CN113963822B - Method and device for monitoring radioactivity abnormality of one-loop, storage medium and electronic equipment - Google Patents
Method and device for monitoring radioactivity abnormality of one-loop, storage medium and electronic equipment Download PDFInfo
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- CN113963822B CN113963822B CN202111158476.4A CN202111158476A CN113963822B CN 113963822 B CN113963822 B CN 113963822B CN 202111158476 A CN202111158476 A CN 202111158476A CN 113963822 B CN113963822 B CN 113963822B
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- 238000000034 method Methods 0.000 title claims abstract description 32
- 238000012544 monitoring process Methods 0.000 title claims abstract description 32
- 230000005856 abnormality Effects 0.000 title claims abstract description 21
- 230000002159 abnormal effect Effects 0.000 claims abstract description 39
- 230000004044 response Effects 0.000 claims abstract description 8
- 230000002547 anomalous effect Effects 0.000 claims abstract description 6
- 230000001052 transient effect Effects 0.000 claims description 35
- 238000012546 transfer Methods 0.000 claims description 18
- 238000002955 isolation Methods 0.000 claims description 17
- 230000009467 reduction Effects 0.000 claims description 16
- 238000004590 computer program Methods 0.000 claims description 15
- 239000002826 coolant Substances 0.000 claims description 15
- 238000012806 monitoring device Methods 0.000 claims description 11
- 238000002347 injection Methods 0.000 claims description 10
- 239000007924 injection Substances 0.000 claims description 10
- 230000002285 radioactive effect Effects 0.000 claims description 7
- 238000001514 detection method Methods 0.000 claims description 5
- 238000005070 sampling Methods 0.000 claims description 5
- 238000005336 cracking Methods 0.000 claims description 4
- 239000007788 liquid Substances 0.000 claims description 4
- 239000002699 waste material Substances 0.000 claims description 4
- 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
- 238000005253 cladding Methods 0.000 description 6
- 230000000694 effects Effects 0.000 description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 230000004888 barrier function Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 230000006870 function Effects 0.000 description 4
- 239000012857 radioactive material Substances 0.000 description 4
- 230000007423 decrease Effects 0.000 description 3
- 239000000243 solution Substances 0.000 description 3
- 239000008188 pellet Substances 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 230000033228 biological regulation Effects 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- 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 radioactivity abnormality of a loop, a storage medium and electronic equipment, wherein the method comprises the steps of detecting a radioactivity value of the loop; determining the operation condition of a unit and an abnormal threshold corresponding to the operation condition; the loop radioactivity value and the anomaly threshold value are obtained, and the loop radioactivity value is compared with the anomaly threshold value to determine whether the loop radioactivity is anomalous. The method realizes the accurate judgment of the radioactivity abnormality of the loop by comparing the radioactivity value of the loop with the abnormal threshold value under the corresponding working condition, so as to ensure reasonable response of the automatic action of the radioactivity abnormality of the loop, ensure that operators can accurately judge the radioactivity level of the loop and provide important support for reasonably taking treatment measures.
Description
Technical Field
The invention relates to the technical field of nuclear power plant radioactivity monitoring, in particular to a primary loop radioactivity anomaly monitoring method and device, a storage medium and electronic equipment.
Background
The nuclear conditions differ from other conditions in that it may lead to unacceptable release of radioactive material. To prevent the release of radioactive materials to the environment, nuclear power plants are typically provided with a plurality of safety barriers, which, if their integrity is ensured, effectively limit the radioactive consequences of the operating conditions. For pressurized water reactor nuclear power plants, three safety barriers are generally arranged: fuel containment, a circuit pressure boundary, and a containment vessel. The importance of the fuel cladding as a first safety barrier is self-evident. The damage to the fuel cladding can cause radioactive material in the fuel gap to leak to a loop coolant, and in order to find possible damage to 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 loop coolant is abnormal, and a loop coolant radioactivity monitoring channel is connected with a loop main pipeline through a sampling pipeline or is arranged on a down-leak loop of a chemical and volume control system.
