CN114496319A - Method and device for determining running state of high-temperature gas cooled reactor unit - Google Patents

Method and device for determining running state of high-temperature gas cooled reactor unit Download PDF

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CN114496319A
CN114496319A CN202111491024.8A CN202111491024A CN114496319A CN 114496319 A CN114496319 A CN 114496319A CN 202111491024 A CN202111491024 A CN 202111491024A CN 114496319 A CN114496319 A CN 114496319A
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determining
nsss
operation mode
threshold value
average value
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CN114496319B (en
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张晓斌
张冀兰
杨加东
洪伟
刘华
柯海鹏
郭云
蒋勇
魏文斌
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Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Huaneng Nuclear Energy Technology Research Institute Co Ltd
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Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Huaneng Nuclear Energy Technology Research Institute Co Ltd
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • 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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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The disclosure provides a method and a device for determining the operating state of a high-temperature gas cooled reactor unit, and relates to the technical field of nuclear reactor engineering. The method comprises the following steps: determining an operation mode of each NSSS according to a plurality of out-of-stack power range nuclear power channel measurement values, a plurality of out-of-stack intermediate range nuclear power channel measurement values, a plurality of out-of-stack source range channel counting rate measurement values, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each NSSS; and then determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS. Therefore, the operating state of the high-temperature gas cooled reactor unit is determined by determining the working mode corresponding to each NSSS module, so that the operating state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call operating procedures in different states according to the current operating state of the high-temperature gas cooled reactor unit; and the method avoids the occurrence of loopholes in the execution process of the technical specification under different operation states, and improves the nuclear safety supervision level.

Description

Method and device for determining running state of high-temperature gas cooled reactor unit
Technical Field
The disclosure relates to the technical field of nuclear reactor engineering, in particular to a method and a device for determining the operating state of a high-temperature gas cooled reactor unit.
Background
The modular high-temperature gas cooled reactor adopts a structural type that two Nuclear Steam Supply System (NSSS) modules are connected with a Steam turbine generator unit to operate and generate power. During operation, one or two NSSS modules supply steam to the generator set and do work, and the steam turbine drives the generator set to generate electricity.
However, each NSSS module has multiple operation modes, and the operation modes of two NSSS modules are combined, so that the operation state of the high temperature gas cooled reactor unit becomes more complicated, and it is difficult for a worker to determine the operation state of the high temperature gas cooled reactor unit and call an operation rule according to different operation states. Therefore, how to accurately determine the operating mode corresponding to each NSSS module, and further determine the operating state of the high temperature gas cooled reactor unit, is a technical problem that needs to be solved urgently.
Disclosure of Invention
The present disclosure is directed to solving, at least to some extent, one of the technical problems in the related art.
An embodiment of the first aspect of the present disclosure provides a method for determining an operating state of a high temperature gas cooled reactor unit, including:
obtaining a plurality of nuclear power channel measurement values of an out-of-stack power range, a plurality of nuclear power channel measurement values of an out-of-stack middle range, a plurality of counting rate measurement values of an out-of-stack range channel, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each nuclear steam supply system NSSS in the high-temperature gas cooled reactor;
determining an operating mode of each NSSS according to a plurality of off-stack power range nuclear power channel measurement values, a plurality of off-stack intermediate range nuclear power channel measurement values, a plurality of off-stack range channel count rate measurement values, a primary coolant inlet temperature measurement value, and a primary coolant outlet temperature measurement value corresponding to each NSSS;
and determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS.
Optionally, before the determining the operation mode of each NSSS, the method further includes:
obtaining a first average value corresponding to the plurality of off-stack power range nuclear power channel measurement values, a second average value corresponding to the plurality of off-stack intermediate range nuclear power channel measurement values, a third average value corresponding to the plurality of off-stack range channel count rate measurement values, and a fourth average value of the primary coolant inlet temperature measurement value and the primary coolant outlet temperature measurement value corresponding to each NSSS;
in response to the second average being less than a first threshold, a trip depth is obtained.
Optionally, the determining the operation mode of each NSSS includes:
and determining that the operation mode of the NSSS is an operation mode one in response to the first average value being greater than or equal to a second threshold value.
Optionally, the determining the operation mode of each NSSS includes:
determining that the NSSS is in a second operating mode in response to the second average value being greater than a first threshold and less than a second threshold;
or,
determining that the operation mode of the NSSS is an operation mode two in response to the third average value being greater than a third threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode two in response to the second average value being smaller than the first threshold value and the trip depth being smaller than a fourth threshold value.
Optionally, the determining the operation mode of each NSSS includes:
determining that the operation mode of the NSSS is an operation mode three in response to the third average value being smaller than a third threshold value and the fourth average value being greater than or equal to a fifth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode three in response to the second average value being smaller than a first threshold value, the fourth average value being greater than or equal to a fifth threshold value, and the trip depth being greater than a fourth threshold value.
Optionally, the determining the operation mode of each NSSS includes:
determining that the operation mode of the NSSS is an operation mode four in response to the third average value being less than a third threshold value and the fourth average value being greater than or equal to a sixth threshold value and less than a fifth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode four in response to the second average value being less than a first threshold value, the fourth average value being greater than or equal to a sixth threshold value and less than a fifth threshold value, and the trip depth being greater than a fourth threshold value.
Optionally, the determining the operation mode of each NSSS includes:
determining that the operation mode of the NSSS is an operation mode five in response to the third average value being less than a third threshold value and the fourth average value being less than a sixth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode five in response to the second average value being less than a first threshold value, the fourth average value being less than a sixth threshold value, and the trip depth being greater than a fourth threshold value.
