CN112858376B - Method for measuring content of dissolved hydrogen in primary loop of reactor - Google Patents
Method for measuring content of dissolved hydrogen in primary loop of reactor Download PDFInfo
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- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 title claims abstract description 165
- 239000001257 hydrogen Substances 0.000 title claims abstract description 165
- 229910052739 hydrogen Inorganic materials 0.000 title claims abstract description 165
- 238000000034 method Methods 0.000 title claims abstract description 38
- 239000002826 coolant Substances 0.000 claims abstract description 66
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims abstract description 45
- 239000001307 helium Substances 0.000 claims abstract description 42
- 229910052734 helium Inorganic materials 0.000 claims abstract description 42
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims abstract description 33
- 238000005259 measurement Methods 0.000 claims abstract description 28
- 239000007791 liquid phase Substances 0.000 claims abstract description 17
- 239000007789 gas Substances 0.000 claims abstract description 16
- 229910052757 nitrogen Inorganic materials 0.000 claims abstract description 13
- 241000277275 Oncorhynchus mykiss Species 0.000 claims abstract description 8
- 239000000126 substance Substances 0.000 claims description 12
- 229910001873 dinitrogen Inorganic materials 0.000 claims description 7
- 239000012528 membrane Substances 0.000 claims description 3
- 230000035699 permeability Effects 0.000 claims description 3
- 238000010926 purge Methods 0.000 claims description 2
- 238000004458 analytical method Methods 0.000 abstract description 7
- 150000002431 hydrogen Chemical class 0.000 abstract description 5
- 230000035945 sensitivity Effects 0.000 abstract description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 13
- 229910000831 Steel Inorganic materials 0.000 description 3
- 238000001514 detection method Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000003908 quality control method Methods 0.000 description 3
- 239000010959 steel Substances 0.000 description 3
- 230000009897 systematic effect Effects 0.000 description 3
- KDLHZDBZIXYQEI-UHFFFAOYSA-N Palladium Chemical compound [Pd] KDLHZDBZIXYQEI-UHFFFAOYSA-N 0.000 description 2
- 230000000737 periodic effect Effects 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 238000004587 chromatography analysis Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 238000011010 flushing procedure Methods 0.000 description 1
- 238000004817 gas chromatography Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000000691 measurement method Methods 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 229910052763 palladium Inorganic materials 0.000 description 1
- 238000004064 recycling Methods 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 238000001179 sorption measurement Methods 0.000 description 1
- 239000002351 wastewater Substances 0.000 description 1
- 238000004065 wastewater treatment Methods 0.000 description 1
Classifications
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N25/00—Investigating or analyzing materials by the use of thermal means
- G01N25/18—Investigating or analyzing materials by the use of thermal means by investigating thermal conductivity
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N30/00—Investigating or analysing materials by separation into components using adsorption, absorption or similar phenomena or using ion-exchange, e.g. chromatography or field flow fractionation
- G01N30/02—Column chromatography
-
- 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
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
-
- 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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- Biochemistry (AREA)
- Analytical Chemistry (AREA)
- Pathology (AREA)
- Immunology (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Chemical & Material Sciences (AREA)
- General Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
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- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a method for measuring the content of dissolved hydrogen in a primary loop of a reactor, which comprises the following steps: s1, respectively installing a flowmeter and a pressure gauge on an inlet and an outlet of a flow cell of a portable hydrogen analyzer, and calibrating; s2, connecting the portable hydrogen analyzer in a reactor loop, and connecting a gas supply steel head of the portable hydrogen analyzer with a nitrogen supply system; s3, enabling the coolant in the first loop of the reactor to enter the flow cell through the inlet and return to the first loop of the reactor through the outlet; s4, the portable hydrogen analyzer is used for measuring the coolant to obtain the total content of hydrogen and helium in the coolant; s5, subtracting the content of helium in the coolant, which is measured in advance through a gas-liquid phase separator, from the total content of hydrogen and helium to obtain the content of hydrogen in the coolant. The invention realizes the online continuous measurement of the content of the dissolved hydrogen in the loop coolant of the reactor, improves the accuracy, stability and sensitivity of the measurement of the content of the dissolved hydrogen, reduces the irradiation dose of personnel during the analysis of the dissolved hydrogen, and improves the working efficiency.
