WO2016091146A1 - 核电站安全壳内氢气浓度测量方法、装置及系统 - Google Patents

核电站安全壳内氢气浓度测量方法、装置及系统 Download PDF

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Publication number
WO2016091146A1
WO2016091146A1 PCT/CN2015/096603 CN2015096603W WO2016091146A1 WO 2016091146 A1 WO2016091146 A1 WO 2016091146A1 CN 2015096603 W CN2015096603 W CN 2015096603W WO 2016091146 A1 WO2016091146 A1 WO 2016091146A1
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Prior art keywords
hydrogen
containment
nuclear power
power plant
measuring
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English (en)
French (fr)
Inventor
肖洲
何大宇
董孝胜
许丹
刘智寅
吕爱国
付皓
刘路
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China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
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China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
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Publication of WO2016091146A1 publication Critical patent/WO2016091146A1/zh
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    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N27/00—Investigating or analysing materials by the use of electric, electrochemical, or magnetic means
    • G01N27/02—Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating impedance
    • G01N27/04—Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating impedance by investigating resistance
    • G01N27/14—Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating impedance by investigating resistance of an electrically-heated body in dependence upon change of temperature
    • G01N27/16—Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating impedance by investigating resistance of an electrically-heated body in dependence upon change of temperature caused by burning or catalytic oxidation of surrounding material to be tested, e.g. of gas
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention belongs to the technical field of nuclear power, and more particularly to a method, a device and a system for measuring hydrogen concentration in a containment of a nuclear power plant.
  • the existing hydrogen concentration monitoring program for serious accidents at nuclear power plants mainly includes the following two types:
  • One is a severe accident hydrogen concentration monitoring method using the principle of catalytic reaction.
  • a temperature sensor is disposed at the inlet and the outlet of the combustible gas recombiner, and the catalyzed reaction heat of the combustible gas recombiner, that is, the temperature difference between the inlet and outlet, is calculated and converted into a hydrogen concentration to achieve a serious accident.
  • the purpose of the hydrogen concentration Specifically, components that can withstand severe accidents (combustible gas recombiners and temperature sensors) are disposed in the containment, and measurement signals are transmitted through the signal wires to the processing cabinet outside the containment case for processing. Handle the cabinet outside the containment area in a non-harsh environment.
  • the method can only be used in an aerobic environment, and the failure is measured in an inert gas environment.
  • the catalytic reaction heat cannot truly reflect the hydrogen concentration, and is only applicable.
  • the method is indirect hydrogen concentration measurement, mainly measuring reaction heat, heat loss may occur in combustible gas recombiner, and the measured temperature difference may not be able to characterize hydrogen composite heat, reaction
  • the distance between the component and the catalytic reaction component affects the measurement accuracy, and the accuracy of the hydrogen concentration measurement cannot be guaranteed.
  • the other is a method for measuring the hydrogen concentration of severe accidents outside the containment of gas.
  • the gas of the containment vessel is pumped out to the gas measuring device outside the containment through a conduit (capillary or other pipeline), and the measuring device is less tolerable in the monitoring chamber after being cooled, depressurized, etc.
  • the hydrogen concentration monitoring device of the environmental condition measures the hydrogen concentration, and finally calculates the hydrogen concentration in the containment by calculating the compensation.
  • the sampling head and sampling line in the containment are resistant to severe accidents, and the sampling circuit has a back-sweep function to prevent the aerosol in the containment from clogging the sampling tube under severe accident conditions.
  • the measuring cabinet and the processing cabinet are located outside the containment.
  • the method uses the gas to be taken out of the containment to measure, after the temperature drop and the pressure drop measurement, the measured parameters are more difficult to accurately and accurately characterize the hydrogen concentration in the containment; at the same time, the method has the rupture of the sample line, further increasing the safety.
  • the leakage point of the shell extracts the radioactive gas in the containment outside the containment, which increases the risk of exposure to personnel outside the containment and is not safe.
  • the object of the invention is to provide an accurate, in the monitoring of hydrogen concentration in the containment of a nuclear power plant Hydrogen concentration measurement technology in a safe containment.
  • the present invention provides a method for measuring hydrogen concentration in a containment of a nuclear power plant, the method comprising:
  • the processing cabinet determines the hydrogen concentration in the containment of the nuclear power plant according to the collected conductivity signal and the pressure signal in the nuclear power plant containment.
  • the method further comprises:
  • the hydrogen measuring component is connected to the processing cabinet through a nuclear-grade cable, and the processing cabinet collects a conductivity signal after the hydrogen measuring component absorbs and releases hydrogen through the nuclear-grade cable.
  • the method further comprises:
  • the temperature measuring element measures the temperature value at which the hydrogen measuring member is located.
  • the processing cabinet determines the hydrogen concentration in the containment of the nuclear power plant according to the collected conductivity signal and the pressure signal in the containment of the nuclear power plant, including:
  • the processing cabinet determines the hydrogen concentration in the containment of the nuclear power plant according to the collected conductivity signal, the temperature value, and the pressure signal in the containment of the nuclear power plant.
  • the processing cabinet determines the hydrogen concentration in the containment of the nuclear power plant according to the collected conductivity signal, the temperature value, and the pressure signal in the containment of the nuclear power plant. include:
  • the pressure signal in the station containment determines the hydrogen concentration in the containment of the nuclear power plant.
  • the method further comprises:
  • the palladium silver alloy is plated on a high temperature resistant ceramic sheet.
  • the method further comprises:
  • the hydrogen measuring member outer casing is made of sintered stainless steel.
  • the method further comprises:
  • a protective cover for spraying against the spray liquid is further disposed above the hydrogen measuring component.
  • the present invention also provides a hydrogen concentration measuring device in a nuclear power plant containment, which is disposed in a nuclear power plant containment, the device comprising:
  • a transmission unit configured to transmit the conductivity signal of the probe to the processing cabinet, so that the processing cabinet determines the hydrogen concentration in the containment of the nuclear power plant according to the conductivity signal and the pressure signal in the nuclear power plant containment.
  • the device further comprises:
  • a heating element for heating the probe to bring the probe to a constant temperature state.
  • the device further includes: a temperature measuring element that measures a temperature value of the position where the probe is located.
  • the device further comprises:
  • a shield to prevent the spray from contacting the probe.
  • the transmission unit Transmitting the conductivity signal of the probe to the processing cabinet includes:
  • the transmission unit transmits the conductivity signal of the probe to the electrical penetration of the containment through the nuclear grade cable, and then leads from the electrical penetration to the processing cabinet outside the containment through the other end cable outside the containment.