For pressurized water reactor nuclear power plants, iodine I131 equivalent is typically used to characterize the level of primary radioactivity, considering that volatile iodine is a good nuclide for characterizing the integrity of the cladding. Meanwhile, under transient operation conditions of the nuclear power plant, such as load reduction or shutdown, an iodine peak phenomenon can be observed: the sudden drop in pressure in the fuel pellet gap increases the coolant flow into the gap and a large amount of isotopes of iodine will leak with the coolant into the primary loop coolant. Therefore, whether a loop radioactivity anomaly can reasonably reflect whether a fuel cladding is broken or not is a key issue.
At present, iodine peak phenomenon is not considered in primary loop radioactivity anomaly monitoring of domestic in-service pressurized water reactor nuclear power plants, a normalized primary loop steady-state radioactivity threshold (such as 1 muCi/g) given in a safety analysis report is directly used as a criterion of primary loop radioactivity anomaly, and if primary loop radioactivity exceeds the threshold, the primary loop radioactivity anomaly is considered, and all primary loop coolant outlet pipelines including a down-flow loop are automatically isolated. However, using the normalized one-circuit steady-state radioactivity threshold, even if the enclosure breakage does not exceed the allowable limit, it may be possible to misjudge the one-circuit radioactivity anomaly due to iodine peaks during transient operation, and automatic isolation of the down-let loop and the like may result in loss of effective control means for regulator water level regulation, which may cause difficulty for operators to control the reactor.
Disclosure of Invention
The embodiment of the invention provides a method and a system for monitoring radioactivity abnormality of a loop, which are used for solving the problem of misjudgment of radioactivity abnormality of the loop due to iodine peaks.
The embodiment of the invention provides a method for monitoring radioactivity abnormality of a primary circuit, which comprises the following steps: detecting a loop radioactivity value; determining the operation condition of a unit and an abnormal threshold corresponding to the operation condition; the loop radioactivity value and the anomaly threshold value are obtained, and the loop radioactivity value is compared with the anomaly threshold value to determine whether the loop radioactivity is anomalous.
Further, the method further comprises: control performs a response when the loop radioactivity value is greater than the anomaly threshold value and the loop radioactivity is anomalous.
Further, the determining the operation condition of the unit includes: detecting pressure values at two sides of the steam generator; when the pressure difference of the 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 a main steam pipeline is broken; determining an abnormal threshold corresponding to the operating condition, including: and 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 a leak rate of the steam generator; when the leakage rate is larger than a second preset threshold value, determining the operation working condition of the unit as the cracking of the heat transfer tube of the steam generator; determining an abnormal threshold corresponding to the operating condition, including: and obtaining nuclear reactor power, and determining a steam generator heat transfer tube rupture threshold 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 trigger signal of a safety injection system is received, and/or a load reduction of the steam turbine is detected to be more than 25%, and/or a load reduction of the reactor is detected to be more than 25%, determining that the operation working condition of the unit is a significant transient working condition; determining an abnormal threshold corresponding to the operating condition, including: and acquiring a transient source item value, wherein the transient source item value is a transient threshold value.
Further, the determining the operation condition of the unit includes: when the pressure difference at two sides of the steam generator is smaller than a first preset threshold, the leakage rate is smaller than a second preset threshold, a shutdown signal is not received, a safety injection system trigger signal is not received, the load reduction of the steam engine is not detected to be more than 25%, and the load reduction of the reactor is not detected to be more than 25%, the running condition of the unit is a steady-state running condition; determining an abnormal threshold corresponding to the operating condition, including: and obtaining a steady-state source item value, wherein the steady-state source item value is a steady-state threshold value.
Further, the control execution response includes: triggering a loop radioactive abnormality alarm signal; closing all isolation valves on the coolant outlet lines; closing a loop sampling pipeline isolation valve; closing the release line isolation valve; closing the main pump shaft seal high-pressure leakage pipeline isolation valve; closing the waste liquid treatment channel isolation valve.
The invention also provides a loop radioactivity 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 an 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 or not.
