CN114496319B - 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

Info

Publication number
CN114496319B
CN114496319B CN202111491024.8A CN202111491024A CN114496319B CN 114496319 B CN114496319 B CN 114496319B CN 202111491024 A CN202111491024 A CN 202111491024A CN 114496319 B CN114496319 B CN 114496319B
Authority
CN
China
Prior art keywords
operation mode
nsss
determining
threshold value
average value
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN202111491024.8A
Other languages
Chinese (zh)
Other versions
CN114496319A (en
Inventor
张晓斌
张冀兰
杨加东
洪伟
刘华
柯海鹏
郭云
蒋勇
魏文斌
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Huaneng Nuclear Energy Technology Research Institute Co Ltd
Original Assignee
Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Huaneng Nuclear Energy Technology Research Institute Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Huaneng Shandong Shidaobay Nuclear Power Co Ltd, Huaneng Nuclear Energy Technology Research Institute Co Ltd filed Critical Huaneng Shandong Shidaobay Nuclear Power Co Ltd
Priority to CN202111491024.8A priority Critical patent/CN114496319B/en
Publication of CN114496319A publication Critical patent/CN114496319A/en
Application granted granted Critical
Publication of CN114496319B publication Critical patent/CN114496319B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • 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

Abstract

The disclosure provides a method and a device for determining the running state of a high-temperature gas cooled reactor unit, and relates to the technical field of nuclear reactor engineering. Comprising 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 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; and then determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS. Therefore, the operation state of the high-temperature gas cooled reactor unit is determined by determining the corresponding working mode of each NSSS module, so that the operation state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call the operation rules in different states according to the current operation state of the high-temperature gas cooled reactor unit; loopholes in the technical specification execution process under different running states are avoided, and the nuclear safety supervision level is improved.