  • the probe is specifically formed by plating a palladium silver alloy on a high temperature resistant ceramic sheet.
  • the probe further comprises:
  • the device further comprises:
  • a hydrogen measuring assembly housing is disposed over the probe plated with a palladium silver alloy film and the heating element.
  • the present invention also provides a hydrogen concentration measuring system in a nuclear power plant containment, the system comprising: a hydrogen measuring component for detecting hydrogen in a safety shell of the nuclear power plant;
  • the hydrogen measuring component is installed in the nuclear power plant containment, and the outer surface is plated with a palladium silver alloy film.
  • the hydrogen measuring component is connected to the processing cabinet through a nuclear-grade cable, and the processing cabinet collects the conductivity signal after the hydrogen measuring component absorbs and releases hydrogen through the nuclear-grade cable.
  • the system further comprises:
  • the heating element is installed in the nuclear power plant containment for keeping the hydrogen measuring component at a constant temperature.
  • the system further comprises: a temperature measuring component installed in the nuclear power plant containment for measuring the temperature value of the position where the hydrogen measuring component is located.
  • the system further comprises:
  • a shield for preventing the spray liquid from contacting the hydrogen measuring component.
  • the processing cabinet collects the conductivity signal after the hydrogen measuring component absorbs and releases hydrogen, and according to the collected conductivity signal and the inside of the nuclear power plant containment
  • the pressure signal determines the hydrogen concentration in the containment of the nuclear power plant, including:
  • the processing cabinet determines the hydrogen concentration in the containment of the nuclear power plant according to the collected conductivity signal, the temperature value, and the pressure signal in the containment of the nuclear power plant.
  • the hydrogen measuring unit is connected to the nuclear grade cable through a cable plug connector.
  • the processing cabinet collects the conductivity signal after the hydrogen measuring component absorbs and releases hydrogen, and further includes:
  • the method, device and system for measuring hydrogen concentration in the containment of the nuclear power plant of the present invention have the following beneficial technical effects: the conductivity signal of the hydrogen measuring component plated with the palladium-silver alloy film is disposed in the safety shell of the nuclear power plant through the processing cabinet.
  • the temperature signal in the containment of the nuclear power plant and the pressure signal can be used to measure the hydrogen concentration in the containment of the nuclear power plant.
  • Hydrogen can be achieved in both aerobic and anaerobic environments
  • the concentration measurement can be used in a wide range; at the same time, it can be applied to the measurement of hydrogen concentration in high temperature, high pressure and high irradiation environments, which can well overcome the influence of harsh environment on hydrogen concentration measurement.
  • the implementation method is simple and easy, and achieves good technical results.
  • Figure 1A provides an existing solution for a method for measuring hydrogen concentration in a containment of a nuclear power plant.
  • Figure 1B provides yet another prior embodiment of a method for measuring hydrogen concentration in a containment of a nuclear power plant.
  • Fig. 2 is a flow chart showing an example of a method for measuring hydrogen concentration in a containment of a nuclear power plant according to the present invention.
  • Fig. 4 is a view showing an example of a hydrogen concentration measuring system in the containment of the nuclear power plant of the present invention.
  • Fig. 5 is a view showing still another example of the hydrogen concentration measuring system in the containment of the nuclear power plant of the present invention.
  • FIG. 2 Please refer to FIG. 2 in combination with FIG. 2, which provides a method for measuring the hydrogen concentration in the containment of a nuclear power plant. specific:
  • step 201 a hydrogen gas measuring member plated with a palladium silver alloy film is disposed in the nuclear power plant containment.
  • a hydrogen gas measuring member plated with a palladium silver alloy film is disposed in the nuclear power plant containment.
  • the hydrogen in the containment of the nuclear power plant is detected by a hydrogen measuring component.
  • the hydrogen measuring member may be composed of a carrier and a filamentous metal film on the carrier.
  • the metal film is made of a palladium-silver alloy, and the palladium-silver alloy has a property that the internal hydrogen molecules change their electrical conductivity after absorbing or releasing hydrogen gas in the mixed gas.
  • Step 203 The processing cabinet collects a conductivity signal after the hydrogen measuring component absorbs and releases hydrogen.
  • the hydrogen measuring component is connected to the processing cabinet through the nuclear grade cable, and the processing cabinet collects the conductivity signal after the hydrogen measuring component absorbs and releases the hydrogen through the nuclear grade cable.
  • the hydrogen measuring component is connected to the nuclear grade cable through a cable plug connector, and transmits the conductivity signal to the electrical penetration of the nuclear power plant containment, and the electrical penetration transmits the conductivity signal to the processing cabinet through the cable.
  • the hydrogen measuring component transmits electrical signals to the electrical penetration of the containment through a nuclear grade cable that withstands severe environmental conditions, and then the other end of the containment cable is routed from the electrical penetration to the processing cabinet outside the containment.
  • the safety shell is equipped with a nuclear grade cable that is resistant to serious accidents.
  • the insulation material inside the cable is made of high temperature resistant and radiation resistant insulation material.
  • the heating element is used to bring the hydrogen gas measuring member to a constant temperature state.
  • the electrical conductivity of the palladium-silver alloy decreases above about 150 ° C with increasing temperature, while the conductivity of the palladium - silver alloy is substantially unaffected by temperature at a certain temperature, and the effect of the combined temperature on the measured value ensures hydrogen measurement.
  • the part is at a constant temperature.
  • the temperature measuring element measures a temperature value at a position where the hydrogen measuring part is located.
  • the measured temperature values are used to compensate for the palladium silver alloy measurements.
  • Step 205 The processing cabinet determines the hydrogen concentration in the containment of the nuclear power plant according to the collected conductivity signal and the pressure signal in the nuclear power plant containment.
  • the processing cabinet outside the containment receives the conductivity signal and temperature value of the palladium-silver alloy, it is compensated by a special algorithm, and temperature compensation is introduced into the algorithm.
  • the measured hydrogen concentration is the volume concentration, measured The volume concentration is greatly affected by the pressure of the environment, so in the processing device part, the external containment pressure signal is received to compensate the measurement output and improve the accuracy.
  • the final calculated hydrogen concentration characterizes the hydrogen concentration in the containment and takes into account the effects of temperature and pressure within the containment.