An embodiment of a second aspect of the present disclosure provides an apparatus for determining an operating state of a high temperature gas cooled reactor unit, including:
the system comprises a first acquisition module, a second acquisition module and a control module, wherein the first acquisition module is used for acquiring a plurality of nuclear power channel measurement values of an out-of-stack power range, a plurality of nuclear power channel measurement values of an out-of-stack middle range, a plurality of counting rate measurement values of an out-of-stack range channel, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value which correspond to each nuclear steam supply system NSSS in the high-temperature gas cooled reactor;
a first determining module for determining an operating mode of each NSSS based on a plurality of off-stack power range nuclear power channel measurements, a plurality of off-stack intermediate range nuclear power channel measurements, a plurality of off-stack source range channel count rate measurements, a primary coolant inlet temperature measurement, and a primary coolant outlet temperature measurement corresponding to said each NSSS;
and the second determination module is used for determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS.
Optionally, the system further includes a second obtaining module, specifically configured to:
obtaining a first average value corresponding to the plurality of off-stack power range nuclear power channel measurement values, a second average value corresponding to the plurality of off-stack intermediate range nuclear power channel measurement values, a third average value corresponding to the plurality of off-stack range channel count rate measurement values, and a fourth average value of the primary coolant inlet temperature measurement value and the primary coolant outlet temperature measurement value corresponding to each NSSS;
in response to the second average being less than a first threshold, a trip depth is obtained.
Optionally, the first determining module is specifically configured to:
and determining that the operation mode of the NSSS is an operation mode one in response to the first average value being greater than or equal to a second threshold value.
Optionally, the first determining module is specifically configured to:
determining that the NSSS is in a second operating mode in response to the second average value being greater than a first threshold and less than a second threshold;
or,
determining that the operation mode of the NSSS is an operation mode two in response to the third average value being greater than a third threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode two in response to the second average value being smaller than the first threshold value and the trip depth being smaller than a fourth threshold value.
Optionally, the first determining module is specifically configured to:
determining that the operation mode of the NSSS is an operation mode three in response to the third average value being smaller than a third threshold value and the fourth average value being greater than or equal to a fifth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode three in response to the second average value being smaller than a first threshold value, the fourth average value being greater than or equal to a fifth threshold value, and the trip depth being greater than a fourth threshold value.
Optionally, the first determining module is specifically configured to:
determining that the operation mode of the NSSS is an operation mode four in response to the third average value being less than a third threshold value and the fourth average value being greater than or equal to a sixth threshold value and less than a fifth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode four in response to the second average value being less than a first threshold value, the fourth average value being greater than or equal to a sixth threshold value and less than a fifth threshold value, and the trip depth being greater than a fourth threshold value.
Optionally, the first determining module is specifically configured to:
determining that the operation mode of the NSSS is an operation mode five in response to the third average value being less than a third threshold value and the fourth average value being less than a sixth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode five in response to the second average value being less than a first threshold value, the fourth average value being less than a sixth threshold value, and the trip depth being greater than a fourth threshold value.
An embodiment of a third aspect of the present disclosure provides an electronic device, including: the system comprises a memory, a processor and a computer program stored on the memory and capable of running on the processor, wherein the processor executes the program to realize the method for determining the running state of the high-temperature gas-cooled reactor unit according to the embodiment of the first aspect of the disclosure.
An embodiment of a fourth aspect of the present disclosure provides a computer-readable storage medium, which stores a computer program, and when the computer program is executed by a processor, the computer program implements the method for determining the operating state of the high temperature gas-cooled reactor unit as set forth in the embodiment of the first aspect of the present disclosure.
An embodiment of a fifth aspect of the present disclosure provides a computer program product, which includes a computer program and, when being executed by a processor, implements the method for determining the operating state of a high temperature gas cooled reactor unit as set forth in the embodiment of the first aspect of the present disclosure.
The method and the device for determining the running state of the high-temperature gas cooled reactor unit have the following beneficial effects:
in the embodiment of the disclosure, the operation mode of each NSSS can be determined according to a plurality of off-stack power range nuclear power channel measurement values, a plurality of off-stack intermediate range nuclear power channel measurement values, a plurality of off-stack source range channel counting rate measurement values, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each NSSS; and then determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS. Therefore, the operating state of the high-temperature gas cooled reactor unit is determined by determining the working mode corresponding to each NSSS module, so that the operating state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call operating procedures in different states according to the current operating state of the high-temperature gas cooled reactor unit; and the method avoids the occurrence of loopholes in the execution process of the technical specification under different operation states, and improves the nuclear safety supervision level.
Additional aspects and advantages of the disclosure will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the disclosure.
Drawings
The above and/or additional aspects and advantages of the present disclosure will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings of which:
fig. 1 is a schematic flowchart illustrating a method for determining an operating state of a high temperature gas cooled reactor unit according to an embodiment of the present disclosure;
fig. 2 is a schematic flow chart illustrating a method for determining an operating state of a high temperature gas cooled reactor unit according to another embodiment of the present disclosure;
fig. 2a is a schematic flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure;
fig. 2b is a schematic flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure;
fig. 2c is a schematic flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure;
fig. 2d is a schematic flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure;
fig. 2e is a schematic flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure;
fig. 3 is a schematic structural diagram of an apparatus for determining an operating state of a high temperature gas cooled reactor unit according to an embodiment of the present disclosure;
FIG. 4 illustrates a block diagram of an exemplary electronic device suitable for use in implementing embodiments of the present disclosure.
Detailed Description
Reference will now be made in detail to the embodiments of the present disclosure, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the drawings are exemplary and intended to be illustrative of the present disclosure, and should not be construed as limiting the present disclosure.