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 an operating state of a high-temperature gas cooled reactor unit.
Background
The modular high-temperature gas cooled reactor adopts a structural mode that two nuclear steam supply systems (Nuclear Steam Supply System, NSSS) are connected with a steam turbine generator unit in a running and power generation mode. During operation, one or both NSSS modules supply steam to the motor unit and do work, and the turbine drives the generator unit to generate electricity.
However, each NSSS module has multiple operation modes, and the operation modes of the two NSSS modules are combined, so that the operation state of the high-temperature gas cooled reactor unit becomes more complex, and it is difficult for a worker to determine the operation state of the high-temperature gas cooled reactor unit and call an operation procedure according to different operation states. Therefore, how to accurately determine the corresponding working mode of each NSSS module, and further determine the operation state of the high-temperature gas cooled reactor unit, is a technical problem to be solved.
Disclosure of Invention
The present disclosure aims to solve, at least to some extent, one of the technical problems in the related art.
An embodiment of a first aspect of the present disclosure provides a method for determining an operating state of a high temperature gas cooled reactor unit, including:
Acquiring a plurality of out-of-pile power range nuclear power channel measurement values, a plurality of out-of-pile intermediate range nuclear power channel measurement values, a plurality of out-of-pile 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 a high-temperature gas cooled reactor;
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 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;
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:
acquiring a first average value corresponding to the plurality of out-of-stack power range nuclear power channel measurement values, a second average value corresponding to the plurality of out-of-stack intermediate range nuclear power channel measurement values, a third average value corresponding to the plurality of out-of-stack range channel count rate measurement values, and a fourth average value of the main coolant inlet temperature measurement value and the main coolant outlet temperature measurement value corresponding to each NSSS;
And acquiring the shutdown depth in response to the second average value being smaller than a first threshold value.
Optionally, the determining the operation mode of each NSSS includes:
and determining that the running mode of the NSSS is a running mode I 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 mode of operation in response to the second average value being greater than a first threshold value and less than a second threshold value;
or alternatively, the process may be performed,
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 alternatively, the process may be performed,
and determining that the operation mode of the NSSS is an operation mode II in response to the second average value being smaller than a first threshold value and the shutdown 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 III 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 alternatively, the process may be performed,
and determining that the NSSS operation mode is an operation mode III in response to the second average value being smaller than a first threshold value, the fourth average value being larger than or equal to a fifth threshold value, and the shutdown depth being larger 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 IV in response to the third average value being smaller than a third threshold value, the fourth average value being greater than or equal to a sixth threshold value and smaller than a fifth threshold value;
or alternatively, the process may be performed,
and determining that the operation mode of the NSSS is an operation mode four 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 sixth threshold value and smaller than a fifth threshold value, and the shutdown 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 alternatively, the process may be performed,
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 shutdown depth being greater than a fourth threshold value.
An embodiment of a second aspect of the present disclosure provides a device for determining an operation state of a high temperature gas cooled reactor unit, including:
the first acquisition module is used for acquiring a plurality of out-of-pile power range nuclear power channel measurement values, a plurality of out-of-pile middle range nuclear power channel measurement values, a plurality of out-of-pile 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, configured to determine 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 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;
and the second determining module is used for determining the operating state of the high-temperature gas cooled reactor unit according to the operating mode of each NSSS.
Optionally, the method further comprises a second acquisition module, specifically configured to:
acquiring a first average value corresponding to the plurality of out-of-stack power range nuclear power channel measurement values, a second average value corresponding to the plurality of out-of-stack intermediate range nuclear power channel measurement values, a third average value corresponding to the plurality of out-of-stack range channel count rate measurement values, and a fourth average value of the main coolant inlet temperature measurement value and the main coolant outlet temperature measurement value corresponding to each NSSS;
and acquiring the shutdown depth in response to the second average value being smaller than a first threshold value.
Optionally, the first determining module is specifically configured to:
and determining that the running mode of the NSSS is a running mode I 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 mode of operation in response to the second average value being greater than a first threshold value and less than a second threshold value;
or alternatively, the process may be performed,
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 alternatively, the process may be performed,
and determining that the operation mode of the NSSS is an operation mode II in response to the second average value being smaller than a first threshold value and the shutdown 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 III 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 alternatively, the process may be performed,
and determining that the NSSS operation mode is an operation mode III in response to the second average value being smaller than a first threshold value, the fourth average value being larger than or equal to a fifth threshold value, and the shutdown depth being larger 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 IV in response to the third average value being smaller than a third threshold value, the fourth average value being greater than or equal to a sixth threshold value and smaller than a fifth threshold value;
Or alternatively, the process may be performed,
and determining that the operation mode of the NSSS is an operation mode four 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 sixth threshold value and smaller than a fifth threshold value, and the shutdown 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 alternatively, the process may be performed,
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 shutdown 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 in the memory and capable of running on the processor, wherein the processor realizes 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 when the processor executes the program.
An embodiment of a fourth aspect of the present disclosure provides a computer readable storage medium storing a computer program, where the computer program is executed by a processor to implement a method for determining an operation state of a high temperature gas cooled reactor unit according to the embodiment of the first aspect of the present disclosure.