The present invention also provides a computer readable storage medium storing a computer program which when executed by a processor implements a loop radioactivity anomaly monitoring method as described above.
The invention also provides a computer device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor implements the loop radioactivity anomaly monitoring method as described above when executing the computer program.
According to the loop radioactivity anomaly monitoring method provided by the embodiment of the invention, the steady state threshold, the transient state threshold, the SGTR threshold and the MSLB threshold are introduced to formulate loop radioactivity anomaly threshold criteria under different operation conditions, so that misjudgment on loop radioactivity anomaly 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.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings that are needed in the description of the embodiments of the present invention will be briefly described below, it being obvious that the drawings in the following description are only some embodiments of the present invention, and that other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a flow chart of a method for monitoring radioactivity anomalies in a loop according to an embodiment of the present invention;
FIG. 2 is a flow chart of a method for monitoring a radioactive abnormality of a loop according to an embodiment of the present invention;
FIG. 3 is a flow chart of anomaly threshold selection logic provided by an embodiment of the present invention;
FIG. 4 is a graph of MSLB threshold versus nuclear reactor power provided by an embodiment of the present invention;
FIG. 5 is a graph of SGTR threshold versus nuclear reactor power provided by an embodiment of the present invention;
FIG. 6 is a schematic diagram of a loop radioactivity anomaly monitoring device according to an embodiment of the present invention;
fig. 7 is a schematic diagram of a computer device according to an embodiment of the present invention.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and fully with reference to the accompanying drawings, in which it is evident that the embodiments described are some, but not all embodiments of the invention. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
The following describes a method, apparatus, storage medium, and electronic device for monitoring a radioactivity anomaly in a loop according to an embodiment of the present invention in detail with reference to fig. 1 to 7 of the accompanying drawings and detailed description.
Before describing the embodiments of the present application in detail, for ease of understanding, common technical words are first introduced.
Safety barrier: the enclosed shell which is arranged between the nuclear fuel and the public and contains radioactive products comprises the following components in sequence from inside to outside: fuel containment, a circuit pressure boundary, and a containment vessel.
Source item: during normal or operating conditions of a nuclear power plant, the morphology, quantity, composition, and other release characteristics of the radioactive material released into the environment over time
Iodine peak: during load shedding or shutdown, the temperature and pressure at the fuel pellets and gaps decrease, the coolant entering the gaps increases, and a large amount of isotopes of iodine will enter the primary loop coolant with the coolant vapor. This phenomenon is commonly referred to as iodine peak or spike release. This phenomenon can also be tracked when a loop system is depressurized.
FIG. 1 is a flow chart of a method for monitoring radioactivity anomalies in a loop according to an embodiment of the present invention. As shown in fig. 1, the method for monitoring the radioactivity abnormality of the first circuit comprises the following steps:
S1, detecting a loop radioactivity value.
Specifically, a reactor coolant radioactivity monitoring meter may be used to detect a loop radioactivity value.
S2, determining the operation condition of the unit and an abnormal threshold corresponding to the operation condition.
Specifically, the operation condition of the unit is determined, the current abnormal threshold value of the loop radioactivity value is determined according to the operation condition of the unit, so that whether the loop radioactivity value is abnormal or not is judged, misjudgment on the loop radioactivity abnormality caused by the iodine peak effect is avoided, reasonable response of automatic action can be realized when the loop radioactivity is abnormal, meanwhile, operators can accurately judge the loop 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 at 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 a main steam pipeline is broken. In this embodiment, determining the anomaly threshold value corresponding to the operating condition includes: and 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 a main steam pipeline cracking state can be judged by monitoring the pressure on two sides of the steam generator. Furthermore, the steam generator pressure instruments can be arranged on two sides of the steam generator to detect pressure values on two sides of the steam generator, the differential pressure of the steam generator is detected to be high, and when the pressure difference on two sides of the steam generator is larger than a first preset threshold value, the operation condition of the unit can be confirmed to be the main steam pipeline fracture state. When the operation working condition of the unit is the main steam pipeline fracture state, comparing the main steam pipeline fracture threshold value under the main steam pipeline fracture working condition with the detected loop radioactivity value to judge whether the loop radioactivity is abnormal. It is therefore desirable to determine a main steam line break threshold for the current main steam line break conditions.