The following describes a method and an apparatus for determining an operating state of a high temperature gas cooled reactor unit according to an embodiment of the present disclosure with reference to the drawings.
Fig. 1 is a schematic flowchart of a method for determining an operating state of a high temperature gas cooled reactor unit according to an embodiment of the present disclosure.
The embodiment of the disclosure is exemplified by the method for determining the operating state of the high temperature gas-cooled reactor unit being configured in the device for determining the operating state of the high temperature gas-cooled reactor unit, and the device for determining the operating state of the high temperature gas-cooled reactor unit may be applied to any electronic equipment, so that the electronic equipment may perform a function of determining the operating state of the high temperature gas-cooled reactor unit.
The electronic device may be a Personal Computer (PC), a cloud device, a mobile device, and the like, and the mobile device may be a hardware device having various operating systems, touch screens, and/or display screens, such as a mobile phone, a tablet Computer, a Personal digital assistant, a wearable device, and an in-vehicle device.
As shown in fig. 1, the method for determining the operating state of the high temperature gas cooled reactor unit may include the following steps:
step 101, obtaining a plurality of nuclear power channel measurement values of an out-of-stack power range, a plurality of nuclear power channel measurement values of an out-of-stack middle range, a plurality of counting rate measurement values of an out-of-stack range channel, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each NSSS in the high-temperature gas cooled reactor.
It can be understood that the dual NSSS high temperature gas cooled reactor includes two NSSS, and when the operating state of the high temperature gas cooled reactor unit is determined, the operating mode corresponding to each NSSS needs to be determined first.
It should be noted that each NSSS includes 4 off-stack power range channels, 2 off-stack middle range channels, and 2 off-stack source range channels. Therefore, in the embodiment of the disclosure, 4 out-of-stack power range nuclear power channel measurement values, 2 out-of-stack middle range nuclear power channel measurement values, and 2 out-of-stack source range channel count rate measurement values can be obtained. The present disclosure is not limited thereto.
Wherein the main coolant inlet temperature measurement may be an average of temperatures within the plurality of main coolant inlet passages; the main coolant outlet temperature measurement may be an average of the temperatures within the plurality of main coolant outlet passages. The present disclosure is not limited thereto.
Step 102, determining an operation mode of each NSSS according to a plurality of off-stack power range nuclear power channel measurement values, a plurality of off-stack intermediate range nuclear power channel measurement values, a plurality of off-stack source range channel count rate measurement values, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each NSSS.
Each NSSS may have 5 operation modes, which are: the method comprises the following steps of operating in a first operating mode, namely power operation, operating in a second operating mode, starting, operating in a third operating mode, namely shutdown, operating in a fourth operating mode, namely cold shutdown, and operating in a fifth operating mode, namely maintenance shutdown. The present disclosure is not limited thereto.
Optionally, after obtaining the multiple off-stack power range nuclear power channel measurement values, the multiple off-stack intermediate range nuclear power channel measurement values, the multiple off-stack external range channel count rate measurement values, the main coolant inlet temperature measurement value, and the main coolant outlet temperature measurement value corresponding to each NSSS, the obtained values may be input into a Distributed Control System (DCS) System, and an operation mode corresponding to each NSSS is determined by logic.
And 103, determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS.
It can be understood that the dual NSSS high temperature gas cooled reactor includes two NSSS, each having 5 operation modes, and the high temperature gas cooled reactor unit has 25 operation states. The operating state of the high temperature gas cooled reactor unit may be as shown in table 1.
TABLE 1
Figure BDA0003399358680000071
NSSS #1 is the 1 st NSSS in the high temperature gas cooled reactor, NSSS #2 is the 2 nd NSSS in the high temperature gas cooled reactor, and 1#4 and 2#5 indicate that NSSS #1 is the operation mode 4 and NSSS #2 is the operation mode 5.
It is understood that each element and each corresponding relationship in table 1 exist independently; these elements, correspondences, are exemplarily listed in the same table, but do not represent that all elements, correspondences, in the table must coexist according to the representation in table 1. Wherein the value of each element and each correspondence is independent of any other element value or correspondence in table 1. Therefore, as can be understood by those skilled in the art, the value of each element and each corresponding relationship in table 1 are independent embodiments.
Optionally, after the operating state of the high temperature gas cooled reactor unit is determined according to the operating mode of each NSSS, the operating state of the high temperature gas cooled reactor unit may be displayed on a large screen of the main control room for visualization. Therefore, an operator can call operation regulations in different states according to the current operation state of the high-temperature gas cooled reactor unit; under the condition of an emergency, making a correct response according to the running state of the current high-temperature gas cooled reactor unit; and the method avoids the occurrence of loopholes in the execution process of the technical specification under different operation states, and improves the nuclear safety supervision level.
It should be noted that the principle of determining the operating state of the high temperature gas cooled reactor unit according to the measurement parameter corresponding to each NSSS in the embodiment of the present disclosure is also applicable to other types of nuclear reactors. Such as a pressurized water reactor, a boiling water reactor, etc. The state combinations of NSSS and regular islands can be considered simultaneously, as desired, using the same principles. The present disclosure is not limited thereto.
In the embodiment of the disclosure, the operation mode of each NSSS can be determined according to a plurality of off-stack power range nuclear power channel measurement values, a plurality of off-stack intermediate range nuclear power channel measurement values, a plurality of off-stack source range channel counting rate measurement values, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each NSSS; and then determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS. Therefore, the operating state of the high-temperature gas cooled reactor unit is determined by determining the working mode corresponding to each NSSS module, so that the operating state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call operating procedures in different states according to the current operating state of the high-temperature gas cooled reactor unit; and the method avoids the occurrence of loopholes in the execution process of the technical specification under different operation states, and improves the nuclear safety supervision level.