An embodiment of a fifth aspect of the present disclosure proposes 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 unit as proposed by an 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 may be determined 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 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; and then determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS. Therefore, the operation state of the high-temperature gas cooled reactor unit is determined by determining the corresponding working mode of each NSSS module, so that the operation state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call the operation rules in different states according to the current operation state of the high-temperature gas cooled reactor unit; loopholes in the technical specification execution process under different running states are avoided, and the nuclear safety supervision level is improved.
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 foregoing 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, in which:
FIG. 1 is a schematic flow chart of a method for determining an operating state of a high temperature gas cooled reactor unit according to an embodiment of the disclosure;
FIG. 2 is a schematic flow chart of a method for determining an operating state of a high temperature gas cooled reactor unit according to another embodiment of the disclosure;
FIG. 2a is a flow chart 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 flow chart 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 flow chart 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 flow chart 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 flow chart 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 a device 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
Embodiments of the present disclosure are described in detail below, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to like or similar elements or elements having like or similar functions throughout. The embodiments described below by referring to the drawings are exemplary and intended for the purpose of explaining the present disclosure and are not to be construed as limiting the present disclosure.
The following describes a method and a device for determining an operation state of a high-temperature gas cooled reactor unit according to an embodiment of the present disclosure with reference to the accompanying drawings.
Fig. 1 is a flow chart of a method for determining an operation state of a high-temperature gas cooled reactor unit according to an embodiment of the disclosure.
The embodiment of the disclosure is illustrated by the method for determining the operation state of the high-temperature gas-cooled reactor unit being configured in the device for determining the operation state of the high-temperature gas-cooled reactor unit, and the device for determining the operation state of the high-temperature gas-cooled reactor unit can be applied to any electronic equipment, so that the electronic equipment can execute the function of determining the operation state of the high-temperature gas-cooled reactor unit.
The electronic device may be a personal computer (Personal Computer, abbreviated as PC), a cloud device, a mobile device, etc., and the mobile device may be a mobile phone, a tablet computer, a personal digital assistant, a wearable device, a vehicle-mounted device, etc. with various hardware devices including an operating system, a touch screen, and/or a display screen.
As shown in fig. 1, the method for determining the operation state of the high temperature gas cooled reactor unit may include the following steps:
step 101, obtaining a plurality of out-of-pile power range nuclear power channel measurement values, a plurality of out-of-pile intermediate range nuclear power channel measurement values, a plurality of out-of-pile 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 in the high-temperature gas cooled reactor.
It can be understood that the dual NSSS high temperature gas cooled reactor includes two NSSS, when determining the operation state of the high temperature gas cooled reactor unit, the operation mode corresponding to each NSSS needs to be determined first.
Each NSSS includes 4 off-stack power range channels, 2 off-stack mid-range channels, and 2 off-stack range channels. Thus, in embodiments of the present disclosure, 4 out-of-stack power-range nuclear power channel measurements, 2 out-of-stack mid-range nuclear power channel measurements, 2 out-of-stack range channel count rate measurements may be obtained. The present disclosure is not limited in this regard.
Wherein the primary coolant inlet temperature measurement may be an average of temperatures within the plurality of primary coolant inlet channels; the primary coolant outlet temperature measurement may be an average of temperatures within the plurality of primary coolant outlet channels. The present disclosure is not limited in this regard.
Step 102, 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 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.
Wherein, each NSSS may have 5 operation modes, respectively: operation mode one, power operation, operation mode two, starting, operation mode three, stack shutdown, operation mode four, cold stack shutdown, operation mode five, and maintenance stack shutdown. The present disclosure is not limited in this regard.
Optionally, after obtaining a plurality of out-of-stack power range nuclear power channel measurement values, a plurality of out-of-stack mid-range nuclear power channel measurement values, a plurality of out-of-stack 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, the obtained out-of-stack power range nuclear power channel measurement values, the obtained out-of-stack mid-range nuclear power channel measurement values, the obtained out-of-stack external range channel count rate measurement values, the obtained main coolant inlet temperature measurement value, and the obtained main coolant outlet temperature measurement value may be input into a distributed control system (Distributed Control System, DCS) system, and the corresponding operation mode of each NSSS may be determined through logic.
And step 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 comprises two NSSS, each NSSS has 5 operation modes, and then the high temperature gas cooled reactor unit has 25 operation states. The operation state of the high-temperature gas cooled reactor unit can be shown in table 1.
TABLE 1
Figure BDA0003399358680000071
The nsss#1 is the 1 st NSSS in the high-temperature gas cooled reactor, the nsss#2 is the 2 nd NSSS in the high-temperature gas cooled reactor, and 1#4,2#5 indicate that nsss#1 is the operation mode 4 and nsss#2 is the operation mode 5.
It can be understood that each element in table 1, each corresponding relationship, exists independently; these elements, correspondences are illustratively listed in the same table, but do not represent that all elements in the table, correspondences must exist simultaneously in accordance with what is shown in table 1. Wherein the value of each element and each correspondence is independent of any other element value or correspondence in table 1. It will be appreciated by those skilled in the art that the values of each element and each corresponding relationship in table 1 are each an independent embodiment.
Optionally, after the operation state of the high-temperature gas cooled reactor unit is determined according to the operation mode of each NSSS, the operation state of the high-temperature gas cooled reactor unit may be displayed in a main control room large screen for visualization. Therefore, operators can call the operation rules in different states according to the current operation state of the high-temperature gas cooled reactor unit; under the condition of emergency, making correct response according to the current running state of the high-temperature gas cooled reactor unit; loopholes in the technical specification execution process under different running states are avoided, and the nuclear safety supervision level is improved.
It should be noted that, in the embodiment of the present disclosure, the principle of determining the operation state of the high temperature gas cooled reactor unit according to the measurement parameters corresponding to each NSSS is also applicable to other types of nuclear reactors. Such as pressurized water reactors, boiling water reactors, and the like. The state combinations of NSSS and conventional islands can be considered simultaneously, using the same principle, as desired. The present disclosure is not limited in this regard.