In an embodiment of the present invention, the first preset threshold may be set according to a specific situation.
Specifically, under the main steam pipeline fracture working condition, the excessive cooling of the two loops can lead the temperature and the pressure of the first loop to be suddenly reduced, and meanwhile, the positive reactivity introduced by the temperature reduction can lead the core nuclear power to be obviously increased, so that the power effect of an iodine peak is considered. The current MSLB threshold may be determined based on a change relationship between the MSLB threshold and the nuclear reactor power.
As shown in fig. 4, as the nuclear reactor power decreases, the MSLB threshold linearity increases under the power effect of the iodine peak. Specifically, the MSLB threshold is up to 500 times 1 μCi/g. At nuclear reactor power levels of 80% to 100%, the MSLB threshold may be 60 times 1 μCi/g, where the MSLB threshold corresponds to a transient threshold. After the MSLB threshold is determined, the detected loop radioactivity value is compared to determine if the 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 a leak rate of the steam generator; and when the leakage rate is larger than a second preset threshold value, determining the operation condition of the unit as the rupture of the heat transfer tube of the steam generator. In this embodiment, determining the anomaly threshold value corresponding to the operating condition includes: and obtaining nuclear reactor power, and determining a steam generator heat transfer tube rupture threshold according to the nuclear reactor power.
Specifically, whether the operation condition of the unit is the rupture of the heat transfer tube of the steam generator can be judged through the leakage rate of the steam generator. Specifically, a steam generator leakage monitoring instrument may be provided on one side of the at least one steam generator to monitor whether the leakage rate of the at least one steam generator exceeds a second preset threshold. When the leakage rate of any one steam generator is larger than a second preset threshold value, the operation working condition of the unit can be determined to be that the heat transfer pipe of the steam generator is broken.
When the operation working condition of the unit is that the steam generator heat transfer tube breaks, comparing the steam generator heat transfer tube breaking threshold value under the steam generator heat transfer tube breaking working condition with the detected loop radioactivity value to judge whether the loop radioactivity is abnormal or not. It is therefore desirable to determine the main steam line break threshold for current steam generator heat transfer pipe break conditions.
In an embodiment of the present invention, the second preset threshold may be set according to a specific situation. As one example, the second preset threshold may be 70L/h. When the leakage rate of one steam generator exceeds 70L/h, the steam generator is considered to be in a broken working condition of the heat transfer tube of the steam generator.
Specifically, similar to MSLB, the relationship between SGTR threshold and nuclear reactor power is varied 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 peak. The SGTR threshold is up to 335 times 1 μCi/g, and 60 times 1 μCi/g is taken at 80% to 100% nuclear reactor power, where the SGTR threshold corresponds to the transient threshold. After the SGTR threshold is determined, the detected loop radioactivity value is compared to determine if the 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: and when the shutdown signal is received, and/or a trigger signal of a safety injection system is received, and/or the load reduction of the steam turbine is detected to be more than 25%, and/or the load reduction of the reactor is detected to be more than 25%, determining that the operation working condition of the unit is a large transient working condition. In this embodiment, determining the anomaly threshold value corresponding to the operating condition includes: and acquiring a transient source item value, wherein the transient source item value is a transient threshold value.
Specifically, one of the following situations arises, namely, considered to be in a significant transient process, such as: and receiving a shutdown signal, receiving a trigger signal of a safety injection system, detecting that the load of the steam turbine is reduced by more than 25 percent, and detecting that the load of the reactor is reduced by more than 25 percent. And when the unit is in a major transient process, a transient threshold value is selected to judge the radioactivity abnormality of the loop.
