CN113421674B - Method and device for calculating leakage rate of primary loop during high-temperature reactor cold test - Google Patents

Method and device for calculating leakage rate of primary loop during high-temperature reactor cold test Download PDF

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Publication number
CN113421674B
CN113421674B CN202110580316.2A CN202110580316A CN113421674B CN 113421674 B CN113421674 B CN 113421674B CN 202110580316 A CN202110580316 A CN 202110580316A CN 113421674 B CN113421674 B CN 113421674B
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temperature
calculating
primary circuit
loop
steam generator
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CN113421674A (en
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刘志明
姜峰
雷川
邢校萄
孙天宇
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Huaneng Shandong Shidaobay Nuclear Power Co Ltd
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Huaneng Shandong Shidaobay Nuclear Power Co Ltd
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • G21D3/002—Core design; core simulations; core optimisation
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/001—Mechanical simulators
    • 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
    • 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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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Examining Or Testing Airtightness (AREA)

Abstract

The disclosure provides a method and a device for calculating a loop leakage rate during a high-temperature reactor cold test. The method comprises the following steps: calculating the average temperature value of each component according to the acquired temperature value of each temperature measuring point of the loop; calculating the average temperature of the loop, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature value of each component; calculating the body pressure of the primary loop according to the pressure measuring point of the primary loop, the integral temperature of the reactor pressure vessel and the steam generator shell; calculating the mass of the gas in the primary circuit at a certain moment according to the average temperature of the primary circuit and the bulk pressure of the primary circuit; and calculating the leakage rate of the primary circuit according to the calculated mass of the gas of the primary circuit at different moments. The leakage rate of the loop during the cold test of the high-temperature reactor can be accurately measured, and the blank that the leakage rate of the loop cannot be measured in the prior art is filled.