Description
Technical Field
The invention relates to the technical field of reactor water quality analysis, in particular to a method for measuring the content of dissolved hydrogen in a primary loop of a reactor.
Background
The dissolved hydrogen content in the primary coolant must be controlled to a certain extent during the operation of the pressurized water reactor, as specified by the water chemistry specifications of the nuclear power plant. Under the power operation and cold shutdown modes, the proper hydrogen content can not only effectively inhibit the irradiation decomposition of the primary circuit water, but also prevent the hydrogen embrittlement effect of the nuclear fuel zirconium alloy, and simultaneously prevent the corrosion of the primary circuit pressure boundary material. Accurate measurement of dissolved hydrogen concentration in reactor-loop coolant is a precondition and necessary condition for tracking and adjusting hydrogen concentration, and is closely related to safe operation of nuclear power plants.
The measurement methods of dissolved hydrogen in a pressurized water reactor loop mainly comprise three methods: by means of a decanter and a gas-liquid phase separator chromatography of gas chromatography, the method has accurate measurement and traceable source, but is complex to operate; an on-line instrument based on the principle of hydrogen adsorption of a metal palladium electrode, wherein the instrument electrode needs frequent regeneration and flushing and has slow response and extremely low reliability; the thermal conductivity type hydrogen analyzer is portable and online, wherein online hydrogen analyzers are less common, and the portable hydrogen analyzer is applied to most nuclear power plants. Although the portable hydrogen analyzer has reports about the use mode, common problems and solutions thereof, the influence of a plurality of different water chemistry conditions on the measurement of a single-circuit coolant is not studied in detail, so that the problems of complex operation, waste of the coolant, lower accuracy of the measurement result and the like exist in the actual use process.
The water chemistry conditions affecting the measurement result mainly include: sample water flow through the portable hydrogen analyzer; measuring back pressure of the portable hydrogen analyzer; the interference of various interference gases in the coolant on the detection of dissolved hydrogen; hydrogen analyzer system errors.
The low accuracy of the traditional method is mainly reflected in that the interference of the interference gas in the loop coolant on the detection of the dissolved hydrogen is not considered, and the interference of helium gas on the measurement result of the dissolved hydrogen is not evaluated and compensated.
The complex operation of the traditional method is mainly characterized in that: the purging nitrogen used by the hydrogen analyzer in the traditional method is sourced from a cylinder of the hydrogen analyzer, the cylinder has small volume and needs to be inflated regularly by using an external high-pressure nitrogen steel cylinder, the inflation process is complex, and the safety risk exists in the use process of the high-pressure nitrogen; the traditional method only uses pure hydrogen gas to calibrate the portable hydrogen analyzer, and does not consider the influence of other gases on the hydrogen measurement result, and an external high-pressure hydrogen steel cylinder is required to be used for the pure hydrogen gas calibration, so that the operation is dangerous and complex.
Coolant is wasted mainly because: when the traditional method uses the hydrogen analyzer, the primary loop coolant sample water flowing through the reactor of the hydrogen analyzer is directly discharged to the air and then is discharged into a wastewater treatment system as chemical wastewater, and the primary loop coolant is not directly recycled.
Disclosure of Invention
The invention aims to provide a method for measuring the content of dissolved hydrogen in a reactor loop for realizing on-line continuous measurement.