Further specifically, the transient source term value given in the security analysis report may be taken as the transient threshold value by obtaining the transient source term value given in the security analysis report. Typically the transient threshold is about tens of times the steady state threshold. For example, if the steady state threshold is 1 μCi/g, the transient threshold may be 60 μCi/g.
In an embodiment of the present invention, as shown in fig. 3, the determining the operation condition of the unit includes: when the pressure difference at two sides of the steam generator is smaller than a first preset threshold, the leakage rate is smaller than a second preset threshold, a shutdown signal is not received, a safety injection system trigger signal is not received, the load drop of the steam turbine is not detected to exceed 25%, and the load drop 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 anomaly threshold value corresponding to the operating condition includes: and obtaining a steady-state source item value, wherein the steady-state source item value is a steady-state threshold value.
Specifically, when the pressure difference at two sides of the steam generator is smaller than a first preset threshold, the leakage rate is smaller than a second preset threshold when the operation working condition of the unit is not the main steam pipeline breaking working condition, the shutdown signal is not received when the operation working condition of the unit is not the steam generator heat transfer pipe breaking, the safety injection system triggering signal is not received, the load of the steam turbine is not detected to be more than 25%, and the operation working condition of the unit is not a heavy transient working condition when the load of the reactor is not detected to be more than 25%. The unit can be considered to be in a steady state working condition, and a steady state threshold value is selected to judge the radioactivity abnormality of the primary loop under the condition.
Further specifically, the steady state source term value given in the security analysis report may be taken as the steady state threshold by obtaining the steady state source term value given in the security analysis report. The steady state threshold may be 1. Mu. Ci/g.
S3, acquiring the loop radioactivity value and the abnormality threshold, and comparing the loop radioactivity value with the abnormality threshold to determine whether the loop radioactivity is abnormal.
Specifically, when the operating conditions of the unit and the corresponding abnormal thresholds thereof are determined, the detected loop radioactivity value is compared with the corresponding abnormal thresholds. To determine whether the radioactivity of the loop is abnormal.
In an embodiment of the present invention, the method for monitoring a loop radioactivity anomaly further comprises: control performs a response when the loop radioactivity value is greater than the anomaly threshold value and the loop radioactivity is anomalous.
Specifically, under the main steam pipe fracture working condition, when the detected loop radioactivity value is larger than the current main steam pipe fracture threshold value, the loop radioactivity abnormality is determined. And under the working condition of breakage of the heat transfer tube of the steam generator, when the detected radioactivity value of the primary circuit is larger than the current breakage threshold value of the heat transfer tube of the steam generator, determining that the radioactivity of the primary circuit is abnormal. Under significant transient conditions, a loop radioactivity anomaly is identified when the detected loop radioactivity value is greater than the current transient threshold. Under steady state operating conditions, a loop radioactivity anomaly is identified when the detected loop radioactivity value is greater than the current steady state threshold.
In an embodiment of the present invention, the control execution response includes: triggering a loop radioactive abnormality alarm signal; closing all isolation valves on the coolant outlet lines; closing a loop sampling pipeline isolation valve; closing the release line isolation valve; closing the main pump shaft seal high-pressure leakage pipeline isolation valve; closing the waste liquid treatment channel isolation valve.
Specifically, when a loop radioactivity anomaly is determined, a loop radioactivity anomaly alarm signal and linkage automatic action are reported. Namely triggering a loop radioactive abnormality alarm signal and simultaneously linkage automatic action to close the isolation valves on all the coolant outlet pipelines, comprises closing a loop sampling pipeline isolating valve, closing a down-leakage pipeline isolating valve, closing a main pump shaft seal high-pressure leakage pipeline isolating valve, closing a waste liquid treatment channel isolating valve and the like.
According to the loop radioactivity anomaly monitoring method provided by the embodiment of the invention, the steady state threshold, the transient state threshold, the SGTR threshold and the MSLB threshold are introduced to formulate loop radioactivity anomaly threshold criteria under different operation conditions, so that misjudgment of loop radioactivity anomaly 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 radioactivity abnormality of the primary circuit. The primary radioactivity 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 loop radioactivity anomaly monitoring device according to an embodiment of the present invention, and as shown in fig. 6, a loop radioactivity anomaly monitoring device 10 includes a detection module 11, a determination module 12 and a judgment 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 judging module 13 is configured to obtain the loop radioactivity value and the anomaly threshold value, and compare the loop radioactivity value with the anomaly threshold value to determine whether the loop radioactivity is anomaly.