Description

Method and device for calculating leakage rate of primary loop during cold test of high-temperature reactor
Technical Field
The disclosure belongs to the technical field of high-temperature reactors, and particularly relates to a method and a device for calculating a leakage rate of a primary circuit during a cold test period of a high-temperature reactor.
Background
The high temperature gas cooled reactor nuclear power station demonstration project is a world first reactor, a loop of the high temperature gas cooled reactor nuclear power station adopts compressed air and a small amount of helium as test media, a series of process tests of 10 pressure platforms are carried out in stages, and the strength and the tightness of a reactor loop system, equipment and auxiliary pipelines thereof under the pressure higher than the design pressure are mainly verified.
However, there is no way to calculate the leakage rate of the primary circuit during the high temperature stack cold test.
Disclosure of Invention
The present disclosure is directed to at least one of the technical problems of the prior art, and provides a method and an apparatus for calculating a leakage rate of a primary circuit during a cold test of a high temperature reactor.
In one aspect of the disclosure, a method for calculating a loop leakage rate during a cold test of a high-temperature reactor is provided, the method comprising:
calculating the average temperature value of each component according to the acquired temperature value of each temperature measuring point of the loop;
calculating the average temperature of the loop, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature value of each component;
calculating the body pressure of the primary loop according to the pressure measuring point of the primary loop, the integral temperature of the reactor pressure vessel and the steam generator shell;
calculating the mass of the gas of the primary circuit at a certain moment according to the average temperature of the primary circuit and the body pressure of the primary circuit;
and calculating the leakage rate of the primary circuit according to the calculated mass of the gas of the primary circuit at different moments.
In some embodiments, calculating an average temperature value for each component based on the collected temperature values for each temperature measurement point of the circuit comprises:
respectively comparing the temperature value of each temperature measuring point with a preset temperature threshold range, and rejecting the temperature measuring points which are not matched with the temperature threshold range;
and calculating the average temperature value of each part according to the temperature values of the rest temperature measuring points.
In some embodiments, calculating the average temperature of the loop, the bulk temperature of the reactor pressure vessel, and the bulk temperature of the steam generator shell based on the average temperature of each of the components comprises:
and calculating the average temperature of the primary circuit, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature of each component and the proportion of each component in the primary circuit.
In some embodiments, the fractional portion is a volumetric fractional portion.
In some embodiments, calculating the bulk pressure of the primary loop from the pressure measurement of the primary loop, the bulk temperature of the reactor pressure vessel and the steam generator shell comprises:
and calculating the body pressure of the primary circuit according to the pressure measuring point of the primary circuit, the overall temperature of the reactor pressure vessel and the steam generator shell and the proportion of the reactor pressure vessel and the steam generator shell in the primary circuit.
In some embodiments, the fractional portion is a volume fractional portion.
In some embodiments, the method further comprises:
and displaying the calculated leakage rate value of the circuit.
In another aspect of the present disclosure, there is provided a primary circuit leakage rate calculation apparatus during a cold test of a high temperature reactor, the apparatus including:
the first calculation module is used for calculating the average temperature value of each component according to the acquired temperature value of each temperature measurement point of the loop;
the second calculation module is used for calculating the average temperature of the loop, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature value of each component;
the third calculation module is used for calculating the body pressure of the primary circuit according to the pressure measuring point of the primary circuit, the integral temperature of the reactor pressure vessel and the integral temperature of the steam generator shell;
the fourth calculation module is used for calculating the mass of the gas in the primary circuit at a certain moment according to the average temperature of the primary circuit and the body pressure of the primary circuit;
and the fifth calculation module is used for calculating the leakage rate of the primary circuit according to the calculated mass of the gas of the primary circuit at different moments.
In some embodiments, the second calculation module for calculating the average temperature of the circuit, the bulk temperature of the reactor pressure vessel, and the bulk temperature of the steam generator shell according to the average temperature of each of the components includes:
and the second calculation module is used for calculating the average temperature of the circuit, the bulk temperature of the reactor pressure vessel and the bulk temperature of the steam generator shell according to the average temperature of each component and the volume proportion of each component in the circuit.
In some embodiments, the third calculation module for calculating the bulk pressure of the circuit from the temperature of the entire system including the pressure measurement point of the circuit, the reactor pressure vessel, and the steam generator shell comprises:
and the third calculating module is used for calculating the body pressure of the primary circuit according to the pressure measuring point of the primary circuit, the overall temperatures of the reactor pressure vessel and the steam generator shell and the volume proportion of the reactor pressure vessel and the steam generator shell in the primary circuit.
According to the method and the device for calculating the leakage rate of the loop in the high-temperature reactor cold test period, the average temperature value of each part is obtained according to the temperature value of the loop temperature measuring point. Then, the average temperature of the primary circuit, and the overall temperature of the reactor pressure vessel and the steam generator shell are calculated according to the average temperature values. And then, calculating the body pressure of the primary circuit according to the pressure measuring point and the overall temperature. And then, calculating the mass of the gas in the primary circuit at a certain moment according to the average temperature and the body pressure of the primary circuit. And finally, calculating the leakage rate of the primary circuit according to the calculated mass of the gas of the primary circuit at different moments. The leakage rate of the loop in the cold test period of the high-temperature reactor can be accurately measured, and the gap that the leakage rate of the loop cannot be measured in the prior art is filled.