In the embodiment of the disclosure, the operation mode of each NSSS may be determined 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 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; and then determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS. Therefore, the operation state of the high-temperature gas cooled reactor unit is determined by determining the corresponding working mode of each NSSS module, so that the operation state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call the operation rules in different states according to the current operation state of the high-temperature gas cooled reactor unit; loopholes in the technical specification execution process under different running states are avoided, and the nuclear safety supervision level is improved.
Fig. 2 is a flow chart of a method for determining an operation state of a high-temperature gas cooled reactor unit according to an embodiment of the disclosure, as shown in fig. 2, the method for determining an operation state of a high-temperature gas cooled reactor unit may include the following steps:
step 201, obtaining a plurality of out-of-pile power range nuclear power channel measurement values, a plurality of out-of-pile intermediate range nuclear power channel measurement values, a plurality of out-of-pile 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.
The specific implementation manner of step 201 may refer to the detailed descriptions in other embodiments in the disclosure, and will not be described in detail herein.
Step 202, determining 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 count 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.
For example, if each NSSS corresponds to 4 out-of-stack power range core power channel measurements, P is respectively 1 、P 2 、P 3 、P 4 Then the first average value is
Figure BDA0003399358680000081
If each NSSS corresponds to 2 nuclear power channel measurement values with extra-stack power range, the nuclear power channel measurement values are P respectively 5 、P 6 Then the second average value is +.>
Figure BDA0003399358680000082
If each NSSS corresponds to 2 measurement values of the counting rate of the external source range channel, the measurement values are S respectively 1 、S 2 Then the third average value is +.>
Figure BDA0003399358680000083
If the primary coolant inlet temperature measurement is T 1 The main coolant outlet temperature measurement is T 2 Fourth stepAverage value of->
Figure BDA0003399358680000084
And 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 appreciated that in the case where the second average value corresponding to the measured values of the plurality of out-of-stack mid-range nuclear power channels is smaller than the first threshold, the operation mode corresponding to NSSS cannot be accurately determined only by using the measured value corresponding to the nuclear power. Therefore, when the second average value is smaller than the first threshold value, the physical quantity with reflectivity is introduced, the corresponding working mode of NSSS is comprehensively judged, and the accuracy of NSSS working mode judgment is improved.
The shutdown depth may be, among other things, the negative reactivity achieved by the reactor when all control poisons are thrown 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 value, determining that the operation mode of the NSSS is the operation mode one.
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 flow chart 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 core power channel measurements P are measured at 4 out-of-stack power ranges 1 、P 2 、P 3 、P 4 Corresponding first average value P avg1 Greater than or equal to the second threshold value 30% P Rated for In the case of (a), determining the NSSS operation mode as operationRow pattern one.
Optionally, determining that NSSS is in the second operation mode if the second average value is greater than the first threshold value and less than the second threshold value; or if the third average value is greater than the third threshold value, determining that the running mode of the NSSS is a running mode two; or if the second average value is smaller than the first threshold value and the shutdown depth is smaller than the fourth threshold value, determining that the operation mode of the NSSS is an operation mode two.
The third threshold value can be determined according to an engineering experience value, and the engineering experience value can be determined according to a current starting experience value of the high-temperature gas cooled reactor. For example, the third threshold may be 20cps, which is not limited by the present 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 in this disclosure.
Fig. 2b is a flow chart 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, a second average value P corresponding to the core power channel measurement at the mid-span outside 2 stacks avg2 Greater than a first threshold of 0.01% P Rated for And less than 30% P of the second threshold Rated for In the case of (2), determining that NSSS is in the second operation mode; alternatively, at a third average value S avg3 If the second threshold value is larger than 20cps, determining that the operation mode of the NSSS is an operation mode II; alternatively, at the second average value P avg2 Less than a first threshold of 0.01% P Rated for And under the condition that the shutdown depth rho is smaller than the fourth threshold value 1000pcm, determining the operation mode of the NSSS to be the operation mode two.
Optionally, determining that the operation mode of the NSSS is the operation mode three when the third average value is smaller than the third threshold value and the fourth average value is greater than or equal to the fifth threshold value; or when 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, determining that the operation mode of the NSSS is an operation mode III.
Wherein the fifth threshold is a threshold corresponding to an average of the main coolant inlet temperature measurement value T1 and the main coolant outlet temperature measurement value T2. For example, the fifth threshold may be 150 ℃, which is not limited by the present disclosure.
Fig. 2c is a flow chart 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 a third average value S avg3 Less than a third threshold value of 20cps, and a fourth average value T avg4 Under the condition that the temperature is greater than or equal to a fifth threshold value of 150 ℃, determining the operation mode of NSSS to be an operation mode III; alternatively, at the second average value P avg2 Less than a first threshold of 0.01% P Rated for Fourth average value T avg4 And determining the operation mode of the NSSS to be an operation mode III under the conditions that the temperature is equal to or higher than a fifth threshold value 150 ℃ and the shutdown depth rho is equal to or higher than a fourth threshold value 1000 pcm.
Optionally, determining that the operation mode of the NSSS is the operation mode four when the third average value is smaller than the third threshold value, the fourth average value is greater than or equal to the sixth threshold value, and smaller than the fifth threshold value; or when the second average value is smaller than the first threshold value, the fourth average value is larger than or equal to the sixth threshold value and smaller than the fifth threshold value, and the shutdown depth is larger than the fourth threshold value, determining that the operation mode of the NSSS is the operation mode four.
Wherein the fifth threshold is a threshold corresponding to an average of the main coolant inlet temperature measurement value T1 and the main coolant outlet temperature measurement value T2. For example, the sixth threshold may be 50 ℃, which is not limited by the present disclosure.
Fig. 2d is a flow chart 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 a third average value S avg3 Less than a third threshold of 20cps, a fourth average value T avg4 Determining that the operation mode of the NSSS is an operation mode IV under the condition that the temperature is greater than or equal to a sixth threshold value of 50 ℃ and is less than a fifth threshold value of 150 ℃; alternatively, at the second average value P avg2 Less than a first threshold of 0.01% P Rated for Fourth average value T avg4 And determining the operation mode of the NSSS to be an operation mode four under the conditions that the temperature is greater than or equal to a sixth threshold value of 50 ℃ and less than a fifth threshold value of 150 ℃ and the shutdown depth rho is greater than a fourth threshold value of 1000 pcm.