  • the hydrogen concentration measurement in the containment of the nuclear power plant can be realized by processing the cabinet to collect the conductivity signal of the hydrogen measuring component plated with the palladium-silver alloy film in the safety shell of the nuclear power plant and the pressure signal in the safety shell of the nuclear power plant. It can realize the measurement of hydrogen concentration in aerobic and anaerobic environments, and it can be used in a wide range. At the same time, it can be applied to the measurement of hydrogen concentration under high temperature, high pressure and high irradiation environment. It is very good for customer service. influences.
  • FIG. 3 provides a schematic diagram of an embodiment of a hydrogen concentration measuring device in a containment of a nuclear power plant.
  • the device is disposed within the nuclear power plant containment and includes a probe 301 and a transfer unit 303. among them,
  • the probe 301 is plated with a palladium-silver alloy film for absorbing hydrogen gas in the containment of the nuclear power plant.
  • the ability of the palladium-silver alloy to absorb and release hydrogen reaches an equilibrium state, and the conductivity of the palladium-silver alloy is proportional to the hydrogen concentration.
  • the transmission unit 303 is configured to transmit the conductivity signal of the probe 301 to the processing cabinet, so that the processing cabinet determines the hydrogen concentration in the nuclear power plant containment according to the conductivity signal and the pressure signal in the nuclear power plant containment.
  • the apparatus further includes a heating element for heating the probe 301 to bring the probe to a constant temperature state.
  • the conductivity of the palladium-silver alloy is proportional to the hydrogen concentration. At a certain temperature, the ability of the palladium-silver alloy to absorb and release hydrogen will reach equilibrium and the resistance response will be faster.
  • the conductivity of palladium-silver alloy decreases with temperature above about 150 °C, while the conductivity of palladium-silver alloy is not affected by temperature at a certain temperature. The effect of combined temperature on the measured value increases in the hydrogen measurement module.
  • the heating element is used to ensure that the probe 301 is at a constant temperature.
  • the device further includes a temperature measuring element that measures the temperature value of the position where the probe 301 is located.
  • the probe includes a temperature measuring component that is resistant to serious accidents, and the measured temperature value is used to compensate for the palladium-silver alloy measurement. Measured value.
  • the device further includes a shield for preventing the spray liquid from contacting the probe 301.
  • the probe 301 is specifically formed by plating a palladium silver alloy on a high temperature resistant ceramic sheet. Outside the probe 301 is a casing made of sintered stainless steel.
  • the measurement of the hydrogen concentration in the safety shell of the nuclear power plant can be realized by processing the cabinet to collect the conductivity signal of the probe plated with the palladium-silver alloy film in the safety shell of the nuclear power plant and the pressure signal in the safety shell of the nuclear power plant.
  • FIG. 4 provides a schematic diagram of an embodiment of a hydrogen concentration measurement system in a containment of a nuclear power plant.
  • the hydrogen measurement unit 401 and the processing cabinet 403 are included. specific:
  • the hydrogen measuring unit 401 is configured to detect hydrogen in the containment of the nuclear power plant.
  • the ability of the palladium-silver alloy to absorb and release hydrogen reaches an equilibrium state, and the conductivity of the palladium-silver alloy is proportional to the hydrogen concentration.
  • the ability of certain forms of palladium-silver alloy to absorb and release hydrogen will reach an equilibrium state faster, and the conductivity of palladium-silver alloy is proportional to the hydrogen concentration.
  • a hydrogen gas measuring member 401 plated with a palladium silver alloy film is disposed in the nuclear power plant containment. The hydrogen in the containment of the nuclear power plant is absorbed by the hydrogen measuring unit 401.
  • the hydrogen measuring member 401 may be composed of a carrier and a filamentous metal film on the carrier.
  • the metal film is made of a palladium-silver alloy, and the palladium-silver alloy has a property that the internal hydrogen molecules change their electrical conductivity after absorbing or releasing hydrogen gas in the mixed gas.
  • the processing cabinet 403 is configured to collect the conductivity signal after the hydrogen measuring component absorbs the released hydrogen gas, and determine the hydrogen concentration in the safety shell of the nuclear power plant according to the collected conductivity signal and the pressure signal in the nuclear power plant containment.
  • the hydrogen measuring component 401 is connected to the processing cabinet through a nuclear-grade cable, and the processing cabinet 403 collects the conductivity signal after the hydrogen gas measuring component 401 absorbs the hydrogen gas through the nuclear-grade cable.
  • the hydrogen measuring unit 401 is connected to the nuclear grade cable through a cable plug connector.
  • the hydrogen measuring component 401 is connected to the nuclear grade cable through a cable plug connector to transmit the conductivity signal to On the electrical penetration of the nuclear power plant containment, the electrical penetration transmits the conductivity signal through the cable to the processing cabinet 403.
  • the hydrogen measuring component 401 transmits an electrical signal to the electrical penetration of the containment through a nuclear grade cable that withstands severe environmental conditions, and then the other end of the containment cable is routed from the electrical penetration to the processing cabinet 403 outside the containment.
  • the safety shell is equipped with a nuclear grade cable that is resistant to serious accidents.
  • the insulation material inside the cable is made of high temperature resistant and radiation resistant insulation material.
  • the hydrogen concentration measurement in the containment of the nuclear power plant can be realized by processing the cabinet to collect the conductivity signal of the hydrogen measuring component plated with the palladium-silver alloy film in the safety shell of the nuclear power plant and the pressure signal in the safety shell of the nuclear power plant.
  • FIG. 5 provides a schematic diagram of an embodiment of a hydrogen concentration measurement system in a containment of a nuclear power plant.
  • the utility model comprises a hydrogen measuring component 501, a processing cabinet 503, a temperature measuring component 507, a protective cover 509 and a hydrogen measuring component outer casing 511. among them:
  • the hydrogen measuring unit 501 is configured to absorb hydrogen in the containment of the nuclear power plant.
  • a hydrogen gas measuring member 501 plated with a palladium silver alloy film is disposed in the nuclear power plant containment.
  • the hydrogen in the containment of the nuclear power plant is absorbed by the hydrogen measuring unit 501.
  • the hydrogen measuring part 501 may be composed of a carrier and a filamentous metal film on the carrier.
  • the metal film is made of a palladium-silver alloy, and the palladium-silver alloy has a characteristic of releasing hydrogen from the mixed gas, and extracts a pure hydrogen concentration from the mixed gas.
  • the hydrogen measuring part 501 may be composed of a carrier and a metal film on the carrier.
  • the metal film is made of a palladium-silver alloy, and the palladium-silver alloy has a characteristic of measuring the hydrogen concentration by absorbing and releasing hydrogen from the mixed gas.