The technical scheme adopted for solving the technical problems is as follows: the method for measuring the content of the dissolved hydrogen in a first loop of the reactor comprises the following steps:
s1, respectively installing a flowmeter and a pressure gauge on an inlet and an outlet of a flow cell of a portable hydrogen analyzer, and calibrating the portable hydrogen analyzer;
s2, connecting the portable hydrogen analyzer in a reactor loop, and connecting a gas supply steel head of the portable hydrogen analyzer with a nitrogen supply system of a nuclear island;
s3, enabling the coolant in the first loop of the reactor to enter the flow cell through the inlet and return to the first loop of the reactor through the outlet;
s4, the portable hydrogen analyzer is used for measuring the accessed coolant to obtain the total content of hydrogen and helium in the coolant;
s5, subtracting the content of helium in the coolant, which is measured in advance through a gas-liquid phase separator, from the total content of hydrogen and helium in the obtained coolant to obtain the content of hydrogen in the coolant.
Preferably, in step S2, the outlet of the flow cell is connected to a chemical volume control system of a reactor loop through a quick connector.
Preferably, in step S2, one end of the pressure reducing valve is connected to the gas supply steel head of the portable hydrogen analyzer through a hose, and the other end is connected to the nitrogen gas supply system of the nuclear island through a quick connector.
Preferably, in step S4, the portable hydrogen analyzer is purged with nitrogen by supplying nitrogen through a nitrogen supply system at the time of measurement.
Preferably, in step S3, the coolant in the flow cell flows out to the control tank of the chemical and volumetric control system through the outlet, and then returns to the primary reactor loop.
Preferably, in step S3, the outlet of the flow cell is connected to a control box of the chemical and volume control system through a quick connector.
Preferably, in step S3, the flow rate of the coolant entering the flow cell is controlled to be more than or equal to 200mL/min.
Preferably, the algorithm of step S5 is obtained by the following method:
the portable hydrogen analyzer uses a thermal conductivity detector, and the measurement result is represented by the following formula (1):
[H 2 ] M ＝[H 2 ] T +k×[He]+c (1)
in the formula, [ H ] 2 ] M For the hydrogen content measured by the portable hydrogen analyzer, [ H ] 2 ] T And [ He ]]The contents of hydrogen and helium measured by the gas-liquid phase separator are respectively, k is a helium compensation coefficient, and c is a system error;
under the condition that the electrode semipermeable membrane of the portable hydrogen analyzer has the same selective permeability to hydrogen and helium, k is expressed as: k=λh2/λ He The method comprises the steps of carrying out a first treatment on the surface of the Wherein λH2 is the thermal conductivity of hydrogen, λ He Is the thermal conductivity of helium; at 25 ℃, k=0.88;
according to the formula (1), the actual values of k and c are calculated according to the content of dissolved hydrogen when the concentration of helium in a loop coolant is different, the value of k is 1.0, and c is not more than 1.23mL/kg, so that the response of the portable hydrogen analyzer to hydrogen and helium is the same, and the system error is small, and therefore the content of hydrogen in the coolant is obtained by subtracting the content of helium in the coolant measured by the gas-liquid phase separator from the total content of hydrogen and helium in the coolant measured by the portable hydrogen analyzer.
According to the method for measuring the content of the dissolved hydrogen in the first loop of the reactor, disclosed by the invention, the online continuous measurement of the content of the dissolved hydrogen in the coolant in the first loop of the reactor is realized through the portable hydrogen analyzer, and the coolant is returned to the first loop after being measured, so that the recycling is realized; the accuracy, stability and sensitivity of measuring the content of the dissolved hydrogen in the loop coolant are improved, the irradiation dose of personnel during the analysis of the dissolved hydrogen is reduced, the working efficiency is improved, and the chemical analysis personnel are protected.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a flow chart of a method for determining the dissolved hydrogen content of a primary loop of a reactor according to the present invention;
fig. 2 is a schematic structural view of a portable hydrogen analyzer according to the present invention.
Detailed Description
For a clearer understanding of technical features, objects and effects of the present invention, a detailed description of embodiments of the present invention will be made with reference to the accompanying drawings.
Referring to fig. 1 and 2, a method for determining the content of dissolved hydrogen in a first loop of a reactor according to an embodiment of the present invention includes the following steps:
s1, a flowmeter 20 is arranged at the inlet or the outlet of the flow cell of the portable hydrogen analyzer 10.