Optionally, determining that the operation mode of the NSSS is the operation mode five if the third average value is smaller than the third threshold value and the fourth average value is smaller than the sixth threshold value; or determining that the operation mode of the NSSS is the operation mode five when 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 flow chart 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 a third average value S avg3 Less than a third threshold of 20cps, a fourth average value T avg4 Under the condition that the temperature is lower than a sixth threshold value of 50 ℃, determining the operation mode of NSSS to be an operation mode five; alternatively, at the second average value P avg2 Less than a first threshold of 0.01% P Rated for Fourth average value T avg4 And determining the operation mode of the NSSS to be an operation mode five under the condition that the temperature is lower than a sixth threshold value 50 ℃ and the shutdown depth rho is higher than a fourth threshold value 1000 pcm.
And 205, determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS.
The specific implementation manner of step 205 may refer to the detailed description of other embodiments in the disclosure, and will not be described in detail herein.
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 intermediate range nuclear power channel measurement values, a third average value corresponding to a plurality of out-of-stack source range channel count rate measurement values, a fourth average value and a shutdown depth of a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value, and then an operation state of a high-temperature gas cooled reactor unit is determined according to the operation mode of each NSSS. Therefore, the accuracy of judging the NSSS running mode is further improved, the running state accuracy of the high-temperature gas cooled reactor unit is further improved, and an operator can call running rules in different states according to the current running state of the high-temperature gas cooled reactor unit; moreover, loopholes in the technical specification execution process under different running states are avoided, and the nuclear safety supervision level is improved.
In order to achieve the above embodiment, the present disclosure further provides a device for determining an operation state of a high-temperature gas cooled reactor unit.
Fig. 3 is a schematic structural diagram of a device for determining an operating state of a high-temperature gas cooled reactor unit according to an embodiment of the disclosure. As shown in fig. 3, the apparatus 300 for determining an operation state of a high temperature gas cooled reactor unit may include: a first acquisition module 310, a first determination module 320, a second determination module 330.
The first obtaining module 310 is configured to obtain a plurality of out-of-pile power range nuclear power channel measurement values, a plurality of out-of-pile intermediate range nuclear power channel measurement values, a plurality of out-of-pile 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, configured to determine 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 mid-range nuclear power channel measurement values, a plurality of out-of-stack 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;
and a second determining module 330, configured to determine an operation state of the high temperature gas cooled reactor unit according to an operation mode of each NSSS.
Optionally, the method further comprises a second acquisition module, specifically configured to:
acquiring 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 source range channel count 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;
and acquiring the shutdown depth in response to the second average being less than the first threshold.
Optionally, the first determining module 320 is specifically configured to:
and determining the operation mode of the NSSS to be the operation mode I in response to the first average value being greater than or equal to the second threshold.
Optionally, the first determining module 320 is specifically configured to:
responsive to the second average value being greater than the first threshold value and less than the second threshold value, determining that NSSS is operating mode two;
or alternatively, the process may be performed,
determining the operation mode of the NSSS to be the operation mode II in response to the third average value being greater than a third threshold value;
or alternatively, the process may be performed,
and determining that the operation mode of the NSSS is an operation mode two in response to the second average value being less than the first threshold value and the shutdown depth being less 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 III 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 alternatively, the process may be performed,
and determining that the operation mode of the NSSS is an operation mode III in response to the second average value being smaller than the first threshold value, the fourth average value being greater than or equal to 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 NSSS operation mode is an operation mode IV 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 alternatively, the process may be performed,
and determining that the NSSS operating mode is an operating mode four 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 less than the third threshold value and the fourth average value being less than the sixth threshold value;
or alternatively, the process may be performed,
and determining that the operation mode of the NSSS is an operation mode five in response to the second average value being less than the first threshold value, the fourth average value being less than the sixth threshold value, and the shutdown depth being greater than the fourth threshold value.
The functions and specific implementation principles of the foregoing modules in the embodiments of the present disclosure may refer to the foregoing method embodiments, and are not repeated herein.
The device for determining the operation state of the high-temperature gas cooled reactor unit in the embodiment of the disclosure can determine the operation mode of each NSSS according to a plurality of out-of-pile power range nuclear power channel measurement values, a plurality of out-of-pile intermediate range nuclear power channel measurement values, a plurality of out-of-pile 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; and then determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS. Therefore, the operation state of the high-temperature gas cooled reactor unit is determined by determining the corresponding working mode of each NSSS module, so that the operation state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call the operation rules in different states according to the current operation state of the high-temperature gas cooled reactor unit; loopholes in the technical specification execution process under different running states are avoided, and the nuclear safety supervision level is improved.
In order to achieve the above embodiments, the present disclosure further proposes an electronic device including: the method for determining the operating state of the high-temperature gas cooled reactor unit according to the embodiment of the disclosure is realized when the processor executes the program.
In order to implement the foregoing embodiments, the present disclosure further proposes a computer-readable storage medium storing a computer program that, when executed by a processor, implements a method for determining an operating state of a high-temperature gas cooled reactor unit as proposed in the foregoing embodiments of the present disclosure.
In order to implement the foregoing embodiments, the disclosure further proposes a computer program product, including a computer program, which, when executed by a processor, implements a method for determining an operating state of a high temperature gas cooled reactor unit as proposed in the foregoing embodiments of the 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 merely an example and should not be construed to limit the functionality and scope of use of embodiments of the present disclosure in any way.