  • the correspondence ratio of palladium-silver alloy in different mixing ratios will be different under hydrogen concentration, and palladium will be overabsorbed.
  • the hydrogen content in pure palladium solid phase cannot form a good linear relationship with hydrogen partial pressure.
  • a suitable ratio of palladium silver composition will form a good linear relationship, and the solid phase hydrogen content is proportional to the conductivity, so that the hydrogen partial pressure and the conductivity form a good linear relationship.
  • the processing cabinet 503 is configured to collect the conductivity signal after the hydrogen measuring component 501 absorbs the released hydrogen, and determine the hydrogen concentration in the safety shell of the nuclear power plant according to the collected conductivity signal and the pressure signal in the nuclear power plant containment.
  • the hydrogen measuring component 501 is connected to the processing cabinet 503 through a nuclear-grade cable or a severely-resistant cable, and the processing cabinet 503 collects the conductivity signal after the hydrogen-releasing component 501 absorbs the hydrogen by the nuclear-grade cable.
  • the hydrogen measuring component 501 is connected to the nuclear-grade cable through a cable plug connector, and transmits the conductivity signal to the electrical penetration of the nuclear power plant containment, and the electrical penetration transmits the conductivity signal to the processing cabinet through the cable. 503.
  • the hydrogen measuring component 501 transmits an electrical signal to the electrical penetration of the containment through a nuclear grade cable that withstands severe environmental conditions, and then the other end of the containment cable is routed from the electrical penetration to the processing cabinet 503 outside the containment.
  • the safety shell is equipped with a nuclear grade cable that is resistant to serious accidents.
  • the insulation material inside the cable is made of high temperature resistant and radiation resistant insulation material.
  • a heating element 505 is mounted within the nuclear power plant containment for maintaining the hydrogen measuring component at a constant temperature.
  • the hydrogen measuring member 501 is placed in a constant temperature state using the heating element 505. Specifically, the electrical conductivity of the palladium-silver alloy decreases above about 150 ° C with increasing temperature, while the conductivity of the palladium - silver alloy is substantially unaffected by temperature at a certain temperature, and the effect of the combined temperature on the measured value is used to ensure The hydrogen measuring part 501 is at a constant temperature.
  • the temperature measuring element 507 is installed in the nuclear power plant containment for measuring the temperature value of the position where the hydrogen measuring component is located.
  • the temperature measuring element 507 measures the temperature value of the position at which the hydrogen measuring part 501 is located.
  • the measured temperature values are used to compensate for the palladium silver alloy measurements.
  • a shield 509 is provided for preventing the spray liquid from contacting the hydrogen gas measuring component.