The flow meter 20 is used to monitor the flow of coolant into the flow cell; preferably, the flow meter 20 is mounted at the inlet of the flow cell.
A pressure gauge 30 is fitted at the outlet of the flow cell for monitoring the pressure.
After the flowmeter 20 and the pressure gauge 30 are installed, the portable hydrogen analyzer 10 is calibrated. The portable hydrogen analyzer can be calibrated by using a pure hydrogen gas calibration method, and can also be directly calibrated manually by using the dissolved hydrogen measurement result of the gas-liquid phase separator.
S2, connecting the portable hydrogen analyzer 10 in a reactor-loop, and connecting a gas supply steel head of the portable hydrogen analyzer 10 with a nitrogen supply system (RAZ) of the nuclear island.
Wherein the portable hydrogen analyzer 10 is connected to a corresponding passage in the reactor-loop for accessing the coolant to the flow cell, depending on the hydrogen content in the coolant to be measured. The outlet of the flow cell is connected with the chemical volume control system of the first loop of the reactor through the quick connector 40, so that the measured coolant is discharged from the outlet of the flow cell to the chemical volume control system to be discharged back to the first loop of the reactor for reuse, and waste is avoided.
The pressure gauge 30 is located on the connection line between the quick connector 40 and the outlet of the flow cell and monitors the back pressure of the portable hydrogen analyzer 10 to maintain a steady state.
The gas supply steel head of the portable hydrogen analyzer 10 is connected to a nitrogen gas supply system (RAZ) through a pressure reducing valve 50. Further, one end of the pressure reducing valve 50 is connected to a gas supply steel head of the portable hydrogen analyzer 10 through a hose 60, and the other end is connected to a nitrogen gas supply system of the nuclear island through a quick connector 70. The nitrogen gas supply system continuously supplies nitrogen gas to the portable hydrogen analyzer 10, eliminating the cumbersome operation of periodically charging the portable hydrogen analyzer 10 cylinder with an external high-pressure nitrogen gas cylinder.
And S3, the coolant of the first loop of the reactor enters the flow cell of the portable hydrogen analyzer 10 through an inlet, and returns to the first loop of the reactor through an outlet.
Since the sample water flow rate has an important influence on the measurement result of dissolved hydrogen, the flow rate influence characteristics of the portable hydrogen analyzer 10 are as follows: when the sample water flow is smaller than 200mL/min, the measurement result is greatly increased along with the increase of the sample water flow; when the flow rate is increased to 200-500 mL/min, the measurement result is stable. Therefore, in order to reduce the influence of the flow rate variation on the measurement of dissolved hydrogen, the sample water flow rate must not be lower than 200mL/min when the portable hydrogen analyzer 10 is in use.
According to the above conclusion, in combination with the flow meter 20 on the inlet of the flow cell, the flow rate of the coolant entering the flow cell is controlled to be equal to or more than 200mL/min.
In addition, the hydrogen solubility is related to the pressure, and the back pressure of the portable hydrogen analyzer 10 has a slight influence on the measurement result of dissolved hydrogen according to the test result, and the higher the pressure is, the larger the measured value is, so that the back pressure needs to be kept stable as much as possible during the measurement.
The outlet of the flow cell of the portable hydrogen analyzer 10 is connected to the control tank of the chemical and volume control system through a quick connector 40, and the coolant discharged from the outlet of the flow cell is first returned to the control tank of the chemical and volume control system and then to the reactor loop.
S4, the portable hydrogen analyzer 10 measures the accessed coolant to obtain the total content of hydrogen and helium in the coolant.
S5, subtracting the helium content in the coolant, which is measured in advance through a gas-liquid phase separator, from the total content of the hydrogen and the helium in the obtained coolant to obtain the content of the hydrogen in the coolant (namely the content of the dissolved hydrogen in the coolant).
Wherein the coolant measured by the gas-liquid phase separator and the coolant entering the portable hydrogen analyzer 10 are the same coolant in the same path in the reactor-loop.
In general, portable hydrogen analyzers are subject to interference gases when in use. Calculating the thermal conductivity (W (m.K)) of common gas in a reactor loop at 25 ℃ according to a gas thermal conductivity calculation formula 1 ) Respectively (H) 2 ，0.17064)、(He，0.15016)、(N 2 ，0.02475)、(O 2 0.02571), (Ar, 0.01795), (Xe, 0.00568), (Kr, 0.00946). Wherein O is 2 Ar, xe and Kr are less contained in the reactor-loop and have extremely low thermal conductivity, N 2 As background gases for hydrogen analyzers, they have negligible effect on dissolved hydrogen measurements. However, helium has a thermal conductivity and a molecular diameter similar to those of hydrogen, and when present in a large amount, affects the measurement result. Thus, the dissolved hydrogen and helium measurements from the gas-liquid phase separator can be used to evaluate and remove helium interference with dissolved hydrogen detection by the following method:
the portable hydrogen analyzer uses a thermal conductivity detector, and the measurement result can be expressed as the following formula (1):
[H 2 ] M ＝[H 2 ] T +k×[He]+c (1)
in the formula, [ H ] 2 ] M For the hydrogen content (i.e. dissolved hydrogen content) measured by the portable hydrogen analyzer, [ H ] 2 ] T And [ He ]]The contents of hydrogen and helium measured by the gas-liquid phase separator are respectively, k is a helium compensation coefficient, and c is a systematic error.
Under the same conditions of selective permeability of the electrode semipermeable membrane of the portable hydrogen analyzer to hydrogen and helium, k can be expressed as: k=λh2/λ He The method comprises the steps of carrying out a first treatment on the surface of the Wherein λH2 is the thermal conductivity of hydrogen, λ He Is the thermal conductivity of helium. At 25 ℃, k=0.88.
From equation (1), the actual values of k and c are calculated from the dissolved hydrogen content of the primary coolant at different helium concentrations, and the results are shown in Table 1. As can be seen from Table 1, the value of k is about 1.0, c is not more than 1.23mL/kg, i.e., the response of the portable hydrogen analyzer to hydrogen and helium is substantially the same, and the systematic error is small, so that the total content of hydrogen and helium in the coolant measured by the portable hydrogen analyzer can be subtracted from the content of helium in the coolant measured by the gas-liquid phase separator to obtain the content of hydrogen in the coolant.
TABLE 1 Compensation coefficient for dissolved helium and systematic error
In addition, the portable hydrogen analyzer 10 used in the present invention should also perform periodic calibration of the portable hydrogen analyzer 10 in order to maintain the measurement accuracy continuously; quality control checks are performed on the portable hydrogen analyzer 10 for assessing the stability and accuracy of the instrument analysis process.
The portable hydrogen analyzer can be calibrated by using a pure hydrogen gas calibration method, and when the hydrogen content in the primary loop coolant of the reactor is high, the portable hydrogen analyzer can also be directly calibrated manually by using the dissolved hydrogen measurement result of the gas-liquid phase separator. Because an external high-pressure hydrogen steel bottle is required to be used for calibrating the pure hydrogen gas, the operation is dangerous and complex, and the manual calibration process is simple and has no risk of hydrogen use by using the analysis result of the gas-liquid phase separator.
And (3) measuring the content of dissolved hydrogen by using a gas-liquid phase separator at regular intervals to be used as a quality control check basis of the portable hydrogen analyzer. Helium content analysis, periodic calibration, and quality control checks can be performed simultaneously.
The method for measuring the content of dissolved hydrogen in the primary loop coolant of the reactor has the advantages that the measuring working efficiency is obviously improved, and the irradiation dose of an analyst is greatly reduced; when the concentration of dissolved hydrogen in the coolant is 1.50-32.10 mL/kg, the measurement error is not more than 1.37mL/kg. After a single calibration, the portable hydrogen analyzer may be used for at least 2 months; the accuracy, stability and sensitivity are all better than that of DH1021 type hydrogen meter.
When the method is applied to normal power operation and overhaul start-stop period of the reactor, the measured value of the dissolved hydrogen is more accurate, sensitive and reliable, the control of the content of the dissolved hydrogen of the primary loop coolant of the nuclear power unit is facilitated, and the reactor is safer and more reliable to operate.
The foregoing description is only illustrative of the present invention and is not intended to limit the scope of the invention, and all equivalent structures or equivalent processes or direct or indirect application in other related technical fields are included in the scope of the present invention.
Claims (7)
1. A method for measuring the content of dissolved hydrogen in a first loop of a reactor, comprising the steps of:
s1, respectively installing a flowmeter and a pressure gauge on an inlet and an outlet of a flow cell of a portable hydrogen analyzer, and calibrating the portable hydrogen analyzer;
s2, connecting the portable hydrogen analyzer in a reactor loop, and connecting a gas supply steel head of the portable hydrogen analyzer with a nitrogen supply system of a nuclear island;
s3, enabling the coolant in the first loop of the reactor to enter the flow cell through the inlet and return to the first loop of the reactor through the outlet;
s4, the portable hydrogen analyzer is used for measuring the accessed coolant to obtain the total content of hydrogen and helium in the coolant;
s5, subtracting the content of helium in the coolant, which is measured in advance through a gas-liquid phase separator, from the total content of hydrogen and helium in the obtained coolant to obtain the content of hydrogen in the coolant, wherein the algorithm of the step S5 is obtained by the following method:
the portable hydrogen analyzer uses a thermal conductivity detector, and the measurement result is represented by the following formula (1):
[H 2 ] M ＝[H 2 ] T +k×[He]+c (1)
in the formula, [ H ] 2 ] M For the hydrogen content measured by the portable hydrogen analyzer, [ H ] 2 ] T And [ He ]]The contents of hydrogen and helium measured by the gas-liquid phase separator are respectively, k is a helium compensation coefficient, and c is a system error;
under the condition that the electrode semipermeable membrane of the portable hydrogen analyzer has the same selective permeability to hydrogen and helium, k is expressed as: k=λh 2 Lambda He; wherein lambda H 2 Is the thermal conductivity of hydrogen, λHe is the thermal conductivity of helium; at 25 ℃, k=0.88;
according to the formula (1), the actual values of k and c are calculated according to the content of dissolved hydrogen when the concentration of helium in a loop coolant is different, the value of k is 1.0, and c is not more than 1.23mL/kg, so that the response of the portable hydrogen analyzer to hydrogen and helium is the same, and the system error is small, and therefore the content of hydrogen in the coolant is obtained by subtracting the content of helium in the coolant measured by the gas-liquid phase separator from the total content of hydrogen and helium in the coolant measured by the portable hydrogen analyzer.
2. The method for determining the content of dissolved hydrogen in a first loop of a reactor according to claim 1, wherein in step S2, the outlet of the flow cell is connected to a chemical volume control system of the first loop of the reactor through a quick connector.
3. The method for measuring the content of dissolved hydrogen in a first loop of a reactor according to claim 1, wherein in the step S2, one end of a pressure reducing valve is connected with a gas supply steel head of the portable hydrogen analyzer through a hose, and the other end is connected with a nitrogen gas supply system of a nuclear island through a quick connector.
4. The method for measuring the content of the dissolved hydrogen in the first circuit of the reactor according to claim 3, wherein in the step S4, nitrogen is supplied to the portable hydrogen analyzer through a nitrogen supply system for nitrogen purging.
5. The method according to claim 1, wherein in step S3, the coolant in the flow cell flows out to a tank of a chemical and volumetric control system through the outlet and then returns to the reactor loop.
6. The method for determining the content of dissolved hydrogen in a first circuit of a reactor according to claim 5, wherein in step S3, the outlet of the flow cell is connected to a control box of the chemical and volume control system through a quick connector.
7. The method for measuring the content of dissolved hydrogen in a first loop of a reactor according to claim 1, wherein in the step S3, the flow rate of the coolant entering the flow cell is controlled to be equal to or more than 200mL/min.
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