Fig. 2 is a schematic flowchart illustrating a method for determining an operating state of a high temperature gas cooled reactor unit according to an embodiment of the present disclosure, and as shown in fig. 2, the method for determining an operating state of a high temperature gas cooled reactor unit may include the following steps:
step 201, obtaining a plurality of nuclear power channel measurement values of the out-of-stack power range, a plurality of nuclear power channel measurement values of the out-of-stack middle range, a plurality of counting rate measurement values of the out-of-stack range channel, a measurement value of the main coolant inlet temperature, and a measurement value of the main coolant outlet temperature corresponding to each nuclear steam supply system NSSS in the high temperature gas cooled reactor.
The specific implementation form of step 201 may refer to detailed descriptions in other embodiments in this disclosure, and details are not repeated here.
Step 202, determining a first average corresponding to a plurality of off-stack power range nuclear power channel measurements, a second average corresponding to a plurality of off-stack intermediate range nuclear power channel measurements, a third average corresponding to a plurality of off-stack range channel count rate measurements, and a fourth average of a primary coolant inlet temperature measurement and a primary coolant outlet temperature measurement corresponding to each NSSS.
For example, if each NSSS corresponds to 4 nuclear power channel measurements in the off-stack power range, P is the number1、P2、P3、P4The first average value is
Figure BDA0003399358680000081
If each NSSS corresponds to 2 nuclear power channel measurement values of the out-of-stack power range, the nuclear power channel measurement values are respectively P5、P6Then the second average value is
Figure BDA0003399358680000082
If each NSSS corresponds to 2 out-of-pile source range channel counting rate measurement values, the measurement values are S1、S2Then the third average value is
Figure BDA0003399358680000083
If the measured value of the main coolant inlet temperature is T1The primary coolant outlet temperature measurement is T2Then the fourth average value is
Figure BDA0003399358680000084
And step 203, acquiring the shutdown depth under the condition that the second average value is smaller than the first threshold value.
The first threshold value can be determined according to the rated nuclear power of the current high-temperature gas cooled reactor. For example, the first threshold may be 0.01% of the rated nuclear power of the high temperature gas cooled reactor, which is not limited by the present disclosure.
It can be understood that, when the second average value corresponding to the multiple off-stack mid-range nuclear power channel measurement values is smaller than the first threshold, the operating mode corresponding to the NSSS cannot be accurately determined only by using the measurement value corresponding to the nuclear power. Therefore, under the condition that the second average value is smaller than the first threshold value, the physical quantity of the reflecting property is introduced, the working mode corresponding to the NSSS is comprehensively judged, and the accuracy of NSSS working mode judgment is improved.
Wherein the shutdown depth can be the negative reactivity achieved by the reactor when all control poisons are put into the core.
Step 204, determining an operation mode of each NSSS according to the first average value, the second average value, the third average value and the fourth average value corresponding to each NSSS.
Optionally, when the first average value is greater than or equal to the second threshold, the operation mode of the NSSS is determined as operation mode one.
The magnitude of the second threshold value can be determined according to the rated nuclear power of the current high-temperature gas cooled reactor. For example, the second threshold may be 30% of the rated nuclear power of the high temperature gas cooled reactor, which is not limited by the present disclosure.
Fig. 2a is a schematic flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure. As shown in FIG. 2a, the nuclear power channel measurements P are taken at 4 off-stack power ranges1、P2、P3、P4Corresponding first average value Pavg1Greater than or equal to the second threshold value of 30% PRated valueIn the case of (3), the operation mode of NSSS is determined as operation mode one.
Optionally, when the second average value is greater than the first threshold and smaller than the second threshold, it is determined that the NSSS is in the second operation mode; or determining that the operation mode of the NSSS is the second operation mode when the third average value is greater than the third threshold value; or determining that the operation mode of the NSSS is the second operation mode under the condition that the second average value is smaller than the first threshold value and the shutdown depth is smaller than the fourth threshold value.
The third threshold value may be determined according to an engineering empirical value, and the engineering empirical value may be determined according to a starting empirical value of the current high-temperature gas-cooled reactor. For example, the third threshold may be 20cps, which is not limited by this disclosure.
The fourth threshold corresponding to the shutdown depth may also be determined according to an empirical value, for example, the fourth threshold may be 1000pcm, which is not limited by the present disclosure.
Fig. 2b is a flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure. As shown in FIG. 2b, the second average value P corresponding to the 2 out-of-stack mid-range nuclear power channel measurementsavg2Greater than a first threshold value of 0.01% PRated valueAnd less than the second threshold value by 30% PRated valueUnder the condition of (1), determining that NSSS is an operation mode II; or, at the third mean value Savg3And determining the operation mode of the NSSS to be the operation mode under the condition that the operation mode is larger than the third threshold value of 20cpsII, performing secondary filtration; or, at the second average value Pavg2Less than the first threshold value of 0.01% PRated valueAnd when the shutdown depth ρ is less than the fourth threshold 1000pcm, determining that the operation mode of the NSSS is an operation mode two.
Optionally, when the third average value is smaller than the third threshold and the fourth average value is greater than or equal to the fifth threshold, determining that the operation mode of the NSSS is the third operation mode; or determining that the operation mode of the NSSS is the third operation mode under the conditions that the second average value is smaller than the first threshold value, the fourth average value is larger than or equal to the fifth threshold value, and the shutdown depth is larger than the fourth threshold value.
Wherein the fifth threshold is a threshold corresponding to a main coolant inlet temperature measurement of T1 and a main coolant outlet temperature measurement of an average of T2. For example, the fifth threshold may be 150 ℃, which is not limited by this disclosure.
