CN107024256B - Device and method for measuring liquid level of nuclear reactor container - Google Patents
Device and method for measuring liquid level of nuclear reactor container Download PDFInfo
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- CN107024256B CN107024256B CN201710307479.7A CN201710307479A CN107024256B CN 107024256 B CN107024256 B CN 107024256B CN 201710307479 A CN201710307479 A CN 201710307479A CN 107024256 B CN107024256 B CN 107024256B
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- 239000007788 liquid Substances 0.000 title claims abstract description 68
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- 238000001514 detection method Methods 0.000 claims abstract description 42
- 230000005540 biological transmission Effects 0.000 claims abstract description 34
- 239000002826 coolant Substances 0.000 claims abstract description 24
- 238000004891 communication Methods 0.000 claims abstract description 15
- 239000000523 sample Substances 0.000 claims description 23
- 239000000463 material Substances 0.000 claims description 16
- 230000007797 corrosion Effects 0.000 claims description 10
- 238000005260 corrosion Methods 0.000 claims description 10
- 239000012530 fluid Substances 0.000 claims 3
- 238000005259 measurement Methods 0.000 abstract description 17
- 230000005855 radiation Effects 0.000 description 11
- 229910000831 Steel Inorganic materials 0.000 description 3
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- 239000010959 steel Substances 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
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- 238000005516 engineering process Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
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- 239000002184 metal Substances 0.000 description 1
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- 230000002035 prolonged effect Effects 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 239000003381 stabilizer Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01F—MEASURING VOLUME, VOLUME FLOW, MASS FLOW OR LIQUID LEVEL; METERING BY VOLUME
- G01F23/00—Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm
- G01F23/22—Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm by measuring physical variables, other than linear dimensions, pressure or weight, dependent on the level to be measured, e.g. by difference of heat transfer of steam or water
- G01F23/28—Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm by measuring physical variables, other than linear dimensions, pressure or weight, dependent on the level to be measured, e.g. by difference of heat transfer of steam or water by measuring the variations of parameters of electromagnetic or acoustic waves applied directly to the liquid or fluent solid material
- G01F23/296—Acoustic waves
- G01F23/2962—Measuring transit time of reflected waves
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention provides a device and a method for measuring the liquid level of a nuclear reactor container, wherein the device comprises: the ultrasonic detection device comprises a time controller, a signal generator, a transmitting end, a receiving end, an amplifier, a waveform processor and an ultrasonic detection tube, wherein the time controller is in communication connection with the signal generator and the waveform processor; the ultrasonic detection tube comprises at least two connected tube sections, the inner diameters of the tube sections are sequentially reduced towards the direction of a nuclear reactor coolant, and the waveform processor calculates the numerical value of the liquid level of the nuclear reactor container according to the receiving time of ultrasonic waves reflected by the tube sections and the length of the tube sections. The invention can determine the relation K value of the ratio of the liquid level or the ultrasonic transmission distance to the ultrasonic transmission time in the measurement process, and can accurately measure the liquid level of the nuclear reactor container even in the environment with obvious temperature gradient change or gas density gradient change in the nuclear reactor.
Description
Technical Field
The invention relates to the technical field of nuclear power, in particular to a device and a method for measuring the liquid level of a nuclear reactor container.
Background
At present, the containers of nuclear reactors in nuclear power plants are covered with coolant, and the level of the coolant is crucial to the fuel cooling of the reactor and the safe operation of the whole reactor. The design and arrangement of nuclear reactor equipment, the material composition of the coolant in the reactor, the transient safety performance criteria of the reactor and the like put high demands on a reasonably feasible coolant level measurement scheme.
At present, the coolant liquid level measurement in a pressurized water reactor comprises the measurement of the liquid level of a voltage stabilizer, the measurement of a spent fuel pool and the like, and a pressure sensor or two major measurement types of a microwave, sound wave, ultrasonic wave, radar or laser measuring instrument are generally adopted.
When the pressure sensor is deployed, besides the wide-narrow range differential pressure gauge, a reference differential pressure gauge is also required to be deployed. The pressure difference meter mainly considers the influence of temperature change in a reactor on a pressure sensor and is used for correcting the pressure difference meter with wide measuring range and narrow measuring range.
Whether pressure sensors or ultrasonic sensors, it is difficult to obtain accurate measurements for regions of the reactor where temperature gradients vary significantly, and large errors are introduced. The measurement of the liquid level distance has obvious relation with the temperature gradient in the reactor.