For specific limitations on the primary circuit radioactivity anomaly monitoring device, reference is made to the above limitations on the primary circuit radioactivity anomaly monitoring method, and no further description is given here. The modules in the loop radioactivity anomaly monitoring device can be fully or partially implemented by software, hardware and a combination thereof. The above modules may be embedded in hardware or may be independent of a processor in the computer device, or may be stored in software in a memory in the computer device, so that the processor may call and execute operations corresponding to the above modules.
Fig. 7 is a schematic diagram of a computer device according to an embodiment of the present invention. The computer device may be a server, and its internal structure 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 includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, computer programs, and a database. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The database of the computer equipment is used for storing the loop radioactivity 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, when executed by the processor, implements a loop radioactivity anomaly monitoring method.
In one embodiment, a computer device is provided, including a memory, a processor, and a computer program stored on the memory and executable on the processor, where the processor executes the computer program to implement the steps of the loop radioactivity anomaly monitoring method of the first embodiment, such as steps S1 to S3 shown in fig. 1. Or the processor, when executing the computer program, implements the functions of the modules/units of the loop radioactivity anomaly monitoring device of the above embodiment, such as the functions of the detection module 11, the determination module 12, and the judgment module 13 shown in fig. 6. In order to avoid repetition, a description thereof is omitted.
It will be clearly understood by those skilled in the art that, for convenience and brevity of description, only the above-mentioned division of each functional unit and module is exemplified, and in practical application, the above-mentioned functional allocation may be performed by different functional units and modules according to needs, i.e. the internal structure of the primary circuit radioactivity anomaly monitoring device is divided into different functional units or modules, so as to perform all or part of the above-mentioned functions.
In an embodiment, a computer readable storage medium is provided, on which a computer program is stored, which when executed by a processor implements the steps of the loop radioactivity anomaly monitoring method of the above embodiment, or which when executed by a processor implements the functions of the modules/units in the loop radioactivity anomaly monitoring device of the above embodiment. In order to avoid repetition, a description thereof is omitted.
It will be appreciated that the computer readable storage medium may comprise: any entity or device capable of carrying the computer program code, a recording medium, a U disk, a removable hard disk, a magnetic disk, an optical disk, a computer Memory, a Read-Only Memory (ROM), a random access Memory (Random Access Memory, RAM), an electrical carrier signal, a telecommunications signal, and so forth.
The above embodiments are only for illustrating the technical solution of the present invention, and not for limiting the same; although the 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 scheme described in the foregoing embodiments can be modified or some technical features thereof can be replaced by equivalents; such modifications and substitutions do not depart from the spirit and scope of the technical solutions of the embodiments of the present invention, and are intended to be included in the scope of the present invention.