Fig. 2c is a schematic flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure. As shown in fig. 2c, at the third average value Savg3Less than the third threshold value of 20cps, and a fourth average value Tavg4Determining the operation mode of NSSS to be operation mode three under the condition that the temperature is greater than or equal to the fifth threshold value of 150 ℃; or, at the second average value Pavg2Less than the first threshold value of 0.01% PRated valueThe fourth average value Tavg4And when the temperature is larger than or equal to the fifth threshold value of 150 ℃ and the shutdown depth rho is larger than the fourth threshold value of 1000pcm, determining that the operation mode of the NSSS is the third operation mode.
Optionally, when the third average value is smaller than the third threshold value, and the fourth average value is greater than or equal to the sixth threshold value and smaller than the fifth threshold value, determining that the operation mode of the NSSS is the fourth operation mode; or determining that the operation mode of the NSSS is the fourth operation mode when the second average value is smaller than the first threshold value, the fourth average value is greater than or equal to the sixth threshold value and smaller than the fifth threshold value, and the shutdown depth is greater than the fourth threshold value.
Wherein the fifth threshold is a threshold corresponding to a main coolant inlet temperature measurement of T1 and a main coolant outlet temperature measurement of an average of T2. For example, the sixth threshold may be 50 ℃, which is not limited by this disclosure.
Fig. 2d is a flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure. As shown in fig. 2d, at the third average value Savg3Less than the third threshold value of 20cps, and the fourth average value Tavg4When the temperature is greater than or equal to the sixth threshold value 50 ℃ and is less than the fifth threshold value 150 ℃, determining that the operation mode of the NSSS is an operation mode four; or, at the second average value Pavg2Less than the first threshold value of 0.01% PRated valueThe fourth average value Tavg4And when the third threshold value is greater than or equal to 50 ℃ and less than 150 ℃ and the shutdown depth rho is greater than 1000pcm, determining that the operation mode of the NSSS is the fourth operation mode.
Optionally, when the third average value is smaller than the third threshold and the fourth average value is smaller than the sixth threshold, determining that the operation mode of the NSSS is the operation mode five; or determining that the operation mode of the NSSS is the operation mode five under the conditions that the second average value is smaller than the first threshold value, the fourth average value is smaller than the sixth threshold value and the shutdown depth is larger than the fourth threshold value.
Fig. 2e is a schematic flowchart illustrating a method for determining an operation mode of a nuclear steam supply system according to an embodiment of the present disclosure. As shown in fig. 2e, at the third average value Savg3Less than the third threshold value of 20cps, and the fourth average value Tavg4Determining the operation mode of the NSSS to be an operation mode V under the condition that the temperature is lower than a sixth threshold value 50 ℃; or, at the second average value Pavg2Less than the first threshold value of 0.01% PRated valueThe fourth average value Tavg4And when the temperature is lower than the sixth threshold value 50 ℃ and the shutdown depth p is higher than the fourth threshold value 1000pcm, determining that the operation mode of the NSSS is the fifth operation mode.
And step 205, determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS.
The specific implementation form of step 205 may refer to detailed descriptions in other embodiments in this disclosure, and details are not repeated here.
According to the embodiment of the disclosure, firstly, an operation mode of each NSSS is determined according to a first average value corresponding to a plurality of out-of-stack power range nuclear power channel measurement values corresponding to each NSSS, a second average value corresponding to a plurality of out-of-stack middle range nuclear power channel measurement values, a third average value corresponding to a plurality of out-of-stack source range channel counting rate measurement values, a fourth average value of a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value and a shutdown depth, and then, the operation state of the high-temperature gas cooled reactor unit is determined according to the operation mode of each NSSS. Therefore, the accuracy of judging the NSSS operation mode is further improved, so that the accuracy of the operation state of the high-temperature gas cooled reactor unit is further improved, and an operator can call operation rules in different states according to the current operation state of the high-temperature gas cooled reactor unit; and moreover, leaks are avoided in the execution process of the technical specification under different running states, and the nuclear safety supervision level is improved.
In order to realize the above embodiment, the present disclosure further provides a device for determining an operating state of a high temperature gas cooled reactor unit.
Fig. 3 is a schematic structural diagram of an apparatus for determining an operating state of a high temperature gas cooled reactor unit according to an embodiment of the present disclosure. As shown in fig. 3, the device 300 for determining the operating state of the high temperature gas cooled reactor unit may include: a first obtaining module 310, a first determining module 320, and a second determining module 330.
The first obtaining module 310 is configured to obtain a plurality of off-stack power range nuclear power channel measurement values, a plurality of off-stack intermediate range nuclear power channel measurement values, a plurality of off-stack external range channel count rate measurement values, a main coolant inlet temperature measurement value, and a main coolant outlet temperature measurement value corresponding to each nuclear steam supply system NSSS in the high temperature gas cooled reactor;
a first determining module 320 for determining an operating mode of each NSSS based on a plurality of off-stack power range nuclear power channel measurements, a plurality of off-stack intermediate range nuclear power channel measurements, a plurality of off-stack range channel count rate measurements, a primary coolant inlet temperature measurement, and a primary coolant outlet temperature measurement corresponding to each NSSS;
the second determining module 330 is configured to determine an operating state of the high temperature gas cooled reactor unit according to an operating mode of each NSSS.
Optionally, the system further includes a second obtaining module, specifically configured to:
obtaining a first average value corresponding to a plurality of out-of-stack power range nuclear power channel measurement values, a second average value corresponding to a plurality of out-of-stack intermediate range nuclear power channel measurement values, a third average value corresponding to a plurality of out-of-stack range channel counting rate measurement values and a fourth average value of a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each NSSS;
in response to the second average being less than the first threshold, a trip depth is obtained.