  • a hydrogen measuring assembly housing 511 is placed over the probe plated with a palladium silver alloy film and above the heating element. That is, the cover is above the measurement hydrogen measuring part 501. It can prevent the external aerosol from entering the surface of the covered palladium-silver alloy to affect the measurement effect. Also added anti-spray measures for the protective cover to prevent the influx from entering, affecting Measurement results.
  • the compensation is calculated by a special algorithm, and temperature compensation is introduced into the algorithm.
  • the measured hydrogen concentration is the volume concentration, and the measured volume concentration is greatly affected by the pressure of the environment. Therefore, in the processing device portion, the external containment pressure signal is received to compensate the measurement output and improve the accuracy.
  • the final calculated hydrogen concentration characterizes the hydrogen concentration in the containment and takes into account the effects of temperature and pressure within the containment.
  • the present invention has at least the following beneficial technical effects: collecting a conductivity signal of a hydrogen measuring component plated with a palladium-silver alloy film in a nuclear power plant containment through a processing cabinet and
  • the pressure signal in the containment of the nuclear power plant can be used to measure the hydrogen concentration in the containment of the nuclear power plant. It can realize the measurement of hydrogen concentration in aerobic and anaerobic environments, and it can be used in a wide range. At the same time, it can be applied to the measurement of hydrogen concentration under high temperature, high pressure and high irradiation environment. It is very good for customer service. influences.
  • the implementation method is simple and easy, and achieves good technical results.

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Abstract

一种核电站安全壳内氢气浓度测量方法和相应的测量装置和系统，该方法包括：在核电站安全壳内设置镀有钯银合金膜的氢气测量部件（501）；处理机柜（503）采集氢气测量部件（501）吸收释放氢气后的电导率信号；处理机柜（503）根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。该核电站安全壳内氢气浓度测量方法可实现安全、精确的核电站安全壳内氢气浓度测量。

Description

核电站安全壳内氢气浓度测量方法、装置及系统 技术领域
本发明属于核电技术领域，更具体地说，本发明涉及一种核电站安全壳内氢气浓度测量方法、装置及系统。
背景技术
核电站在发生严重事故时，安全壳内会产生大量的氢气，氢气的爆炸会威胁核电站安全屏障的完整性。核电厂事故工况下会产生大量氢气，氢气的来源：事故早期，锆-水反应高速率地产生氢气；事故中后期，水的辐照分解、堆芯融溶物和混凝土的反应，也会产生大量氢气。大量氢气的聚集使安全壳内氢气浓度有超过爆炸限4％的可能，存在爆炸的危险。为避免氢爆燃事故发生，破坏安全壳完整性，需要构建氢气测量系统对安全壳不同位置的氢气聚集状态进行监测，在事故发生后实施有效地干预。
由于事故工况下安全壳内气体呈现高温、高压、高放射性的特点，因此对于氢气浓度的测量增加了很大的难度。因此核电站需要有一套用于严重事故氢气浓度测量的方法，但是安全壳内在严重事故时环境条件通常较为恶劣，如高温、高压、高辐照等恶劣环境，不利于操作人员对事故的连续监测，较难以有效的方式监测氢气浓度。
现有核电站严重事故氢气浓度监测方案主要包括以下两种：
一种是利用催化反应原理的严重事故氢气浓度监测方法。如图1A所示，在可燃气体复合器的入口和出口设置温度传感器，通过测量可燃气体复合器催化反应热，即进出口温度差，通过计算转化为氢气浓度，从而达到监测严重事故 氢气浓度的目的。具体的，将能耐受严重事故的部件(可燃气体复合器和温度传感器)布置在安全壳内，测量信号通过信号线远传至安全壳外的处理机柜进行处理。处理机柜处于非恶劣环境的安全壳外区域。该方法由于采用可燃气体复合器为催化元件，只有在有氧的环境才能使用，在惰性气体环境测量失效，在高氢气浓度、氧气不足的环境下，催化反应热无法真实反映氢气浓度，只适用于用于低氢气浓度的有氧环境氢气浓度测量；同时，该方法为间接氢气浓度测量，主要测量反应热，可燃气体复合器可能发生热损失，测量的温度差可能无法表征氢气复合热，反应部件和催化反应部件的距离都影响测量精度，氢气浓度测量精度无法保证。
另一种是气体抽出安全壳外的严重事故氢气浓度测量方法。如图1B所示，通过导管(毛细管或其他管线)将安全壳的气体抽出至安全壳外的气体测量装置，测量装置通过降温、降压等处理后，在监测室中由可耐受较低环境条件的氢气浓度监测装置进行测量氢气浓度，最后通过计算补偿等方式计算安全壳内氢气浓度。安全壳内的取样头、取样管线耐受严重事故工况，取样回路具备返吹扫功能，能够避免严重事故工况下安全壳内的气溶胶堵塞取样管。测量机柜和处理机柜处于安全壳外区域。该方法由于采用将气体抽出安全壳外进行测量，经过降温、降压测量，所测得参数较难准确真实表征安全壳内氢气浓度；同时，该方法存在取样管线的破裂的情形，进一步增加安全壳的泄漏点，将安全壳内放射性气体抽出至安全壳外，将增加安全壳外人员受照射的风险，安全性不高。