Claims (6)
1. A method of monitoring a circuit for radiological anomalies, the method comprising:
detecting a loop radioactivity value;
Determining the operation condition of the unit and an abnormal threshold corresponding to the operation condition, including:
1) The determining the operation condition of the unit comprises the following steps: detecting pressure values at two sides of the steam generator; when the pressure difference of the 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 a main steam pipeline is broken;
Determining an abnormal threshold corresponding to the operating condition, including: acquiring nuclear reactor power, and determining a main steam pipeline fracture threshold according to the nuclear reactor power;
2) The determining the operation condition of the unit comprises the following steps: detecting a leak rate of the steam generator; when the leakage rate is larger than a second preset threshold value, determining the operation working condition of the unit as the cracking of the heat transfer tube of the steam generator;
determining an abnormal threshold corresponding to the operating condition, including: obtaining nuclear reactor power, and determining a steam generator heat transfer tube rupture threshold according to the nuclear reactor power;
3) The determining the operation condition of the unit comprises the following steps: when a shutdown signal is received, and/or a trigger signal of a safety injection system is received, and/or a load reduction of the steam turbine is detected to be more than 25%, and/or a load reduction of the reactor is detected to be more than 25%, determining that the operation working condition of the unit is a significant transient working condition;
Determining an abnormal threshold corresponding to the operating condition, including: acquiring a transient source item value, wherein the transient source item value is a transient threshold value;
4) The determining the operation condition of the unit comprises the following steps: when the pressure difference at two sides of the steam generator is smaller than a first preset threshold, the leakage rate is smaller than a second preset threshold, a shutdown signal is not received, a safety injection system trigger signal is not received, the load reduction of the steam engine is not detected to be more than 25%, and the load reduction of the reactor is not detected to be more than 25%, the operation working condition of the unit is a steady-state operation working condition;
determining an abnormal threshold corresponding to the operating condition, including: obtaining a steady-state source item value, wherein the steady-state source item value is a steady-state threshold value;
The loop radioactivity value and the anomaly threshold value are obtained, and the loop radioactivity value is compared with the anomaly threshold value to determine whether the loop radioactivity is anomalous.
2. The method of claim 1, further comprising:
control performs a response when the loop radioactivity value is greater than the anomaly threshold value and the loop radioactivity is anomalous.
3. The method of claim 2, wherein the controlling the execution response comprises:
triggering a loop radioactive abnormality alarm signal;
closing all isolation valves on the coolant outlet lines;
closing a loop sampling pipeline isolation valve;
Closing the release line isolation valve;
closing the main pump shaft seal high-pressure leakage pipeline isolation valve;
Closing the waste liquid treatment channel isolation valve.
4. A loop radioactivity anomaly monitoring device, the 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 an abnormal threshold corresponding to the operation condition, and comprises the following steps:
1) The determining the operation condition of the unit comprises the following steps: detecting pressure values at two sides of a steam generator, and determining that the operation working condition of the unit is that a main steam pipeline is broken when the pressure difference at two sides of the steam generator is larger than a first preset threshold value;
Determining an abnormal threshold corresponding to the operating condition, including: acquiring nuclear reactor power, and determining a main steam pipeline fracture threshold according to the nuclear reactor power;
2) The determining the operation condition of the unit comprises the following steps: detecting a leak rate of the steam generator; when the leakage rate is larger than a second preset threshold value, determining the operation working condition of the unit as the cracking of the heat transfer tube of the steam generator;
determining an abnormal threshold corresponding to the operating condition, including: obtaining nuclear reactor power, and determining a steam generator heat transfer tube rupture threshold according to the nuclear reactor power;
3) The determining the operation condition of the unit comprises the following steps: when a shutdown signal is received, and/or
When a trigger signal of a safety injection system is received and/or the load reduction of the steam turbine is detected to exceed 25 percent and/or the load reduction of the reactor is detected to exceed 25 percent, determining the operation working condition of the unit as a major transient working condition;
Determining an abnormal threshold corresponding to the operating condition, including: acquiring a transient source item value, wherein the transient source item value is a transient threshold value;
4) The determining the operation condition of the unit comprises the following steps: when the pressure difference at two sides of the steam generator is smaller than a first preset threshold, the leakage rate is smaller than a second preset threshold, a shutdown signal is not received, a safety injection system trigger signal is not received, the load reduction of the steam engine is not detected to be more than 25%, and the load reduction of the reactor is not detected to be more than 25%, the operation working condition of the unit is a steady-state operation working condition;
determining an abnormal threshold corresponding to the operating condition, including: obtaining a steady-state source item value, wherein the steady-state source item value is a steady-state threshold value;
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 or not.
5. A computer readable storage medium storing a computer program, wherein the computer program when executed by a processor implements the loop radioactivity anomaly monitoring method of any one of claims 1 to 3.
6. A computer device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor implements the loop radioactivity anomaly monitoring method of any one of claims 1 to 3 when the computer program is executed.
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