Optionally, the first determining module 320 is specifically configured to:
and determining the operation mode of the NSSS to be the first operation mode in response to the first average value being larger than or equal to the second threshold value.
Optionally, the first determining module 320 is specifically configured to:
determining that the NSSS is in a second operation mode in response to the second average value being greater than the first threshold and less than a second threshold;
or,
in response to the third average value being greater than a third threshold value, determining the operating mode of the NSSS to be operating mode two;
or,
and determining the operation mode of the NSSS to be an operation mode two in response to the second average value being smaller than the first threshold value and the shutdown depth being smaller than a fourth threshold value.
Optionally, the first determining module 320 is specifically configured to:
determining that the operation mode of the NSSS is an operation mode three in response to the third average value being smaller than the third threshold value and the fourth average value being greater than or equal to the fifth threshold value;
or,
and determining the operation mode of the NSSS to be an operation mode three in response to the second average value being smaller than the first threshold value, the fourth average value being greater than or equal to a fifth threshold value and the shutdown depth being greater than a fourth threshold value.
Optionally, the first determining module 320 is specifically configured to:
determining that the operation mode of the NSSS is an operation mode four in response to the third average value being smaller than the third threshold value, the fourth average value being greater than or equal to the sixth threshold value and smaller than the fifth threshold value;
or,
and determining that the operation mode of the NSSS is the fourth operation mode in response to the second average value being less than the first threshold value, the fourth average value being greater than or equal to the sixth threshold value and less than the fifth threshold value, and the shutdown depth being greater than the fourth threshold value.
Optionally, the first determining module 320 is specifically configured to:
determining that the operation mode of the NSSS is an operation mode five in response to the third average value being smaller than the third threshold value and the fourth average value being smaller than the sixth threshold value;
or,
and determining the operation mode of the NSSS to be an operation mode five in response to the second average value being smaller than the first threshold value, the fourth average value being smaller than the sixth threshold value and the trip depth being larger than the fourth threshold value.
The functions and specific implementation principles of the modules in the embodiments of the present disclosure may refer to the embodiments of the methods, and are not described herein again.
The device for determining the operation state of the high-temperature gas cooled reactor unit can determine the operation mode of each NSSS according to a plurality of nuclear power channel measurement values of the out-of-stack power range, a plurality of nuclear power channel measurement values of the out-of-stack middle range, a plurality of counting rate measurement values of the out-of-stack range channel, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each NSSS; and then determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS. Therefore, the operating state of the high-temperature gas cooled reactor unit is determined by determining the working mode corresponding to each NSSS module, so that the operating state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call operating procedures in different states according to the current operating state of the high-temperature gas cooled reactor unit; and the method avoids the occurrence of loopholes in the execution process of the technical specification under different operation states, and improves the nuclear safety supervision level.
In order to implement the above embodiments, the present disclosure also provides an electronic device, including: the system comprises a memory, a processor and a computer program stored on the memory and capable of running on the processor, wherein when the processor executes the program, the method for determining the running state of the high-temperature gas-cooled reactor unit is realized according to the embodiment of the disclosure.
In order to implement the foregoing embodiments, the present disclosure further provides a computer-readable storage medium storing a computer program, where the computer program, when executed by a processor, implements the method for determining the operating state of the high temperature gas cooled reactor unit according to the foregoing embodiments of the present disclosure.
In order to implement the foregoing embodiments, the present disclosure also provides a computer program product, which includes a computer program, and when the computer program is executed by a processor, the computer program implements the method for determining the operating state of the high temperature gas cooled reactor unit according to the foregoing embodiments of the present disclosure.
FIG. 4 illustrates a block diagram of an exemplary electronic device suitable for use in implementing embodiments of the present disclosure. The electronic device 12 shown in fig. 4 is only an example and should not bring any limitations to the functionality and scope of use of the embodiments of the present disclosure.
As shown in FIG. 4, electronic device 12 is embodied in the form of a general purpose computing device. The components of computer device 12 may include, but are not limited to: one or more processors or processing units 16, a system memory 28, and a bus 18 that couples various system components including the system memory 28 and the processing unit 16.
Bus 18 represents one or more of any of several types of bus structures, including a memory bus or memory controller, a peripheral bus, an accelerated graphics port, and a processor or local bus using any of a variety of bus architectures. These architectures include, but are not limited to, Industry Standard Architecture (ISA) bus, Micro Channel Architecture (MAC) bus, enhanced ISA bus, Video Electronics Standards Association (VESA) local bus, and Peripheral Component Interconnect (PCI) bus, to name a few.
Computer device 12 typically includes a variety of computer system readable media. Such media may be any available media that is accessible by computer device 12 and includes both volatile and nonvolatile media, removable and non-removable media.
Memory 28 may include computer system readable media in the form of volatile Memory, such as Random Access Memory (RAM) 30 and/or cache Memory 32. Computer device 12 may further include other removable/non-removable, volatile/nonvolatile computer system storage media. By way of example only, storage system 34 may be used to read from and write to non-removable, nonvolatile magnetic media (not shown in FIG. 4, and commonly referred to as a "hard drive"). Although not shown in FIG. 4, a disk drive for reading from and writing to a removable, nonvolatile magnetic disk (e.g., a "floppy disk") and an optical disk drive for reading from or writing to a removable, nonvolatile optical disk (e.g., a Compact disk Read Only Memory (CD-ROM), a Digital versatile disk Read Only Memory (DVD-ROM), or other optical media) may be provided. In these cases, each drive may be connected to bus 18 by one or more data media interfaces. Memory 28 may include at least one program product having a set (e.g., at least one) of program modules that are configured to carry out the functions of embodiments of the disclosure.