有鉴于此，如何实现安全壳内氢气浓度的精确、安全监测，是目前亟待解决的问题。
发明内容
本发明的目的在于：在核电站安全壳内氢气浓度监测中，提供一种精确、 安全的安全壳内氢气浓度测量技术。
为了实现上述发明目的，本发明提供了一种核电站安全壳内氢气浓度测量方法，所述方法包括：
在核电站安全壳内设置镀有钯银合金膜的氢气测量部件；
处理机柜采集氢气测量部件吸收释放氢气后的电导率信号；
处理机柜根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
作为本发明核电站安全壳内氢气浓度测量方法的一种改进，所述方法还包括：
所述氢气测量部件通过核级电缆与处理机柜相连，所述处理机柜通过核级电缆采集氢气测量部件吸收释放氢气后的电导率信号。
作为本发明核电站安全壳内氢气浓度测量方法的一种改进，所述方法还包括：
使用加热元件使氢气测量部件处于恒定温度状态。作为一种核电站安全壳内氢气浓度测量方法的一种改进，所述方法还包括：
测温元件测量氢气测量部件所处位置的温度值。
作为本发明核电站安全壳内氢气浓度测量方法的一种改进，所述处理机柜根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度，包括：
处理机柜根据采集的所述电导率信号、所述温度值以及核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
作为本发明核电站安全壳内氢气浓度测量方法的一种改进，所述处理机柜根据采集的所述电导率信号、所述温度值以及核电站安全壳内的压力信号确定核电站安全壳内氢气浓度，还包括：
处理机柜根据采集的所述电导率信号、所述温度值、温度补偿值以及核电 站安全壳内的压力信号确定核电站安全壳内氢气浓度。
作为本发明核电站安全壳内氢气浓度测量方法的一种改进，所述在核电站安全壳内设置镀有钯银合金膜的氢气测量部件之前，还包括：
将钯银合金镀在耐高温的陶瓷薄片。
作为本发明核电站安全壳内氢气浓度测量方法的一种改进，所述方法还包括：
所述氢气测量部件外壳采用烧结不锈钢材质。
作为本发明核电站安全壳内氢气浓度测量方法的一种改进，所述方法还包括：
所述氢气测量部件上方还设置有防喷淋液喷淋的防护罩。
为了实现上述发明目的，本发明还提供了一种核电站安全壳内氢气浓度测量装置，该装置设置在核电站安全壳内，该装置包括：
镀有钯银合金膜的探头,用于吸收核电站安全壳中的氢气；
传输单元，用于将所述探头的电导率信号传输至处理机柜，以使所述处理机柜根据所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
作为本发明核电站安全壳内氢气浓度测量装置的一种改进，所述装置还包括：
加热元件，用于给所述探头进行加热，以使所述探头处于恒定温度状态。
作为本发明核电站安全壳内氢气浓度测量装置的一种改进，所述装置还包括：测温元件，测量所述探头所处位置的温度值。
作为本发明核电站安全壳内氢气浓度测量装置的一种改进，所述装置还包括：
防护罩，用于防止喷淋液接触所述探头。
作为本发明核电站安全壳内氢气浓度测量装置的一种改进，所述传输单元 将所述探头的电导率信号传输至处理机柜，包括：
传输单元将所述探头的电导率信号通过核级电缆传输至安全壳的电气贯穿件上，再通过安全壳外的另一端电缆从所述电气贯穿件引出至安全壳外的处理机柜。
作为本发明核电站安全壳内氢气浓度测量装置的一种改进，所述探头具体为将钯银合金镀在耐高温的陶瓷薄片形成。
作为本发明核电站安全壳内氢气浓度测量装置的一种改进，所述探头还包括：
采用烧结不锈钢材质的外壳。
作为本发明核电站安全壳内氢气浓度测量装置的一种改进，所述装置还包括：
氢气测量组件外壳，罩在所述镀有钯银合金膜的探头和所述加热元件的上方。
为了实现上述发明目的，本发明还提供了一种核电站安全壳内氢气浓度测量系统，系统包括：氢气测量部件，用于探测核电站安全壳内的氢气；
处理机柜，用于采集所述氢气测量部件吸收释放氢气后的电导率信号，并根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
作为本发明核电站安全壳内氢气浓度测量系统的一种改进，所述氢气测量部件安装在核电站安全壳内，外表面镀有钯银合金膜。
作为本发明核电站安全壳内氢气浓度测量系统的一种改进，所述氢气测量部件通过核级电缆与处理机柜相连，所述处理机柜通过核级电缆采集氢气测量部件吸收释放氢气后的电导率信号。
作为本发明核电站安全壳内氢气浓度测量系统的一种改进，所述系统还包括：
加热元件，安装在核电站安全壳内，用于使氢气测量部件处于恒定温度状态。
作为本发明核电站安全壳内氢气浓度测量系统的一种改进，所述系统还包括：测温元件，安装在核电站安全壳内，用于测量氢气测量部件所处位置的温度值。
作为本发明核电站安全壳内氢气浓度测量系统的一种改进，所述系统还包括：
防护罩，用于防止喷淋液接触所述氢气测量部件。
作为本发明核电站安全壳内氢气浓度测量系统的一种改进，所述处理机柜采集所述氢气测量部件吸收释放氢气后的电导率信号，并根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度，包括：
所述处理机柜根据采集的所述电导率信号、所述温度值以及核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
作为本发明核电站安全壳内氢气浓度测量系统的一种改进，所述氢气测量部件通过核级电缆与处理机柜相连，还包括：
氢气测量部件通过电缆插接头与核级电缆相连。
作为本发明核电站安全壳内氢气浓度测量系统的一种改进，所述处理机柜采集氢气测量部件吸收释放氢气后的电导率信号，还包括：
氢气测量部件通过电缆插接头与核级电缆相连，将电导率信号传输至核电站安全壳的电气贯穿件上，所述电气贯穿件通过电缆线将所述电导率信号传输至处理机柜中。
与现有技术相比，本发明核电站安全壳内氢气浓度测量方法、装置及系统具有以下有益技术效果：通过处理机柜采集在核电站安全壳内设置镀有钯银合金膜的氢气测量部件电导率信号、核电站安全壳内温度信号和的压力信号情况，即可实现对核电站安全壳内氢气浓度的测量。可实现在有氧和无氧环境下氢气 浓度的测量，使用范围较广；同时，对于高温、高压、高辐照环境下的氢气浓度测量均可适用，很好地克服了恶劣环境对氢气浓度测量的影响。此外，实现方法简单易行，取得很好的技术效果。
附图说明
下面结合附图和具体实施方式，对本发明核电站安全壳内氢气浓度测量方法、装置及系统进行详细说明，其中：
图1A提供了核电站安全壳内氢气浓度测量方法的一个现有方案。
图1B提供了核电站安全壳内氢气浓度测量方法的又一个现有方案。
图2提供了本发明核电站安全壳内氢气浓度测量方法的一个实例流程图。
图3提供了本发明核电站安全壳内氢气浓度测量装置的一个实例示意图。
图4提供了本发明核电站安全壳内氢气浓度测量系统的一个实例示意图。
图5提供了本发明核电站安全壳内氢气浓度测量系统的又一个实例示意图。
具体实施方式
为了使本发明的发明目的、技术方案及其有益技术效果更加清晰，以下结合附图和具体实施方式，对本发明进行进一步详细说明。应当强调的是，本说明书中描述的具体实施方式仅仅是为了解释本发明，并非为了限定本发明的使用场合。
请结合参看图2，图2提供了一种核电站安全壳内氢气浓度测量方法。具体的：
步骤201，在核电站安全壳内设置镀有钯银合金膜的氢气测量部件。
在一定温度情况下，钯银合金的吸收及释放氢气的能力将较快达到平衡态，钯银合金的电导率正比于氢气浓度。基于此原理，在核电站安全壳内设置镀有钯银合金膜的氢气测量部件。通过氢气测量部件探测核电站安全壳内的氢气。
进一步的，氢气测量部件可由载体及载体上的丝状金属膜组成。金属膜采用钯银合金制成，根据钯银合金具有在混合气体中吸收或释放氢气后内部氢气分子改变其电导率的特性。