Drawings
FIG. 1 is a flow chart illustrating a method for calculating a loop leakage rate during a cold test of a high temperature reactor according to an embodiment of the present disclosure;
fig. 2 is a schematic structural diagram of a primary circuit leakage rate calculation device during a cold test of a high temperature reactor according to another embodiment of the disclosure.
Detailed Description
For a better understanding of the technical aspects of the present disclosure, reference is made to the following detailed description taken in conjunction with the accompanying drawings.
As shown in fig. 1, an embodiment of the present disclosure relates to a method S100 for calculating a leakage rate of a primary circuit during a cold test of a high temperature reactor, where the method S100 includes:
and S110, calculating the average temperature value of each component according to the acquired temperature values of the temperature measuring points of the loop.
Specifically, in this step, one or more temperature measurement points may be provided in advance at the respective components of the high temperature stack to measure the temperature of each component using the temperature measurement points. In order to ensure the accuracy of the measurement result, it is necessary to calculate the average temperature value of each component according to the collected temperature values of the temperature measuring points, that is, each component is provided with a plurality of temperature measuring points, and the average temperature value of the component is obtained by averaging the temperature values measured by the plurality of temperature measuring points. The present embodiment is not limited to how many temperature measuring points are arranged on each component, and those skilled in the art can determine the temperature measuring points according to actual needs. In addition, a temperature sensor or other devices capable of measuring temperature can be arranged at each temperature measuring point.
And S120, calculating the average temperature of the loop, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature value of each component.
Specifically, in this step, after the average temperature of each of the components is calculated, the average temperature of the circuit, the bulk temperature of the reactor pressure vessel, and the bulk temperature of the steam generator shell may be calculated based on the average temperature of these components.
S130, calculating the body pressure of the primary loop according to the pressure measuring point of the primary loop, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell.
Specifically, in this step, the bulk pressure of the primary circuit may be calculated according to a plurality of pressure measurement points (e.g., two pressure measurement points, etc.) arranged in the primary circuit, the overall temperature of the reactor pressure vessel, and the overall temperature of the steam generator shell.
S140, calculating the mass of the gas in the primary circuit at a certain moment according to the average temperature of the primary circuit and the body pressure of the primary circuit.
Specifically, in this step, the mass of the gas in the primary circuit at a certain time may be calculated according to an ideal gas state equation, and according to the average temperature of the primary circuit and the bulk pressure of the primary circuit calculated at the certain time. That is, in the embodiment of the present disclosure, when the mass of the gas in the primary circuit at a certain time needs to be calculated, the steps S110 to S140 need to be performed.
S150, calculating the leakage rate of the primary loop according to the calculated mass of the gas of the primary loop at different moments.
Specifically, in this step, the different times t may be compared according to the cold test requirements of the high temperature gas cooled reactor nuclear power plant 1 、t 2 Calculated mass m of gas of the primary circuit 1 、m 2 Calculating the leakage rate of said circuit, i.e. leakage rate = (m) 1 -m 2 )/m 1 。
In the method for calculating the leakage rate of the primary circuit of the embodiment, the temperature average value of each component is obtained according to the temperature value of the primary circuit temperature measuring point. Then, the average temperature of the primary circuit, and the overall temperature of the reactor pressure vessel and the steam generator shell are calculated according to the average temperature values. And then, calculating the body pressure of the primary circuit according to the pressure measuring point and the overall temperature. And then, calculating the mass of the gas in the primary circuit at a certain moment according to the average temperature and the body pressure of the primary circuit. And finally, calculating the leakage rate of the primary circuit according to the calculated mass of the gas of the primary circuit at different moments. The embodiment can accurately measure the leakage rate of the loop in the cold test period of the high-temperature reactor, and fills the gap that the leakage rate of the loop cannot be measured in the prior art.
In some embodiments, the calculating an average temperature value of each component according to the collected temperature values of the temperature measurement points of the loop includes:
and respectively comparing the temperature value of each temperature measuring point with a preset temperature threshold range, and rejecting the temperature measuring points which are not matched with the temperature threshold range. And calculating the average temperature value of each part according to the temperature values of the rest temperature measuring points.
Specifically, in the present embodiment, the inventors found that, after a plurality of temperature measurement points are provided on each component during a cold test, there is a deviation in the calculated primary circuit leakage rate in some cases of the test. The inventor finds out through a comparison test that in some cases, not all temperature measuring points can accurately reflect the actual temperature of each component, for example, the temperature values measured by some temperature measuring points are obviously low, or the temperature values measured by some temperature measuring points are obviously high, and the like, so that in the actual sampling process, the abnormal temperature measuring points need to be removed, and the calculated leakage rate of the primary circuit can be ensured to be more accurate.
In some embodiments, calculating the average temperature of the loop, the bulk temperature of the reactor pressure vessel, and the bulk temperature of the steam generator shell based on the average temperature of each of the components comprises:
and calculating the average temperature of the primary circuit, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature of each component and the proportion of each component in the primary circuit.
It should be noted that, in this embodiment, no limitation is made on the specific form of the proportion, and preferably, the proportion is a volume proportion. That is, the average temperature of the primary circuit, the overall temperature of the reactor pressure vessel, and the overall temperature of the steam generator shell can be accurately calculated based on the average temperature of each of the components and the volume fraction of each of the components in the primary circuit. Of course, besides the above, other proportion portions, such as weight proportion portion, etc., can be selected by those skilled in the art according to actual needs.
In some embodiments, calculating the bulk pressure of the circuit from the bulk temperatures of the pressure measurement point of the circuit, the reactor pressure vessel, and the steam generator shell comprises:
and calculating the bulk pressure of the primary circuit according to the pressure measuring point of the primary circuit, the overall temperature of the reactor pressure vessel and the steam generator shell and the proportion of the reactor pressure vessel and the steam generator shell in the primary circuit.
It should be noted that, in the present embodiment, the specific form of the proportion is not limited, and preferably, the proportion is a volume proportion. That is, the bulk pressure of the primary circuit can be accurately calculated based on the pressure measurement point of the primary circuit, the overall temperatures of the reactor pressure vessel and the steam generator shell, and the volume fraction of the reactor pressure vessel and the steam generator shell in the primary circuit. Of course, besides the above, other proportion portions, such as weight proportion portion, etc., can be selected by those skilled in the art according to actual needs.
In some embodiments, the method further comprises: and displaying the calculated leakage rate value of the primary circuit.
Specifically, in this step, the calculated leakage rate value may be pushed to a remote terminal, such as a remote mobile phone, a computer, a tablet, or the like, or the calculated leakage rate value may be directly displayed on a display screen of a cold test site, and the present embodiment is not limited thereto.
In another aspect of the present disclosure, as shown in fig. 2, a primary loop leakage rate calculation apparatus 100 is provided, and the apparatus 100 may be applied to the above-mentioned calculation method, and it can be referred to the above-mentioned related description, which is not repeated herein. The apparatus 100 comprises:
the first calculation module 110 is configured to calculate a temperature average value of each component according to the acquired temperature value of each temperature measurement point of the loop;
a second calculating module 120, configured to calculate an average temperature of the loop, a bulk temperature of the reactor pressure vessel, and a bulk temperature of the steam generator shell according to the average temperature value of each of the components;
a third calculation module 130 for calculating the bulk pressure of the primary loop based on the pressure measurement point of the primary loop, the bulk temperatures of the reactor pressure vessel and the steam generator shell;
a fourth calculating module 140, configured to calculate a mass of the gas in the primary loop at a certain time according to the average temperature of the primary loop and the bulk pressure of the primary loop;
a fifth calculating module 150, configured to calculate a leakage rate of the primary circuit according to the mass of the gas of the primary circuit calculated at different times.
In the primary circuit leakage rate calculation device of the present embodiment, the temperature average value of each component is obtained according to the temperature value of the primary circuit temperature measurement point. Then, the average temperature of the primary circuit and the overall temperature of the reactor pressure vessel and the steam generator shell are calculated according to the average temperature values. And then, calculating the body pressure of the primary circuit according to the pressure measuring point and the overall temperature. And then, calculating the mass of the gas in the primary circuit at a certain moment according to the average temperature and the body pressure of the primary circuit. And finally, calculating the leakage rate of the primary circuit according to the calculated mass of the gas of the primary circuit at different moments. The embodiment can accurately measure the leakage rate of the loop in the cold test period of the high-temperature reactor, and fills the gap that the leakage rate of the loop cannot be measured in the prior art.
In some embodiments, as shown in fig. 2, the second calculating module 120 is configured to calculate the average temperature of the circuit, the bulk temperature of the reactor pressure vessel, and the bulk temperature of the steam generator shell according to the average temperature of each of the components, and includes:
the second calculating module 120 is configured to calculate an average temperature of the circuit, a bulk temperature of the reactor pressure vessel, and a bulk temperature of the steam generator shell according to the average temperature of each of the components and a volume fraction of each of the components in the circuit.
In some embodiments, as shown in fig. 2, the third calculating module 130 for calculating the bulk pressure of the primary loop based on the pressure measurement of the primary loop, the bulk temperature of the reactor pressure vessel and the steam generator shell comprises:
the third calculating module 130 is configured to calculate the bulk pressure of the primary loop according to the pressure measuring point of the primary loop, the overall temperatures of the reactor pressure vessel and the steam generator shell, and the volume fractions of the reactor pressure vessel and the steam generator shell in the primary loop.
It will be understood that the above embodiments are merely exemplary embodiments employed to illustrate the principles of the present disclosure, and the present disclosure is not limited thereto. It will be apparent to those skilled in the art that various changes and modifications can be made therein without departing from the spirit and scope of the disclosure, and these changes and modifications are to be considered within the scope of the disclosure.

Claims (8)

1. A method for calculating a loop leakage rate during a high-temperature reactor cold test is characterized by comprising the following steps:
calculating the average temperature value of each component according to the acquired temperature value of each temperature measuring point of the loop;
calculating the average temperature of the loop, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature value of each component;
calculating the body pressure of the primary loop according to the pressure measuring point of the primary loop, the integral temperature of the reactor pressure vessel and the steam generator shell;
calculating the mass of the gas of the primary circuit at a certain moment according to the average temperature of the primary circuit and the body pressure of the primary circuit;
calculating the leakage rate of the primary circuit according to the calculated mass of the gas of the primary circuit at different moments;
calculating the bulk pressure of the primary loop from the pressure measurement points of the primary loop, the bulk temperatures of the reactor pressure vessel and the steam generator shell, comprising:
and calculating the body pressure of the primary circuit according to the pressure measuring point of the primary circuit, the overall temperature of the reactor pressure vessel and the steam generator shell and the proportion of the reactor pressure vessel and the steam generator shell in the primary circuit.
2. The method of claim 1, wherein calculating an average temperature value for each component based on the collected temperature values for each temperature measurement point of the circuit comprises:
respectively comparing the temperature value of each temperature measuring point with a preset temperature threshold range, and rejecting the temperature measuring points which are not matched with the temperature threshold range;
and calculating the average temperature value of each part according to the temperature values of the rest temperature measuring points.
3. The method of claim 1, wherein calculating an average temperature of the circuit, a bulk temperature of the reactor pressure vessel, and a bulk temperature of the steam generator shell based on the average temperature of each of the components comprises:
and calculating the average temperature of the primary circuit, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature of each component and the proportion of each component in the primary circuit.
4. The method according to claim 3, characterized in that the specific portion is a volume specific portion.
5. The method according to claim 1, characterized in that the specific portion is a volume specific portion.
6. The method according to any one of claims 1 to 5, further comprising:
and displaying the calculated leakage rate value of the circuit.
7. A loop leakage rate calculation apparatus during a high temperature stack cold test, the apparatus comprising:
the first calculation module is used for calculating the temperature average value of each component according to the acquired temperature value of each temperature measuring point of the loop;
the second calculation module is used for calculating the average temperature of the loop, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature value of each component;
the third calculation module is used for calculating the body pressure of the primary circuit according to the pressure measuring point of the primary circuit, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell;
a fourth calculating module, configured to calculate a mass of the gas in the primary circuit at a time according to the average temperature of the primary circuit and a bulk pressure of the primary circuit;
the fifth calculation module is used for calculating the leakage rate of the primary circuit according to the calculated mass of the gas of the primary circuit at different moments;
the third calculating module is configured to calculate the bulk pressure of the primary loop according to the pressure measurement point of the primary loop, the overall temperatures of the reactor pressure vessel and the steam generator shell, and includes:
and the third calculating module is used for calculating the bulk pressure of the primary circuit according to the pressure measuring point of the primary circuit, the overall temperatures of the reactor pressure vessel and the steam generator shell, and the volume proportion of the reactor pressure vessel and the steam generator shell in the primary circuit.
8. The apparatus of claim 7, wherein said second calculating means for calculating an average temperature of said circuit, a bulk temperature of a reactor pressure vessel, and a bulk temperature of a steam generator shell based on an average temperature of each of said components comprises:
and the second calculation module is used for calculating the average temperature of the circuit, the overall temperature of the reactor pressure vessel and the overall temperature of the steam generator shell according to the average temperature of each component and the volume proportion of each component in the circuit.
CN202110580316.2A 2021-05-26 2021-05-26 Method and device for calculating leakage rate of primary loop during high-temperature reactor cold test Active CN113421674B (en)

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