A program/utility 40 having a set (at least one) of program modules 42 may be stored, for example, in memory 28, such program modules 42 including, but not limited to, an operating system, one or more application programs, other program modules, and program data, each of which examples or some combination thereof may comprise an implementation of a network environment. Program modules 42 generally perform the functions and/or methodologies of the embodiments described in this disclosure.
Computer device 12 may also communicate with one or more external devices 14 (e.g., keyboard, pointing device, display 24, etc.), with one or more devices that enable a user to interact with computer device 12, and/or with any devices (e.g., network card, modem, etc.) that enable computer device 12 to communicate with one or more other computing devices. Such communication may be through an input/output (I/O) interface 22. Moreover, computer device 12 may also communicate with one or more networks (e.g., a Local Area Network (LAN), a Wide Area Network (WAN), and/or a public Network such as the Internet) via Network adapter 20. As shown, network adapter 20 communicates with the other modules of computer device 12 via bus 18. It should be understood that although not shown in the figures, other hardware and/or software modules may be used in conjunction with computer device 12, including but not limited to: microcode, device drivers, redundant processing units, external disk drive arrays, RAID systems, tape drives, and data backup storage systems, among others.
The processing unit 16 executes various functional applications and data processing, for example, implementing the methods mentioned in the foregoing embodiments, by executing programs stored in the system memory 28.
According to the technical scheme, the operation mode of each NSSS can be determined according to a plurality of out-of-stack power range nuclear power channel measurement values, a plurality of out-of-stack middle range nuclear power channel measurement values, a plurality of out-of-stack source range channel counting rate measurement values, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each NSSS; and then determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS. Therefore, the operating state of the high-temperature gas cooled reactor unit is determined by determining the working mode corresponding to each NSSS module, so that the operating state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call operating procedures in different states according to the current operating state of the high-temperature gas cooled reactor unit; and the method avoids the occurrence of loopholes in the execution process of the technical specification under different operation states, and improves the nuclear safety supervision level.
In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., 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 present disclosure. In this specification, the schematic representations of the terms used above are not necessarily intended to 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. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present disclosure, "a plurality" means at least two, e.g., two, three, etc., unless explicitly specifically limited otherwise.
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 steps of a custom logic function or process, and alternate implementations are included within the scope of the preferred embodiment of the present disclosure 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 embodiments of the present disclosure.
The logic and/or steps represented in the flowcharts or otherwise described herein, e.g., an ordered listing of executable instructions that can be considered to implement logical functions, can be embodied in any computer-readable medium for use by or in connection with an instruction execution system, apparatus, or device, such as a computer-based system, processor-containing system, or other system that can fetch the instructions from the instruction execution system, apparatus, or device and execute the instructions. For the purposes of this description, a "computer-readable medium" can be any means that can contain, store, communicate, propagate, or transport the program for use by or in connection with the instruction execution system, apparatus, or device. More specific examples (a non-exhaustive list) of the computer-readable medium would include the following: an electrical connection (electronic device) having one or more wires, a portable computer diskette (magnetic device), a Random Access Memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber device, and a portable compact disc read-only memory (CDROM). Additionally, the computer-readable medium could even be paper or another suitable medium upon which the program is printed, as the program can be electronically captured, via for instance optical scanning of the paper or other medium, then compiled, interpreted or otherwise processed in a suitable manner if necessary, and then stored in a computer memory.
It should be understood that portions of the present disclosure 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. 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.
It will be understood by those skilled in the art that all or part of the steps carried by the method for implementing the above embodiments may be implemented by hardware related to instructions of a program, which may be stored in a computer readable storage medium, and when the program is executed, the program includes one or a combination of the steps of the method embodiments.
In addition, functional units in the embodiments of the present disclosure may be integrated into one processing module, or each unit may exist alone physically, or two or more units are integrated into one module. The integrated module can be realized in a hardware mode, and can also be realized in a software functional module mode. The integrated module, if implemented in the form of a software functional module and sold or used as a stand-alone product, may also be stored in a computer readable storage medium.
The storage medium mentioned above may be a read-only memory, a magnetic or optical disk, etc. Although embodiments of the present disclosure have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present disclosure, and that changes, modifications, substitutions and alterations may be made to the above embodiments by those of ordinary skill in the art within the scope of the present disclosure.

Claims (17)

1. A method for determining the operation state of a high-temperature gas cooled reactor unit is characterized by comprising the following steps:
obtaining a plurality of nuclear power channel measurement values of an out-of-stack power range, a plurality of nuclear power channel measurement values of an out-of-stack middle range, a plurality of counting rate measurement values of an out-of-stack range channel, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value corresponding to each nuclear steam supply system NSSS in the high-temperature gas cooled reactor;
determining an operating mode of each NSSS according to a plurality of off-stack power range nuclear power channel measurement values, a plurality of off-stack intermediate range nuclear power channel measurement values, a plurality of off-stack range channel count rate measurement values, a primary coolant inlet temperature measurement value, and a primary coolant outlet temperature measurement value corresponding to each NSSS;
and determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS.
2. The method of claim 1, further comprising, prior to said determining the operating mode of each NSSS:
obtaining a first average value corresponding to the plurality of off-stack power range nuclear power channel measurement values, a second average value corresponding to the plurality of off-stack intermediate range nuclear power channel measurement values, a third average value corresponding to the plurality of off-stack range channel count rate measurement values, and a fourth average value of the primary coolant inlet temperature measurement value and the primary coolant outlet temperature measurement value corresponding to each NSSS;
in response to the second average being less than a first threshold, a trip depth is obtained.