As shown in fig. 4, the electronic device 12 is in the form of a general purpose computing device. Components of computer device 12 may include, but are not limited to: one or more processors or processing units 16, a system memory 28, a bus 18 that connects the various system components, including the system memory 28 and the processing units 16.
Bus 18 represents one or more of several types of bus structures, including a memory bus or memory controller, a peripheral bus, an accelerated graphics port, a processor, and a local bus using any of a variety of bus architectures. By way of example, and not limitation, such architectures include industry Standard architecture (Industry Standard Architecture; hereinafter ISA) bus, micro channel architecture (Micro Channel Architecture; hereinafter MAC) bus, enhanced ISA bus, video electronics standards Association (Video Electronics Standards Association; hereinafter VESA) local bus, and peripheral component interconnect (Peripheral Component Interconnection; hereinafter PCI) bus.
Computer device 12 typically includes a variety of computer system readable media. Such media can 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 (Random Access Memory; hereinafter: RAM) 30 and/or cache memory 32. The 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 or write to non-removable, nonvolatile magnetic media (not shown in FIG. 4, commonly referred to as a "hard disk drive"). Although not shown in fig. 4, a magnetic disk drive for reading from and writing to a removable non-volatile magnetic disk (e.g., a "floppy disk"), and an optical disk drive for reading from or writing to a removable non-volatile optical disk (e.g., a compact disk read only memory (Compact Disc Read Only Memory; hereinafter CD-ROM), digital versatile read only optical disk (Digital Video Disc Read Only Memory; hereinafter DVD-ROM), or other optical media) may be provided. In such cases, each drive may be coupled to bus 18 through one or more data medium interfaces. Memory 28 may include at least one program product having a set (e.g., at least one) of program modules configured to carry out the functions of the various embodiments of the disclosure.
A program/utility 40 having a set (at least one) of program modules 42 may be stored in, for example, 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 or some combination of which may include an implementation of a network environment. Program modules 42 generally perform the functions and/or methods in the embodiments described in this disclosure.
The computer device 12 may also communicate with one or more external devices 14 (e.g., keyboard, pointing device, display 24, etc.), one or more devices that enable a user to interact with the computer device 12, and/or any devices (e.g., network card, modem, etc.) that enable the computer device 12 to communicate with one or more other computing devices. Such communication may occur through an input/output (I/O) interface 22. Moreover, the computer device 12 may also communicate with one or more networks such as a local area network (Local Area Network; hereinafter LAN), a wide area network (Wide Area Network; hereinafter WAN) and/or a public network such as the Internet via the network adapter 20. As shown, network adapter 20 communicates with other modules of computer device 12 via bus 18. It should be appreciated that although not shown, other hardware and/or software modules may be used in connection with computer device 12, including, but not limited to: microcode, device drivers, redundant processing units, external disk drive arrays, RAID systems, tape drives, data backup storage systems, and the like.
The processing unit 16 executes various functional applications and data processing by running programs stored in the system memory 28, for example, implementing the methods mentioned in the foregoing embodiments.
According to the technical scheme, the operation mode of each NSSS can be determined according to a plurality of out-of-pile power range nuclear power channel measurement values, a plurality of out-of-pile intermediate range nuclear power channel measurement values, a plurality of out-of-pile range channel count rate measurement values, a main coolant inlet temperature measurement value and a main coolant outlet temperature measurement value which correspond 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 operation state of the high-temperature gas cooled reactor unit is determined by determining the corresponding working mode of each NSSS module, so that the operation state of the high-temperature gas cooled reactor unit can be accurately determined, and an operator can call the operation rules in different states according to the current operation state of the high-temperature gas cooled reactor unit; loopholes in the technical specification execution process under different running states are avoided, and the nuclear safety supervision level is improved.
In the description of the present specification, a description referring to terms "one embodiment," "some embodiments," "examples," "specific examples," or "some examples," etc., means 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, schematic representations of the above terms are not necessarily directed 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, the different embodiments or examples described in this specification and the features of the different embodiments or examples may be combined and combined by those skilled in the art without contradiction.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In the description of the present disclosure, the meaning of "a plurality" is at least two, such as two, three, etc., unless explicitly specified 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 specific logical functions or steps of the process, and additional 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.
Logic and/or steps represented in the flowcharts or otherwise described herein, e.g., a ordered listing of executable instructions for implementing 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). In addition, the computer readable medium may even be paper or other suitable medium on which the program is printed, as the program may 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-described embodiments, the various steps or methods may be implemented in software or firmware stored in a memory and executed by a suitable instruction execution system. As with the other embodiments, if implemented in hardware, may be implemented using any one or combination of the following techniques, as is well known in the art: discrete logic circuits having logic gates for implementing logic functions on data signals, application specific integrated circuits having suitable combinational logic gates, programmable Gate Arrays (PGAs), field Programmable Gate Arrays (FPGAs), and the like.
Those of ordinary skill in the art will appreciate that all or a portion of the steps carried out in the method of the above-described embodiments may be implemented by a program to instruct related hardware, where the program may be stored in a computer readable storage medium, and where the program, when executed, includes one or a combination of the steps of the method embodiments.
Furthermore, each functional unit in the embodiments of the present disclosure may be integrated in one processing module, or each unit may exist alone physically, or two or more units may be integrated in one module. The integrated modules may be implemented in hardware or in software functional modules. The integrated modules may also be stored in a computer readable storage medium if implemented in the form of software functional modules and sold or used as a stand-alone product.
The above-mentioned storage medium may be a read-only memory, a magnetic disk or an optical disk, or the like. Although embodiments of the present disclosure have been shown and described above, it will be understood that the above embodiments are illustrative and not to be construed as limiting the present disclosure, and that variations, modifications, alternatives, and variations may be made to the above embodiments by one of ordinary skill in the art within the scope of the present disclosure.

