exceed 25%, and the load reduction of a reactor is not detected to exceed 25%, the operation working condition of the unit is a steady-state operation working condition;
determining an abnormal threshold corresponding to the operation condition, including:
and acquiring a steady-state source item value which is a steady-state threshold value.
7. A loop radiological anomaly monitoring method as set forth in claim 2, wherein said controlling performs a response including:
triggering a loop radioactive abnormity alarm signal;
closing the isolation valves on all coolant outlet lines;
closing a primary circuit sampling pipeline isolation valve;
closing the isolating valve of the lower discharge pipeline;
closing a main pump shaft seal high-pressure leakage pipeline isolation valve;
and closing the waste liquid treatment channel isolation valve.
8. A primary circuit radioactive anomaly monitoring device, said device comprising:
the detection module is used for detecting a loop radioactivity value;
the determining module is used for determining the operation condition of the unit and the abnormal threshold corresponding to the operation condition;
and the judging module is used for acquiring the loop radioactivity value and the abnormal threshold value, and comparing the loop radioactivity value with the abnormal threshold value to determine whether the loop radioactivity is abnormal.
9. A computer-readable storage medium, in which a computer program is stored, which, when being executed by a processor, carries out a method for loop radiological anomaly monitoring according to any one of claims 1 to 7.
10. Computer device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, characterized in that the processor implements a loop radiological anomaly monitoring method according to any one of claims 1 to 7 when executing the computer program.
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