步骤203，处理机柜采集氢气测量部件吸收释放氢气后的电导率信号。
进一步的，氢气测量部件通过核级电缆与处理机柜相连，所述处理机柜通过核级电缆采集氢气测量部件吸收释放氢气后的电导率信号。
具体的，氢气测量部件通过电缆插接头与核级电缆相连，将电导率信号传输至核电站安全壳的电气贯穿件上，所述电气贯穿件通过电缆线将所述电导率信号传输至处理机柜中。氢气测量部件通过耐受严重事故环境条件的核级电缆将电信号传输到安全壳的电气贯穿件上，然后安全壳外的另一端电缆从电气贯穿件引出至安全壳外的处理机柜中。安全壳内采用耐受严重事故的核级电缆，电缆内部的绝缘材料采用耐高温、耐辐照的绝缘材料。
进一步的，使用加热元件使氢气测量部件处于恒定温度状态。具体的，钯银合金的电导率在约150℃以上会随温度的升高而降低，而在一定温度钯银合金的电导率基本不受温度影响，结合温度对测量值的影响，保证氢气测量部件处于恒定温度。
进一步的，测温元件测量氢气测量部件所处位置的温度值。
所测的温度值用于补偿钯银合金测量值。
步骤205，处理机柜根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
核电站的安全壳内压力信号可由外部系统测量后提供给本系统。由于气体的体积浓度受压力影响较大，特别是饱和蒸汽气体环境。气体组份会受到水蒸气组份的影响。需要引入安全壳的压力信号用于补偿其测量的氢气浓度值。
安全壳外的处理机柜接收钯银合金的电导率信号和温度值后，经过特殊算法计算补偿，算法中引入温度补偿。另外，测量的氢气浓度是体积浓度，测量 的体积浓度受环境的压力影响较大，因此在处理装置部分，接收外部安全壳压力信号，用于补偿测量输出结果，提高精度。最终计算出的氢气浓度能够表征安全壳内的氢气浓度，且考虑了安全壳内温度和压力的影响。
本发明实施例通过处理机柜采集在核电站安全壳内设置镀有钯银合金膜的氢气测量部件电导率信号和核电站安全壳内的压力信号情况，即可实现对核电站安全壳内氢气浓度的测量。可实现在有氧和无氧环境下氢气浓度的测量，使用范围较广；同时，对于高温、高压、高辐照环境下的氢气浓度测量均可适用，很好地客服了恶劣环境对氢气浓度测量的影响。
请结合参看图3，图3提供了一种核电站安全壳内氢气浓度测量装置的一个实施例的示意图。该装置设置在核电站安全壳内，包括探头301和传输单元303。其中，
探头301，镀有钯银合金膜，用于吸收核电站安全壳中的氢气。
钯银合金的吸收及释放氢气的能力达到平衡态，钯银合金的电导率正比于氢气浓度。
传输单元303，用于将探头301的电导率信号传输至处理机柜，以使所述处理机柜根据所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
进一步的，该装置还包括加热元件，用于给探头301进行加热，以使所述探头处于恒定温度状态。具体的，钯银合金的电导率正比于氢气浓度，在一定温度情况下，钯银合金的吸收及释放氢气的能力将较快达到平衡态，阻值响应更快。钯银合金的电导率在约150℃以上会随温度的升高而降低，而在一定温度钯银合金的电导率基本不受温度影响，结合温度对测量值的影响，在氢气测量组件中增加了加热元件用于保证探头301处于恒定温度。
进一步的，该装置还包括测温元件，测量探头301所处位置的温度值。具体的，探头中包括耐严重事故的测温元件，所测的温度值用于补偿钯银合金测 量值。
进一步的，该装置还包括防护罩，用于防止喷淋液接触探头301。
进一步的，探头301具体为将钯银合金镀在耐高温的陶瓷薄片形成。探头301外还有采用烧结不锈钢材质的外壳。
本发明实施例通过处理机柜采集在核电站安全壳内设置镀有钯银合金膜的探头电导率信号和核电站安全壳内的压力信号情况，即可实现对核电站安全壳内氢气浓度的测量。
请结合参看图4，图4提供了一种核电站安全壳内氢气浓度测量系统的一个实施例的示意图。包括：氢气测量部件401和处理机柜403。具体的：
氢气测量部件401，用于探测核电站安全壳内的氢气。
钯银合金的吸收及释放氢气的能力达到平衡态，钯银合金的电导率正比于氢气浓度。一定形式的钯银合金的吸收及释放氢气的能力将较快达到平衡态，钯银合金的电导率正比于氢气浓度。基于此原理，在核电站安全壳内设置镀有钯银合金膜的氢气测量部件401。通过氢气测量部件401吸收核电站安全壳内的氢气。
进一步的，氢气测量部件401可由载体及载体上的丝状金属膜组成。金属膜采用钯银合金制成，根据钯银合金具有在混合气体中吸收或释放氢气后内部氢气分子改变其电导率的特性。
处理机柜403，用于采集所述氢气测量部件吸收释放氢气后的电导率信号，并根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
氢气测量部件401通过核级电缆与处理机柜相连，处理机柜403通过核级电缆采集氢气测量部件401吸收释放氢气后的电导率信号。氢气测量部件401通过电缆插接头与核级电缆相连。
氢气测量部件401通过电缆插接头与核级电缆相连，将电导率信号传输至 核电站安全壳的电气贯穿件上，电气贯穿件通过电缆线将电导率信号传输至处理机柜403中。氢气测量部件401通过耐受严重事故环境条件的核级电缆将电信号传输到安全壳的电气贯穿件上，然后安全壳外的另一端电缆从电气贯穿件引出至安全壳外的处理机柜403中。安全壳内采用耐受严重事故的核级电缆，电缆内部的绝缘材料采用耐高温、耐辐照的绝缘材料。
本发明实施例通过处理机柜采集在核电站安全壳内设置镀有钯银合金膜的氢气测量部件电导率信号和核电站安全壳内的压力信号情况，即可实现对核电站安全壳内氢气浓度的测量。
请结合参看图5，图5提供了一种核电站安全壳内氢气浓度测量系统的一个实施例的示意图。包括：氢气测量部件501、处理机柜503、测温元件507、防护罩509以及氢气测量组件外壳511。其中：
氢气测量部件501，用于吸收核电站安全壳内的氢气。
在一定温度情况下，钯银合金的吸收及释放氢气的能力将较快达到平衡态，钯银合金的电导率正比于氢气浓度。基于此原理，在核电站安全壳内设置镀有钯银合金膜的氢气测量部件501。通过氢气测量部件501吸收核电站安全壳内的氢气。
进一步的，氢气测量部件501可由载体及载体上的丝状金属膜组成。金属膜采用钯银合金制成，根据钯银合金具有从混合气体吸收释放氢气的特性，从混合气体中提取纯氢气浓度。
具体的，氢气测量部件501可由载体及载体上的金属膜组成。金属膜采用钯银合金制成，利用钯银合金具有从混合气体吸收释放氢气的特性测量氢气浓度。钯银合金不同混合比例，在氢气浓度下的对应关系会有差异，钯金存在过吸收现象，纯钯金固相中的氢气含量不能与氢气分压形成良好的线性关系。合适的钯银组份比例将形成良好的线性关系，而固相氢气含量与电导率成正比关系，因此可以使氢气分压与电导率形成良好的线性关系。
处理机柜503，用于采集所述氢气测量部件501吸收释放氢气后的电导率信号，并根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
进一步的，氢气测量部件501通过核级电缆或耐严重事故电缆与处理机柜503相连，所述处理机柜503通过核级电缆采集氢气测量部件501吸收释放氢气后的电导率信号。
具体的，氢气测量部件501通过电缆插接头与核级电缆相连，将电导率信号传输至核电站安全壳的电气贯穿件上，所述电气贯穿件通过电缆线将所述电导率信号传输至处理机柜503中。氢气测量部件501通过耐受严重事故环境条件的核级电缆将电信号传输到安全壳的电气贯穿件上，然后安全壳外的另一端电缆从电气贯穿件引出至安全壳外的处理机柜503中。安全壳内采用耐受严重事故的核级电缆，电缆内部的绝缘材料采用耐高温、耐辐照的绝缘材料。
加热元件505，安装在核电站安全壳内，用于使氢气测量部件处于恒定温度状态。
进一步的，使用加热元件505使氢气测量部件501处于恒定温度状态。具体的，钯银合金的电导率在约150℃以上会随温度的升高而降低，而在一定温度钯银合金的电导率基本不受温度影响，结合温度对测量值的影响，用于保证氢气测量部件501处于恒定温度。测温元件507，安装在核电站安全壳内，用于测量氢气测量部件所处位置的温度值。
进一步的，测温元件507测量氢气测量部件501所处位置的温度值。
所测的温度值用于补偿钯银合金测量值。
防护罩509，用于防止喷淋液接触所述氢气测量部件。
氢气测量组件外壳511，罩在镀有钯银合金膜的探头和所述加热元件的上方。即罩在测量氢气测量部件501上方。可以防止外部气溶胶进入覆盖钯银合金表面影响测量效果。还增加了防护罩的防喷淋措施，防止喷淋液进入，影响 测量结果。
进一步的，安全壳外的处理机柜503接收钯银合金的电导率信号和温度值后，经过特殊算法计算补偿，算法中引入温度补偿。另外，测量的氢气浓度是体积浓度，测量的体积浓度受环境的压力影响较大，因此在处理装置部分，接收外部安全壳压力信号，用于补偿测量输出结果，提高精度。最终计算出的氢气浓度能够表征安全壳内的氢气浓度，且考虑了安全壳内温度和压力的影响。
系统的实施方法和流程可以参见前述实施例中介绍的方法实施例，此处不再赘述。
结合以上对本发明的详细描述可以看出，相对于现有技术，本发明至少具有以下有益技术效果：通过处理机柜采集在核电站安全壳内设置镀有钯银合金膜的氢气测量部件电导率信号和核电站安全壳内的压力信号情况，即可实现对核电站安全壳内氢气浓度的测量。可实现在有氧和无氧环境下氢气浓度的测量，使用范围较广；同时，对于高温、高压、高辐照环境下的氢气浓度测量均可适用，很好地客服了恶劣环境对氢气浓度测量的影响。此外，实现方法简单易行，取得很好的技术效果。
根据上述原理，本发明还可以对上述实施方式进行适当的变更和修改。因此，本发明并不局限于上面揭示和描述的具体实施方式，对本发明的一些修改和变更也应当落入本发明的权利要求的保护范围内。此外，尽管本说明书中使用了一些特定的术语，但这些术语只是为了方便说明，并不对本发明构成任何限制。

Claims (26)

  1. 一种核电站安全壳内氢气浓度测量方法，其特征在于，所述方法包括：
    在核电站安全壳内设置镀有钯银合金膜的氢气测量部件；
    处理机柜采集氢气测量部件吸收释放氢气后的电导率信号；
    处理机柜根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
  2. 根据权利要求1所述的方法，其特征在于，所述方法还包括：
    所述氢气测量部件通过核级电缆与处理机柜相连，所述处理机柜通过核级电缆采集氢气测量部件吸收释放氢气后的电导率信号。
  3. 根据权利要求2所述的方法，其特征在于，所述方法还包括：
    使用加热元件使氢气测量部件处于恒定温度状态。
  4. 根据权利要求3所述的方法，其特征在于，所述方法还包括：
    测温元件测量氢气测量部件所处位置的温度值。
  5. 根据权利要求4所述的方法，其特征在于，所述处理机柜根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度，包括：
    处理机柜根据采集的所述电导率信号、所述温度值以及核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
  6. 根据权利要求5所述的方法，其特征在于，所述处理机柜根据采集的所述电导率信号、所述温度值以及核电站安全壳内的压力信号确定核电站安全壳内氢气浓度，还包括：
    处理机柜根据采集的所述电导率信号、所述温度值、温度补偿值以及核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
  7. 根据权利要求6所述的方法，其特征在于，所述在核电站安全壳内设置 镀有钯银合金膜的氢气测量部件之前，还包括：
    将钯银合金镀在耐高温的陶瓷薄片。
  8. 根据权利要求7所述的方法，其特征在于，所述方法还包括：
    所述氢气测量部件外壳采用烧结不锈钢材质。
  9. 根据权利要求8所述的方法，其特征在于，所述方法还包括：
    所述氢气测量部件上方还设置有防喷淋液喷淋的防护罩。
  10. 一种核电站安全壳内氢气浓度测量装置，其特征在于，所述装置设置在核电站安全壳内，该装置包括：
    镀有钯银合金膜的探头,用于探测核电站安全壳中的氢气；
    传输单元，用于将所述探头的电导率信号传输至处理机柜，以使所述处理机柜根据所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
  11. 根据权利要求10所述的装置，其特征在于，所述装置还包括：
    加热元件，用于给所述探头进行加热，以使所述探头处于恒定温度状态。
  12. 根据权利要求11所述的装置，其特征在于，所述装置还包括：
    测温元件，测量所述探头所处位置的温度值。
  13. 根据权利要求12所述的装置，其特征在于，所述装置还包括：
    防护罩，用于防止喷淋液接触所述探头。
  14. 根据权利要求13所述的装置，其特征在于，所述传输单元将所述探头的电导率信号传输至处理机柜，包括：
    传输单元将所述探头的电导率信号通过核级电缆传输至安全壳的电气贯穿件上，再通过安全壳外的另一端电缆从所述电气贯穿件引出至安全壳外的处理机柜。
  15. 根据权利要求10-14任一项所述的装置，其特征在于，所述探头具体为将钯银合金镀在耐高温的陶瓷薄片形成。
  16. 根据权利要求15所述的装置，其特征在于，所述探头还包括：
    采用烧结不锈钢材质的外壳。
  17. 根据权利要求16所述的装置，其特征在于，所述装置还包括：
    氢气测量组件外壳，罩在所述镀有钯银合金膜的探头和所述加热元件的上方。
  18. 一种核电站安全壳内氢气浓度测量系统，其特征在于，所述系统包括：
    氢气测量部件，用于探测核电站安全壳内的氢气；
    处理机柜，用于采集所述氢气测量部件吸收释放氢气后的电导率信号，并根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
  19. 根据权利要求18所述的系统，其特征在于，所述氢气测量部件安装在核电站安全壳内，外表面镀有钯银合金膜。
  20. 根据权利要求19所述的系统，其特征在于，所述氢气测量部件通过核级电缆与处理机柜相连，所述处理机柜通过核级电缆采集氢气测量部件吸收释放氢气后的电导率信号。
  21. 根据权利要求20所述的系统，其特征在于，所述系统还包括：
    加热元件，安装在核电站安全壳内，用于使氢气测量部件处于恒定温度状态。
  22. 根据权利要求21所述的系统，其特征在于，所述系统还包括：测温元件，安装在核电站安全壳内，用于测量氢气测量部件所处位置的温度值。
  23. 根据权利要求21所述的系统，其特征在于，所述系统还包括：
    防护罩，用于防止喷淋液接触所述氢气测量部件。
  24. 根据权利要求23所述的系统，其特征在于，所述处理机柜采集所述氢气测量部件吸收释放氢气后的电导率信号，并根据采集的所述电导率信号和核电站安全壳内的压力信号确定核电站安全壳内氢气浓度，包括：
    所述处理机柜根据采集的所述电导率信号、所述温度值以及核电站安全壳内的压力信号确定核电站安全壳内氢气浓度。
  25. 根据权利要求24所述的系统，其特征在于，所述氢气测量部件通过核级电缆与处理机柜相连，还包括：
    氢气测量部件通过电缆插接头与核级电缆相连。
  26. 根据权利要求25所述的系统，其特征在于，所述处理机柜采集氢气测量部件吸收释放氢气后的电导率信号，还包括：
    氢气测量部件通过电缆插接头与核级电缆相连，将电导率信号传输至核电站安全壳的电气贯穿件上，所述电气贯穿件通过电缆线将所述电导率信号传输至处理机柜中。
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