Claims (5)

1. The method for determining the operation state of the high-temperature gas cooled reactor unit is characterized by comprising the following steps of:
acquiring a plurality of out-of-pile power range nuclear power channel measurement values, a plurality of out-of-pile intermediate range nuclear power channel measurement values, a plurality of out-of-pile 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 a high-temperature gas cooled reactor;
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 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;
Determining the operation state of the high-temperature gas-cooled reactor unit according to the operation mode of each NSSS;
before said determining the operation mode of each NSSS, further comprising:
acquiring a first average value corresponding to the plurality of out-of-stack power range nuclear power channel measurement values, a second average value corresponding to the plurality of out-of-stack intermediate range nuclear power channel measurement values, a third average value corresponding to the plurality of out-of-stack range channel count rate measurement values, and a fourth average value of the main coolant inlet temperature measurement value and the main coolant outlet temperature measurement value corresponding to each NSSS;
acquiring the shutdown depth in response to the second average value being less than a first threshold value;
the determining the operation mode of each NSSS includes:
determining that the operation mode of the NSSS is an operation mode I in response to the first average value being greater than or equal to a second threshold value;
the determining the operation mode of each NSSS includes:
determining that the NSSS is in a second mode of operation in response to the second average value being greater than a first threshold value and less than a second threshold value;
or alternatively, the process may be performed,
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 alternatively, the process may be performed,
determining that the operation mode of the NSSS is an operation mode two in response to the second average value being smaller than a first threshold value and the shutdown depth being smaller than a fourth threshold value;
the determining the operation mode of each NSSS includes:
determining that the operation mode of the NSSS is an operation mode III 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 alternatively, the process may be performed,
determining that the operation mode of the NSSS is an operation mode III 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 fifth threshold value, and the shutdown depth being greater than a fourth threshold value;
the determining the operation mode of each NSSS includes:
determining that the operation mode of the NSSS is an operation mode IV in response to the third average value being smaller than a third threshold value, the fourth average value being greater than or equal to a sixth threshold value and smaller than a fifth threshold value;
or alternatively, the process may be performed,
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 shutdown depth being greater than a fourth threshold value;
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 alternatively, the process may be performed,
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 shutdown depth being greater than a fourth threshold value.
2. The device for determining the operation state of the high-temperature gas cooled reactor unit is characterized by comprising the following components:
the first acquisition module is used for acquiring a plurality of out-of-pile power range nuclear power channel measurement values, a plurality of out-of-pile middle range nuclear power channel measurement values, a plurality of out-of-pile 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, configured to determine 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 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;
The second determining module is used for determining the operation state of the high-temperature gas cooled reactor unit according to the operation mode of each NSSS;
the device further comprises a second acquisition module, specifically configured to:
acquiring a first average value corresponding to the plurality of out-of-stack power range nuclear power channel measurement values, a second average value corresponding to the plurality of out-of-stack intermediate range nuclear power channel measurement values, a third average value corresponding to the plurality of out-of-stack range channel count rate measurement values, and a fourth average value of the main coolant inlet temperature measurement value and the main coolant outlet temperature measurement value corresponding to each NSSS;
acquiring the shutdown depth in response to the second average value being less than a first threshold value;
the first determining module is specifically configured to:
determining that the operation mode of the NSSS is an operation mode I in response to the first average value being greater than or equal to a second threshold value;
the first determining module is specifically configured to:
determining that the NSSS is in a second mode of operation in response to the second average value being greater than a first threshold value and less than a second threshold value;
or alternatively, the process may be performed,
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 alternatively, the process may be performed,
determining that the operation mode of the NSSS is an operation mode two in response to the second average value being smaller than a first threshold value and the shutdown depth being smaller than a fourth threshold value;
the first determining module is specifically configured to:
determining that the operation mode of the NSSS is an operation mode III 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 alternatively, the process may be performed,
determining that the operation mode of the NSSS is an operation mode III 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 fifth threshold value, and the shutdown depth being greater than a fourth threshold value;
the first determining module is specifically configured to:
determining that the operation mode of the NSSS is an operation mode IV in response to the third average value being smaller than a third threshold value, the fourth average value being greater than or equal to a sixth threshold value and smaller than a fifth threshold value;
or alternatively, the process may be performed,
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 shutdown depth being greater than a fourth threshold value;
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 alternatively, the process may be performed,
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 shutdown depth being greater than a fourth threshold value.
3. An electronic device comprising a memory, a processor and a computer program stored on the memory and operable on the processor, wherein the processor, when executing the program, implements the method for determining the operating state of a high temperature gas cooled reactor unit according to claim 1.
4. A computer-readable storage medium storing a computer program which, when executed by a processor, implements the method for determining the operating state of a high temperature gas cooled reactor unit according to claim 1.
5. A computer program product comprising a computer program which, when executed by a processor, implements the method of determining the operating condition of a high temperature gas cooled reactor unit as claimed in claim 1.
CN202111491024.8A 2021-12-08 2021-12-08 Method and device for determining running state of high-temperature gas cooled reactor unit Active CN114496319B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202111491024.8A CN114496319B (en) 2021-12-08 2021-12-08 Method and device for determining running state of high-temperature gas cooled reactor unit