3. The method of claim 2, wherein determining the operating mode for each NSSS comprises:
and determining that the operation mode of the NSSS is an operation mode one in response to the first average value being greater than or equal to a second threshold value.
4. The method of claim 2, wherein determining the operating mode for each NSSS comprises:
determining that the NSSS is in a second operating mode in response to the second average value being greater than a first threshold and less than a second threshold;
or,
determining that the operation mode of the NSSS is an operation mode two in response to the third average value being greater than a third threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode two in response to the second average value being smaller than the first threshold value and the trip depth being smaller than a fourth threshold value.
5. The method of claim 2, wherein determining the operating mode for each NSSS comprises:
determining that the operation mode of the NSSS is an operation mode three in response to the third average value being smaller than a third threshold value and the fourth average value being greater than or equal to a fifth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode three in response to the second average value being smaller than a first threshold value, the fourth average value being greater than or equal to a fifth threshold value, and the trip depth being greater than a fourth threshold value.
6. The method of claim 2, wherein determining the operating mode for each NSSS comprises:
determining that the operation mode of the NSSS is an operation mode four in response to the third average value being less than a third threshold value and the fourth average value being greater than or equal to a sixth threshold value and less than a fifth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode four in response to the second average value being less than a first threshold value, the fourth average value being greater than or equal to a sixth threshold value and less than a fifth threshold value, and the trip depth being greater than a fourth threshold value.
7. The method of claim 2, wherein determining the operating mode for each NSSS comprises:
in response to the third average value being less than a third threshold and the fourth average value being less than a sixth threshold, determining that the operating mode of the NSSS is operating mode five;
or,
and determining that the operation mode of the NSSS is an operation mode five in response to the second average value being less than a first threshold value, the fourth average value being less than a sixth threshold value, and the trip depth being greater than a fourth threshold value.
8. An apparatus for determining an operating condition of a high temperature gas cooled reactor unit, comprising:
the system comprises a first acquisition module, a second acquisition module and a control module, wherein the first acquisition module is used for acquiring a plurality of nuclear power channel measurement values of an out-of-stack power range, a plurality of nuclear power channel measurement values of an out-of-stack middle range, a plurality of counting rate measurement values of an out-of-stack range channel, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value which correspond to each nuclear steam supply system NSSS in the high-temperature gas cooled reactor;
a first determining module for determining an operating mode of each NSSS based on a plurality of off-stack power range nuclear power channel measurements, a plurality of off-stack intermediate range nuclear power channel measurements, a plurality of off-stack source range channel count rate measurements, a primary coolant inlet temperature measurement, and a primary coolant outlet temperature measurement corresponding to said each NSSS;
and the second determination module is used for determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS.
9. The apparatus of claim 8, further comprising a second obtaining module, specifically configured to:
obtaining a first average value corresponding to the plurality of off-stack power range nuclear power channel measurement values, a second average value corresponding to the plurality of off-stack intermediate range nuclear power channel measurement values, a third average value corresponding to the plurality of off-stack range channel count rate measurement values, and a fourth average value of the primary coolant inlet temperature measurement value and the primary coolant outlet temperature measurement value corresponding to each NSSS;
in response to the second average being less than a first threshold, a trip depth is obtained.
10. The apparatus of claim 9, wherein the first determining module is specifically configured to:
and determining that the operation mode of the NSSS is an operation mode one in response to the first average value being greater than or equal to a second threshold value.
11. The apparatus of claim 9, wherein the first determining module is specifically configured to:
determining that the NSSS is in a second operating mode in response to the second average value being greater than a first threshold and less than a second threshold;
or,
determining that the operation mode of the NSSS is an operation mode two in response to the third average value being greater than a third threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode two in response to the second average value being smaller than the first threshold value and the trip depth being smaller than a fourth threshold value.
12. The apparatus of claim 9, wherein the first determining module is specifically configured to:
determining that the operation mode of the NSSS is an operation mode three in response to the third average value being smaller than a third threshold value and the fourth average value being greater than or equal to a fifth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode three in response to the second average value being smaller than a first threshold value, the fourth average value being greater than or equal to a fifth threshold value, and the trip depth being greater than a fourth threshold value.
13. The apparatus of claim 9, wherein the first determining module is specifically configured to:
determining that the operation mode of the NSSS is an operation mode four in response to the third average value being less than a third threshold value and the fourth average value being greater than or equal to a sixth threshold value and less than a fifth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode four in response to the second average value being less than a first threshold value, the fourth average value being greater than or equal to a sixth threshold value and less than a fifth threshold value, and the trip depth being greater than a fourth threshold value.
14. The apparatus of claim 9, wherein the first determining module is specifically configured to:
determining that the operation mode of the NSSS is an operation mode five in response to the third average value being less than a third threshold value and the fourth average value being less than a sixth threshold value;
or,
and determining that the operation mode of the NSSS is an operation mode five in response to the second average value being less than a first threshold value, the fourth average value being less than a sixth threshold value, and the trip depth being greater than a fourth threshold value.
15. An electronic device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor executes the computer program to perform the method for determining the operating status of the high temperature gas cooled reactor assembly according to any one of claims 1 to 7.
16. A computer-readable storage medium, storing a computer program, wherein the computer program, when executed by a processor, implements the method for determining the operating state of a high temperature gas cooled reactor train according to any one of claims 1 to 7.
17. A computer program product, comprising a computer program which, when executed by a processor, implements a method for determining an operating state of a high temperature gas cooled reactor assembly according to any one of claims 1 to 7.
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CN117476254B (en) * 2023-09-27 2024-06-04 华能核能技术研究院有限公司 Method and system for stopping modular high-temperature gas cooled reactor unit

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