When an ultrasonic probe is deployed, calibration needs to be performed for the measurement distance and accuracy of the ultrasonic wave. The calibration is usually performed under non-reactor normal operation conditions, such as before reactor start-up, after shutdown, etc. The measured and calibrated conditions (such as temperature and coolant conditions) and the like have larger differences from the actual operation conditions. Thus resulting in a decrease in calibration accuracy.
Taking the measurement of the ultrasonic sensor as an example, the prior art generally adopts an off-line calibration mode, that is, the determination of the relation K value between the liquid level or distance and the ultrasonic transmission time ratio is performed when the ultrasonic sensor enters a certain laboratory or enters a stable environment. The value of the coefficient K is determined to be not changed along with the working environment. In a working environment, the prior art cannot carry out online K value calibration because of no reference distance. The liquid level or distance is determined by measuring the ultrasonic transmission time on line and the K value calculated in advance. The obvious defect of the prior art is that the error of the off-line 'K value of the relation between the liquid level or the distance and the ultrasonic transmission time' is larger. Since there is a significant temperature gradient change in the reactor environment over the entire measurement distance, a parameter defined off-line (without consideration of the actual environment) will cause a large error. The current measurement technology is difficult to measure the environment with obvious temperature gradient change in the reactor with high precision.
Disclosure of Invention
In order to solve the technical problem, the invention provides a device and a method for measuring the liquid level of a nuclear reactor container.
The invention provides a device for measuring the liquid level of a nuclear reactor container, which comprises: the ultrasonic detection device comprises a time controller, a signal generator, a transmitting end, a receiving end, an amplifier, a waveform processor and an ultrasonic detection tube, wherein the time controller is respectively in communication connection with the signal generator and the waveform processor, the signal generator is in communication connection with the transmitting end, the receiving end is in communication connection with the amplifier, and the amplifier is in communication connection with the waveform processor;
the ultrasonic detection tube comprises at least two connected tube sections, and the inner diameters of the tube sections of the ultrasonic detection tube are sequentially reduced;
the time controller outputs a transmission control signal to the signal generator and the waveform processor, the signal generator generates a corresponding transmission pulse signal according to the transmission control signal and outputs the transmission pulse signal to the transmitting end, and the transmitting end generates a corresponding ultrasonic wave according to the transmission pulse signal and transmits the ultrasonic wave;
the receiving end receives the reflected ultrasonic waves and converts the reflected ultrasonic waves into corresponding electric signals, the electric signals are amplified through the amplifier to generate corresponding receiving pulse signals and output the receiving pulse signals to the waveform processor, the waveform processor obtains receiving time of the corresponding ultrasonic waves according to the receiving pulse signals and the emission control signals, and the numerical value of the liquid level of the nuclear reactor container is obtained through calculation according to the length of the pipe section of the ultrasonic detection pipe.
Preferably, the transmitting end and the receiving end are opposite to the orifice of the ultrasonic detection tube; the periphery of the ultrasonic detection tube is wrapped with a material for reducing noise or external signal interference generated by the nuclear reactor.
Preferably, the device further comprises a display which is in communication connection with the waveform processor, and the waveform processor displays the numerical value of the nuclear reactor liquid level obtained through calculation through the display.
Preferably, when the corresponding section of the ultrasonic detection tube is located at the upper part of the coolant level of the nuclear reactor vessel and reaches a preset first distance from the coolant level, the outer part of the ultrasonic detection tube is made of a material with a supporting force strength reaching a preset supporting force strength standard.
Preferably, when the corresponding pipe section in the ultrasonic detection pipe is located at the lower part of the coolant liquid level or located at the upper part of the coolant and is less than a preset second distance away from the coolant liquid level, the outer part of the ultrasonic detection pipe is made of a material with corrosion resistance strength reaching a preset corrosion resistance strength standard.
Preferably, when the number of the pipe sections of the ultrasonic detection pipe is 2, the pipe section close to the liquid level of the nuclear reactor container is set to be a 2 nd pipe section, the pipe section close to the receiving end is set to be a 1 st pipe section, and the time for the receiving end to receive the ultrasonic wave for the first time is T 1 The time of receiving the ultrasonic wave for the second time is T 2 And the length M of the 1 st pipe section is preset in the waveform processor 1 And the length M of the 2 nd pipe section 2 According to the following equation, the waveform processor calculates the nuclear reactor vessel level M 0 ：
M 0 ＝M 2 -M 1 *(T 2 -T 1 )/T 1 。
Preferably, when the number of the pipe sections of the ultrasonic detection pipe is n, wherein n is more than or equal to 3, the pipe sections of the ultrasonic detection pipe are sequentially set to be a 1 st pipe section, a 2 nd pipe section, … …, an n-2 nd pipe section, an n-1 st pipe section and an n th pipe section from the receiving end to the direction close to the liquid level of the nuclear reactor container, and the time corresponding to the receiving of different ultrasonic waves is T 1 、T 2 、……、T n-2 、T n-1 、T n And the lengths of the corresponding pipe sections are respectively as follows: m 1 、M 2 、……、M n-2 、M n-1 、M n Then the waveform processor calculates the nuclear reactor vessel level M according to the equation 0 ：K n-1 +(M 0 +M n-1 )/(M n-1 +M n-2 )*(K n-1 -K n-2 )＝M 0 *(T n -T n-1 ) Wherein, K is n-1 ＝M n-1 /(T n-1 -T n-2 )，K n-2 ＝M n-2 /(T n-2 -T n-3 )，T 0 ＝0。
The invention also provides a method for measuring the liquid level of the nuclear reactor container, which is realized in the device for measuring the liquid level of the nuclear reactor container and comprises the following steps:
s100, emitting ultrasonic waves at a pipe orifice of the ultrasonic detection pipe;
s200, receiving the reflected ultrasonic waves, and calculating to obtain a numerical value of the liquid level of the nuclear reactor container according to time data corresponding to the received ultrasonic waves and length data of a pipe section corresponding to the ultrasonic detection pipe.
Preferably, the first and second electrodes are formed of a metal,
the step S100 includes:
s110: the time controller outputs a transmission control signal to the signal generator and the waveform processor, and the signal generator generates a corresponding output pulse signal according to the transmission control signal and outputs the output pulse signal to a transmitting end;
s120: the transmitting end generates corresponding ultrasonic waves according to the output pulse signals and transmits the ultrasonic waves;
the step S200 includes:
s210, the receiving end receives the reflected ultrasonic wave, amplifies the ultrasonic wave through an amplifier and converts the ultrasonic wave into a corresponding received pulse signal to be output;
s220, the waveform processor receives the receiving pulse signal from the amplifier and the transmitting control signal output by the time controller, and obtains the time T corresponding to the receiving of different ultrasonic waves 1 、T 2 、……、T n-2 、T n-1 、T n Wherein n is more than or equal to 2, and the length M corresponding to the 1 st pipe section, the 2 nd pipe section, … … and the n-th pipe section of the corresponding ultrasonic probe pipe is determined 1 、M 2 、……、M n-2 、M n-1 、M n And calculating the nuclear reactor vessel level M according to the following equation 0 ：
If n =2,M 0 ＝M 2 -M 1 *(T 2 -T 1 )/T 1 ；
If n is not less than 3,K n-1 +(M 0 +M n-1 )/(M n-1 +M n-2 )*(K n-1 -K n-2 )＝M 0 *(T n -T n-1 ) Wherein, K is n-1 ＝M n-1 /(T n-1 -T n-2 )，K n-2 ＝M n-2 /(T n-2 -T n-3 )，T 0 ＝0。
Preferably, the waveform processor is used for calculating the liquid level M of the nuclear reactor container 0 And then displayed by the display.
The implementation of the invention has the following beneficial effects: when the temperature of the space above the liquid level of the nuclear reactor container and the density of the covered gas are changed in a gradient manner and the change is in a linear relationship, because the ultrasonic detecting tube of the device for measuring the liquid level of the nuclear reactor container adopts a sectional type detecting tube, a receiving end can receive ultrasonic waves reflected by different tube sections, and a waveform processor can know the relation K value of the ratio of the liquid level or the transmission distance of the ultrasonic waves to the transmission time of the ultrasonic waves and the length of each tube section according to the time required for receiving the corresponding ultrasonic waves and the length of each tube section, and then the liquid level of the nuclear reactor container can be calculated according to the K value.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
FIG. 1 is a schematic configuration view of an apparatus for measuring a liquid level in a nuclear reactor vessel according to the present invention.
FIG. 2 is a schematic diagram of noise interference when measuring the liquid level in a nuclear reactor vessel according to the present invention.
FIG. 3 is a schematic view of the disposition of the device for measuring the liquid level in the vessel of a nuclear reactor provided by the present invention.
FIG. 4 is a flow chart of a method of measuring nuclear reactor vessel level provided by the present invention.
FIG. 5 is a diagram of ultrasonic waveforms for measuring the level of a nuclear reactor vessel provided by the present invention.
Detailed Description
The invention provides a device for measuring the level of a nuclear reactor vessel, as shown in figure 1, comprising: the ultrasonic detection device comprises a time controller 100, a signal generator 200, a transmitting end 300, a receiving end 400, an amplifier 500, a waveform processor 600 and an ultrasonic detection tube 700, wherein the time controller 100 is respectively in communication connection with the signal generator 200 and the waveform processor 600, the signal generator 200 is in communication connection with the transmitting end 300, the receiving end 400 is in communication connection with the amplifier 500, and the amplifier 500 is in communication connection with the waveform processor 600.
The ultrasonic probe tube 700 includes at least two connected tube segments, and the inner diameters of the tube segments of the ultrasonic probe tube 700 are sequentially reduced toward the coolant of the nuclear reactor, it should be noted that the inner diameter of each tube segment is not changed, and a reflection platform for ultrasonic waves is formed at the joint of two adjacent tube segments. When the ultrasonic probe tube 700 has a segmented outer tube structure, the outer material of each segment may be different. Because neutron radiation, a temperature field, a coolant corrosion environment and the like in the reactor core obviously have gradient changes, different pipe sections corresponding to the ultrasonic detection pipe 700 can be made of different materials according to the environment, so that the service life of the whole measuring device is prolonged. Furthermore, the lengths of the different pipe sections may differ.
The number of the pipe sections of the ultrasonic detection pipe 700 can be determined according to the environment of the reactor vessel to be measured, and when the temperature gradient change of the reactor is large or the gas density gradient covered on the upper part of the liquid level of the reactor vessel is large and the gradient change is in a linear relationship, the number of the pipe sections can be increased; when the temperature of the reactor or the gas density gradient covered on the upper part of the liquid level of the reactor container has small change and the change of the gradient is in a linear relation, the number of the pipe sections can be correspondingly reduced.
The time controller 100 outputs the emission control signal to the signal generator 200 and the waveform processor 600, the signal generator 200 generates a corresponding emission pulse signal according to the emission control signal and outputs the emission pulse signal to the emission terminal 300, and the emission terminal 300 generates a corresponding ultrasonic wave according to the emission pulse signal and emits the ultrasonic wave. Specifically, the transmitting terminal 300 may be provided with an ultrasonic transducer, the transmission control signal output by the time controller 100 may be a commercial power signal, the signal generator 200 converts the commercial power signal into a high-frequency ac pulse signal matched with the ultrasonic transducer, and the ultrasonic transducer converts the high-frequency ac pulse signal into corresponding ultrasonic wave for transmission. Specifically, the transmitting end 300 and the receiving end 400 are opposite to the mouth of the ultrasonic probe 700, so as to prevent the wall of the ultrasonic probe from reflecting ultrasonic waves and interfering with the measurement result.
The receiving end 400 receives the reflected ultrasonic waves and converts the reflected ultrasonic waves into corresponding electric signals, the electric signals are amplified by the amplifier 500 to generate corresponding received pulse signals and output the received pulse signals to the waveform processor 600, the waveform processor 600 obtains the receiving time of the corresponding ultrasonic waves according to the received pulse signals and the emission control signals, and the numerical value of the liquid level of the nuclear reactor container is calculated according to the length of the pipe section of the ultrasonic detection pipe 700. Specifically, the waveform processor 600 obtains the time when the transmitting end transmits the ultrasonic wave according to the transmission control signal output by the time controller 100, obtains the time corresponding to the received different ultrasonic waves according to the received pulse signal, calculates the receiving time corresponding to the different ultrasonic waves, calculates the corresponding "ratio K" of the liquid level or the ultrasonic wave transmission distance to the ultrasonic wave transmission time "according to the length of each pipe section, and finally calculates the liquid level of the nuclear reactor container according to the value K.
Further, the ultrasonic probe tube 700 is wrapped at its outer periphery with a material for reducing noise generated from a nuclear reactor or interference of external signals. As shown in fig. 2, when the liquid level of the nuclear reactor vessel is measured, there may be other external noise interferences, for example, due to environmental influences of neutron radiation, photon radiation, and electronic signals, which may cause the receiving end 400 to receive other interference signals in addition to the reflected ultrasonic waves, thereby affecting the measurement result, and the periphery of the ultrasonic detection tube 700 is wrapped with a material for reducing noise generated by the nuclear reactor or external neutron radiation, photon radiation, and electronic signal interferences, so as to ensure that noise interferences are reduced and the measurement accuracy is improved.
Further, the device for measuring the liquid level of the nuclear reactor container also comprises a display 800 which is in communication connection with the waveform processor 600, and the waveform processor 600 displays the value of the liquid level of the nuclear reactor through the display 800 after calculating the value.
Further, when the corresponding pipe segment of the ultrasonic probe 700 is located above the coolant level of the nuclear reactor vessel and is a first distance from the coolant level that the neutron radiation is small, the exterior of the ultrasonic probe is made of a material having a supporting force strength meeting the preset supporting force strength standard, for example, T91 steel, which has a strong supporting force, and the mechanical and corrosion properties related to the industrial T91 steel have been sufficiently analyzed, but the supporting force is strong but the radiation performance is general, which may have a risk of embrittlement, and needs to limit the neutron radiation strength.
When the corresponding pipe segment of the ultrasonic probe 700 is located at the lower portion of the coolant level or at the upper portion of the coolant level and is located at a distance from the coolant level less than a predetermined second distance where neutron radiation is strong, the outer portion of the ultrasonic probe is made of a material having a corrosion resistance strength meeting a predetermined corrosion resistance strength standard, for example, a 316L steel material may be selected, which has a strong corrosion resistance and a low embrittlement risk.
Further, when the number of the pipe segments of the ultrasonic detection pipe 700 is 2, the pipe segment close to the liquid level of the nuclear reactor container is set to be the 2 nd pipe segment, the pipe segment close to the receiving end 400 is set to be the 1 st pipe segment, and the time when the receiving end 400 receives the ultrasonic waves for the first time is T 1 The time of receiving the ultrasonic wave for the second time is T 2 And the length M of the 1 st pipe segment is preset in the waveform processor 600 1 And length M of 2 nd pipe segment 2 And calculating the nuclear reactor vessel level M according to the following equation 0 ：M 0 ＝M 0 ＝M 2 -M 1 *(T 2 -T 1 )/T 1 ，M 0 The distance between the liquid level of the nuclear reactor container and the joint of the 1 st pipe section and the 2 nd pipe section.
Setting the number of the pipe sections of the ultrasonic detection pipe 700 as n, wherein when n is more than or equal to 3, the pipe sections of the ultrasonic detection pipe 700 are sequentially set as a 1 st pipe section, a 2 nd pipe section, … …, an n-2 nd pipe section, an n-1 th pipe section and an n th pipe section from the receiving end 400 to the direction close to the liquid level of the nuclear reactor container, and the time corresponding to the receiving of different ultrasonic waves is T 1 、T 2 、……、T n-2 、T n-1 、T n And the lengths of the corresponding pipe sections are respectively as follows: m is a group of 1 、M 2 、……、M n-2 、M n-1 、M n Then the waveform processor 600 calculates the nuclear reactor vessel level M according to the following equation 0 ：K n-1 +(M 0 +M n-1 )/(M n-1 +M n-2 )*(K n-1 -K n-2 )＝M 0 *(T n -T n-1 ) Wherein, K is n-1 ＝M n-1 /(T n-1 -T n-2 )，K n-2 ＝M n-2 /(T n-2 -T n-3 )，T 0 ＝0，M 0 The distance between the liquid level of the nuclear reactor container and the joint of the nth pipe section and the (n-1) th pipe section.
In the present invention, the ultrasonic probe tube 700 has a specific sectional geometry (the overall length of the ultrasonic probe tube and the length of the corresponding tube segment during the measurement are determined, and there is a reference distance), and it is possible to define "a relationship K between the liquid level or the ratio of the ultrasonic transmission distance to the ultrasonic transmission time" of the ultrasonic transmission distance segments corresponding to a plurality of different tube segments. The method has the advantages that when the measurement environment is in obvious temperature field gradient change or the medium density has obvious gradient change, the gradient change of the K value can be effectively considered, the K value in practical application can be accurately calculated, and the liquid level of the nuclear reactor container can be calculated.
As shown in fig. 3, the apparatus for measuring the liquid level in a nuclear reactor vessel of the present invention is deployed by inserting one side of an ultrasonic probe below the liquid level in the nuclear reactor.
The invention also provides a method for measuring the liquid level of a nuclear reactor vessel, which is implemented in the device for measuring the liquid level of the nuclear reactor vessel, and as shown in fig. 4, the method comprises the following steps:
s100, the transmitting end 300 faces the pipe orifice of the ultrasonic detection pipe 700 and transmits ultrasonic waves.
S200, the receiving end 400 receives the reflected ultrasonic waves, and calculates to obtain a numerical value of the liquid level of the nuclear reactor container according to time data corresponding to the received ultrasonic waves and length data of the pipe section corresponding to the ultrasonic detection pipe 700.
Further, step S100 includes:
s110: the time controller 100 outputs a transmission control signal to the signal generator 200 and the waveform processor 600, and the signal generator 200 generates a corresponding output pulse signal according to the transmission control signal and outputs the output pulse signal to the transmitting terminal 300.
S120: the transmitting terminal 300 generates and transmits corresponding ultrasonic waves according to the output pulse signals.
The step S200 includes:
s210, the receiving end 400 receives the reflected ultrasonic waves, amplifies the ultrasonic waves through the amplifier 500 and converts the ultrasonic waves into corresponding received pulse signals, and outputs the received pulse signals to the waveform processor 600.
S220, wave form processingThe processor 600 receives the receiving pulse signal from the amplifier 500 and the transmission control signal output by the time controller 100, and obtains the time T corresponding to the receiving of different ultrasonic waves 1 、T 2 、……、T n-2 、T n-1 、T n Wherein n is more than or equal to 2, and the length M corresponding to the 1 st pipe section, the 2 nd pipe section, … … and the nth pipe section of the corresponding ultrasonic detection pipe is determined 1 、M 2 、……、M n-2 、M n-1 、M n And calculating the liquid level M of the nuclear reactor vessel according to the following equation 0 ：
If n =2,M 0 ＝M 2 -M 1 *(T 2 -T 1 )/T 1 ；
If n is not less than 3,K n-1 +(M 0 +M n-1 )/(M n-1 +M n-2 )*(K n-1 -K n-2 )＝M 0 *(T n -T n-1 ) Wherein, K is n-1 ＝M n-1 /(T n-1 -T n-2 )，K n-2 ＝M n-2 /(T n-2 -T n-3 )，T 0 ＝0。
For example, when n =3, M is calculated according to the following equation 0 ：
K 2 +(M 0 +M 2 )/(M 2 +M 1 )*(K 2 -K 1 )＝M 0 *(T 3 -T 2 ) Wherein, K is 2 ＝M 2 /(T 2 -T 1 )，K 1 ＝M 1 /T 1 Corresponding ultrasonic waveform diagram As shown in FIG. 5, the time for receiving pulse 1 corresponding to the ultrasonic wave reflected from the 1 st pipe segment is proportional to M 1 The time for receiving the receiving pulse 2 corresponding to the ultrasonic wave reflected by the 1 st pipe section is proportional to M 2 The time for receiving the receiving pulse 3 corresponding to the ultrasonic wave reflected by the 1 st pipe section is proportional to M 3 。
Further, the waveform processor 600 displays the calculated nuclear reactor vessel level M0 through the display 800.
The invention relates to a device and a method for measuring the liquid level of a nuclear reactor container, when the temperature of the space above the liquid level of the nuclear reactor container and the density of covered gas are changed in a gradient way and the change is in a linear relation, because an ultrasonic detection tube 700 of the device adopts a sectional detection tube, the inner diameters of corresponding tube sections are sequentially reduced along the direction from a transmitting end 300 to the nuclear reactor container, a receiving end 400 can receive ultrasonic waves reflected by different tube sections, a waveform processor 600 can know the moment of transmitting the ultrasonic waves according to a time control signal output by a time controller 100 and then can know the time required for receiving the corresponding ultrasonic waves according to the moment of the received ultrasonic waves, and the length of the tube sections is known, so that the relation K value of the liquid level or the ratio of the transmission distance of the ultrasonic waves to the transmission time of the ultrasonic waves can be known, and the liquid level of the nuclear reactor container can be calculated according to the K value.
Furthermore, the ultrasonic detection tube 700 in the device for measuring the liquid level of the nuclear reactor container of the invention adopts a sectional structure, the radiation of neutrons is strong and the corrosivity is strong when the liquid level of the nuclear reactor container is close to or below the liquid level of the nuclear reactor container, the exterior of the tube section can be made of a material with strong corrosion resistance, the radiation of neutrons is weak when the liquid level of the nuclear reactor container is far away, and the material with strong supporting force can be selected.
The foregoing is a more detailed description of the invention in connection with specific preferred embodiments and it is not intended that the invention be limited to these specific details. For those skilled in the art to which the invention pertains, several simple deductions or substitutions can be made without departing from the spirit of the invention, and all shall be considered as belonging to the protection scope of the invention.
Claims (10)
1. An apparatus for measuring the level of a liquid in a nuclear reactor vessel, comprising: the ultrasonic wave detection device comprises a time controller (100), a signal generator (200), a transmitting end (300), a receiving end (400), an amplifier (500), a waveform processor (600) and an ultrasonic wave detection tube (700), wherein the time controller (100) is respectively in communication connection with the signal generator (200) and the waveform processor (600), the signal generator (200) is in communication connection with the transmitting end (300), the receiving end (400) is in communication connection with the amplifier (500), and the amplifier (500) is in communication connection with the waveform processor (600);
the ultrasonic detection tube (700) comprises at least two connected tube sections, and the inner diameters of the tube sections of the ultrasonic detection tube (700) are sequentially reduced;
the time controller (100) outputs a transmission control signal to the signal generator (200) and the waveform processor (600), the signal generator (200) generates a corresponding transmission pulse signal according to the transmission control signal and outputs the transmission pulse signal to the transmitting terminal (300), and the transmitting terminal (300) generates a corresponding ultrasonic wave according to the transmission pulse signal and transmits the ultrasonic wave;
the receiving end (400) receives the reflected ultrasonic waves and converts the reflected ultrasonic waves into corresponding electric signals, the electric signals are amplified through the amplifier (500) to generate corresponding receiving pulse signals and output the corresponding receiving pulse signals to the waveform processor (600), the waveform processor (600) obtains receiving time of the corresponding ultrasonic waves according to the receiving pulse signals and the emission control signals, and the numerical value of the liquid level of the nuclear reactor container is obtained through calculation according to the length of the pipe section of the ultrasonic detection pipe (700);
wherein, the time for the waveform processor (600) to acquire the received different ultrasonic waves is:
、
、……、
、
、
wherein n is more than or equal to 2, and the lengths corresponding to the 1 st pipe section, the 2 nd pipe section, the … … and the nth pipe section of the ultrasonic probe (700) are->
、
、……、
、
、
Calculating the nuclear reactor vessel level ≥ according to the equation>
：
If n =2, the number of the bits is greater than or equal to 2,
=
-
*(
-
)/
；
if n is more than or equal to 3,
wherein, in the step (A),
，
，
=0。
2. an apparatus for measuring the nuclear reactor tank level according to claim 1, characterized in that said transmitting end (300) and said receiving end (400) are facing the mouth of said ultrasonic probe tube (700); the periphery of the ultrasonic detection tube (700) is wrapped with a material for reducing noise or external signal interference generated by the nuclear reactor.
3. The apparatus of claim 1, further comprising a display (800) communicatively coupled to the waveform processor (600), wherein the waveform processor (600) displays the calculated nuclear reactor fluid level value via the display (800).
4. An apparatus for measuring a nuclear reactor vessel level according to claim 1, characterized in that when the corresponding section of the ultrasonic probe tube (700) is located above the coolant level of the nuclear reactor vessel and at a predetermined first distance from the coolant level, the exterior thereof is made of a material having a supporting force strength that meets a predetermined supporting force strength standard.
5. Apparatus for measuring the level of a nuclear reactor vessel according to claim 4, characterized in that when the corresponding section of the ultrasonic probe tube (700) is located at the lower level of the coolant, or at the upper level of the coolant, at a distance less than a preset second distance from the coolant level, the exterior thereof is made of a material having a corrosion resistance strength that meets a preset corrosion resistance strength standard.
6. An apparatus for measuring a nuclear reactor vessel fluid level according to any one of claims 1 to 5, wherein when the number of the sections of the ultrasonic probe tube (700) is 2, the section near the nuclear reactor vessel fluid level is set as the 2 nd section, the section near the receiving end (400) is set as the 1 st section, and the time when the receiving end (400) receives the ultrasonic waves for the first time is set as
And the time for receiving the ultrasonic wave for the second time is->
And the length of the 1 st tube section is preset in the waveform processor (600)>
And the length of the 2 nd tube section>
Based on the following equation, the waveform processor (600) calculates a nuclear reactor vessel liquid level ÷ according to the following equation>
：
7. The apparatus for measuring the liquid level of a nuclear reactor vessel according to claim 6, wherein when the number of the sections of the ultrasonic probe tube (700) is n, where n is greater than or equal to 3, the sections of the ultrasonic probe tube (700) are sequentially set to 1 st section, 2 nd section, … …, n-2 nd section, n-1 th section, and n th section from the receiving end (400) to the direction close to the liquid level of the nuclear reactor vessel, and the times corresponding to the different ultrasonic waves are received:
、
、……、
、
、
and the lengths of the corresponding pipe sections are respectively as follows:
、
、……、
、
、
Then the waveform processor (600) calculates the nuclear reactor vessel liquid level ≥ according to the equation>
：
Wherein, in the step (A),
，
，
=0。
8. a method for measuring the level of a nuclear reactor vessel, implemented in a device for measuring the level of a nuclear reactor vessel according to any one of claims 1 to 5, characterized in that it comprises the following steps:
s100, emitting ultrasonic waves opposite to the pipe orifice of the ultrasonic detection pipe (700);
s200, receiving the reflected ultrasonic waves, and calculating to obtain a numerical value of the liquid level of the nuclear reactor container according to time data corresponding to the received ultrasonic waves and length data of a pipe section corresponding to the ultrasonic detection pipe (700).
9. A method of measuring nuclear reactor vessel liquid level according to claim 8,
the step S100 includes:
s110: the time controller (100) outputs a transmission control signal to the signal generator (200) and the waveform processor (600), and the signal generator (200) generates a corresponding output pulse signal according to the transmission control signal and outputs the output pulse signal to the transmitting terminal (300);
s120: the transmitting terminal (300) generates corresponding ultrasonic waves according to the output pulse signals and transmits the ultrasonic waves;
the step S200 includes:
s210, the receiving end (400) receives the reflected ultrasonic waves, and the ultrasonic waves are amplified and converted into corresponding receiving pulse signals through an amplifier (500) to be output;
s220, the waveform processor (600) receives the receiving pulse signal from the amplifier (500) and the transmitting control signal output by the time controller (100), and obtains the time corresponding to the receiving of different ultrasonic waves:
、
、……、
、
、
wherein n is more than or equal to 2, and the lengths of the 1 st pipe section, the 2 nd pipe section, the … … and the n-th pipe section of the corresponding ultrasonic probe pipe (700) are determined according to the lengths
、
、……、
、
、
And calculating the nuclear reactor vessel level based on the equation>
：
If n =2, the number of the bits is greater than or equal to 2,
=
-
*(
-
)/
；
if n is more than or equal to 3,
wherein, in the process,
，
，
=0。
10. a method of measuring nuclear reactor vessel level as claimed in claim 9, wherein the waveform processor (600) is calculating the nuclear reactor vessel level
And then displayed through the display (800). />
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| CN111238604B (en) * | 2020-01-14 | 2022-04-29 | 湖北楚禹水务科技有限公司 | Acoustic wave water level gauge, water level detection method, electronic device, and storage medium |
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| JPH07151894A (en) * | 1993-11-26 | 1995-06-16 | Toshiba Corp | Apparatus and method for measuring nuclear reactor power |
| CN101097161A (en) * | 2006-06-30 | 2008-01-02 | 北京奥麦特科技有限公司 | Device for ultrasonic measuring liquid level and method thereof |
| JP2011180052A (en) * | 2010-03-03 | 2011-09-15 | Toshiba Corp | Reactor water-level meter and method of measuring reactor water level |
| CN105987737A (en) * | 2015-02-13 | 2016-10-05 | 中国科学院声学研究所 | Ultrasonic liquid level detector and detection method |
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| JPH05273033A (en) * | 1992-03-26 | 1993-10-22 | Toshiba Corp | Water level measuring apparatus for nuclear reactor |
| JPH07151894A (en) * | 1993-11-26 | 1995-06-16 | Toshiba Corp | Apparatus and method for measuring nuclear reactor power |
| CN101097161A (en) * | 2006-06-30 | 2008-01-02 | 北京奥麦特科技有限公司 | Device for ultrasonic measuring liquid level and method thereof |
| JP2011180052A (en) * | 2010-03-03 | 2011-09-15 | Toshiba Corp | Reactor water-level meter and method of measuring reactor water level |
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