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202111491024.8A CN114496319B (en) 2021-12-08 2021-12-08 Method and device for determining running state of high-temperature gas cooled reactor unit

Publications (2)

Publication Number Publication Date
CN114496319A CN114496319A (en) 2022-05-13
CN114496319B true CN114496319B (en) 2023-05-16

Family

ID=81492692

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202111491024.8A Active CN114496319B (en) 2021-12-08 2021-12-08 Method and device for determining running state of high-temperature gas cooled reactor unit

Country Status (1)

Country Link
CN (1) CN114496319B (en)

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109033904A (en) * 2018-07-11 2018-12-18 岭澳核电有限公司 The calibration of intermediate range protection definite value and verification method, system and terminal device

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6061413A (en) * 1996-03-18 2000-05-09 Westinghouse Electric Company Llc Nuclear steam supply temperature measurement system and method
CN101740153A (en) * 2009-12-01 2010-06-16 中国广东核电集团有限公司 Device and system for monitoring and displaying normal operating condition of unit of nuclear power plant
CN101714413B (en) * 2009-12-23 2012-07-25 清华大学 High-temperature gas cooled reactor steam generating system and method
CN102411997B (en) * 2011-10-25 2014-04-02 清华大学 Control method and system of high temperature gas cooled reactor power
CN110289114B (en) * 2019-06-10 2021-03-09 清华大学 High-temperature gas-cooled reactor power control method and system and high-temperature gas-cooled reactor nuclear power station
CN113345613A (en) * 2021-05-26 2021-09-03 华能山东石岛湾核电有限公司 Monitoring control method and device for high-temperature gas cooled reactor main steam system

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109033904A (en) * 2018-07-11 2018-12-18 岭澳核电有限公司 The calibration of intermediate range protection definite value and verification method, system and terminal device

Also Published As

Publication number Publication date
CN114496319A (en) 2022-05-13

Similar Documents

Publication Publication Date Title
CN114496319B (en) Method and device for determining running state of high-temperature gas cooled reactor unit
CN109162856B (en) Method and system for monitoring state of hydroelectric generating set
CN109213108B (en) Nuclear power station operator operation auxiliary support system and method
CN109033904B (en) Calibration and verification method and system for middle range protection setting value and terminal equipment
CN113705972A (en) Load distribution method, device and storage medium
CN108255687A (en) Application program internal memory monitoring test method, device and the electronic equipment of terminal
CN109980789B (en) State detection method, device, equipment and medium of direct current control protection system
WO2023134263A1 (en) Method and apparatus for testing function of nuclear steam supply system, and computer device and medium
CN115081578A (en) System, method and device for processing fuel ball counter signal and electronic equipment
CN115185313A (en) Trend tracking early warning method and device for bearing bush temperature of hydroelectric generating set
CN108983714B (en) Method and device for monitoring state of unit of million-kilowatt nuclear power station and terminal equipment
CN116014192A (en) Method, system and device for controlling air and hydrogen pressure in hydrogen fuel cell system
TWI756769B (en) Powering method and powering system for power over ethernet
CN108021478A (en) A kind of graphics processor robustness test method
CN110783007B (en) Reactor control room system
CN115295190A (en) Method and device for determining reactor power of high-temperature gas-cooled reactor nuclear power station
CN110716886B (en) Data processing method, device, storage medium and terminal
KR102127120B1 (en) Method for monitoring of nuclear power plant in transient state using signal classification
KR102139097B1 (en) Method for monitoring of nuclear power plant in transient state using signal classification based on group representative signal
CN116206791A (en) Method and device for controlling one-loop of pool type fast reactor, computer equipment and storage medium
CN109444709B (en) Wind turbine generator testing system design method based on virtual instrument technology
CN115359928A (en) High-temperature gas-cooled reactor shutdown depth determination method and device, electronic equipment and medium
JP5502509B2 (en) Core thermal limit value monitoring apparatus, core monitoring system, and core thermal limit value monitoring method
CN117747152A (en) Automatic loading and refueling control method and system for pebble-bed high-temperature gas cooled reactor
CN115312226A (en) Nuclear power equipment fault load shedding control method and device and storage medium

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant