CN104538070A - Method, device and system for measuring concentration of hydrogen in nuclear power station containment vessel - Google Patents

Method, device and system for measuring concentration of hydrogen in nuclear power station containment vessel Download PDF

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Publication number
CN104538070A
CN104538070A CN201410742292.6A CN201410742292A CN104538070A CN 104538070 A CN104538070 A CN 104538070A CN 201410742292 A CN201410742292 A CN 201410742292A CN 104538070 A CN104538070 A CN 104538070A
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hydrogen
nuclear power
power plant
containment shell
plant containment
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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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Priority to CN201410742292.6A priority Critical patent/CN104538070A/en
Publication of CN104538070A publication Critical patent/CN104538070A/en
Priority to PCT/CN2015/096603 priority patent/WO2016091146A1/en
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N27/00Investigating or analysing materials by the use of electric, electrochemical, or magnetic means
    • G01N27/02Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating impedance
    • G01N27/04Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating impedance by investigating resistance
    • G01N27/14Investigating 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
    • G01N27/16Investigating 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
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
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  • Health & Medical Sciences (AREA)
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  • General Health & Medical Sciences (AREA)
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  • Life Sciences & Earth Sciences (AREA)
  • Electrochemistry (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a method for measuring a concentration of hydrogen in a nuclear power station containment vessel. The method comprises that a hydrogen measurement part plated with a palladium-silver alloy membrane is arranged in a nuclear power station containment vessel, a processor cabinet acquires a conductivity signal of the hydrogen measurement part after hydrogen absorption and release, and the processor cabinet determines a concentration of hydrogen in the nuclear power station containment vessel according the acquired conductivity signal and a signal of pressure in the nuclear power station containment vessel. The method for measuring a concentration of hydrogen in a nuclear power station containment vessel can realize safe and accurate measurement of a concentration of hydrogen in the nuclear power station containment vessel. The invention also discloses a device and system for measuring a concentration of hydrogen in a nuclear power station containment vessel.

Description

Density of hydrogen measuring method, Apparatus and system in nuclear power plant containment shell
Technical field
The invention belongs to technical field of nuclear power, more particularly, the present invention relates to density of hydrogen measuring method, Apparatus and system in a kind of nuclear power plant containment shell.
Background technology
When there is major accident in nuclear power station, can produce a large amount of hydrogen in containment, the blast of hydrogen can threaten the integrality of nuclear plant safety barrier.Can produce a large amount of hydrogen under nuclear power plant's accident conditions, the source of hydrogen: accident is early stage, zirconium-water reaction two-forty ground produces hydrogen; The accident middle and later periods, the irradiation of water decomposes, the melt and dissolved thing of reactor core and concrete reaction, also can produce a large amount of hydrogen.The gathering of a large amount of hydrogen makes concentration of hydrogen in containment vessel have to exceed possibility of blast limit 4%, there is the danger of exploding.For avoiding hydrogen deflagration accident having to occur, destroy containment integrity, need to build the hydrogen state of aggregation of hydrogen measurement system to containment diverse location and monitor, after accident occurs, enforcement is intervened effectively.Under accident conditions, reactor releases a large amount of heats, and in containment, the rising of temperature is along with the rising of pressure.As after two generations and two Dai Jia nuclear power plant accidents, temperature can reach 150 degree, pressure can reach 6bar.Gas composition in containment is based on air and water vapor, the High Temperature High Pressure mixed gases containing hydrogen and other gases.
Because gas in containment under accident conditions presents high temperature, high pressure, highly radioactive feature, the measurement therefore for density of hydrogen adds very large difficulty.Therefore nuclear power station needs a set of method measured for major accident density of hydrogen, but environmental baseline is usually comparatively severe during containment inherent major accident, as rugged surroundings such as high temperature, high pressure, high irradiation, be unfavorable for the continuous monitoring of operating personnel to accident, the more difficult concentration of monitoring hydrogen in an efficient way.
Existing nuclear plant severe accident density of hydrogen monitoring scheme mainly comprises following two kinds:
A kind of is the major accident density of hydrogen monitoring method utilizing catalytic reaction principle.As shown in Figure 1A, at the entrance and exit set temperature sensor of inflammable gas recombiner, by measuring inflammable gas recombiner catalytic reaction heat, namely out temperature is poor, be converted into density of hydrogen by calculating, thus reach the object of monitoring major accident density of hydrogen.Concrete, the parts (inflammable gas recombiner and temperature sensor) that can tolerate major accident are arranged in containment, and measuring-signal is processed to the process rack outside containment by signal wire teletransmission.Process rack is in the containment exterior domain of non-rugged surroundings.The method is owing to adopting inflammable gas recombiner to be catalysis element, only could use at the environment of aerobic, measure at inert gas environment and lost efficacy, under high hydrogen concentration, oxygen-deficient environment, catalytic reaction heat truly cannot reflect density of hydrogen, and the aerobic environment density of hydrogen be only applicable to for low density of hydrogen is measured; Meanwhile, the method is that indirect density of hydrogen is measured, and mainly measures reaction heat, may thermal loss be there is in inflammable gas recombiner, the temperature difference measured possibly cannot characterize hydrogen compound thermal, and the distance of reaction part and catalytic reaction parts all affects measuring accuracy, and density of hydrogen measuring accuracy cannot ensure.
Another kind is the major accident density of hydrogen measuring method that gas extracts outside containment out.As shown in Figure 1B, by conduit (kapillary or other pipelines) gas of containment is drawn to the gas measurement device outside containment, measurement mechanism is by after the process such as cooling, step-down, measurement density of hydrogen is carried out, finally by density of hydrogen in the mode computationally secure shells such as calculation compensation by the density of hydrogen monitoring device that can tolerate compared with low environment condition in monitoring room.Sampling head in containment, sampling line tolerance major accident operating mode, sampling loop possesses and returns purging function, the gasoloid blocking stopple coupon under the operating mode that can avoid a nasty accident in containment.Measure rack and process rack and be in containment exterior domain.The method is measured owing to adopting gas to extract out outside containment, measures, the more difficult accurate exact representation concentration of hydrogen in containment vessel of measured parameter through cooling, step-down; Meanwhile, there is the situation of breaking of sampling line in the method, increases the leakage point of containment further, be drawn to outside containment by radgas in containment, and will increase the outer irradiated risk of personnel of containment, security is not high.
In view of this, how realizing accurate, the safety monitoring of concentration of hydrogen in containment vessel, is current problem demanding prompt solution.
Summary of the invention
The object of the invention is to: in nuclear power plant containment shell in density of hydrogen monitoring, provide a kind of accurate, safe concentration of hydrogen in containment vessel measuring technique.
In order to realize foregoing invention object, the invention provides density of hydrogen measuring method in a kind of nuclear power plant containment shell, described method comprises:
The hydrogen measurement parts being coated with Pd-Ag alloy membrane are set in nuclear power plant containment shell;
Process rack gathers the conductivity signal after hydrogen measurement parts absorption release hydrogen;
Process rack is according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell.
One as density of hydrogen measuring method in nuclear power plant containment shell of the present invention is improved, and described method also comprises:
Described hydrogen measurement parts are connected with process rack by core level cable, and described process rack gathers hydrogen measurement parts by core level cable and absorbs the conductivity signal after release hydrogen.
One as density of hydrogen measuring method in nuclear power plant containment shell of the present invention is improved, and described method also comprises:
Heating element is used to make hydrogen measurement parts be in steady temperature state.One as density of hydrogen measuring method in a kind of nuclear power plant containment shell is improved, and described method also comprises:
The temperature value of hydrogen measurement parts present position measured by temperature element.
One as density of hydrogen measuring method in nuclear power plant containment shell of the present invention is improved, and described process rack, according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell, comprising:
Process rack is according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered, described temperature value and nuclear power plant containment shell.
One as density of hydrogen measuring method in nuclear power plant containment shell of the present invention is improved, described process rack, according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered, described temperature value and nuclear power plant containment shell, also comprises:
Process rack is according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered, described temperature value, temperature compensation value and nuclear power plant containment shell.
One as density of hydrogen measuring method in nuclear power plant containment shell of the present invention is improved, described in nuclear power plant containment shell arrange be coated with the hydrogen measurement parts of Pd-Ag alloy membrane before, also comprise:
Palladium-silver is plated in resistant to elevated temperatures ceramic sheet.
One as density of hydrogen measuring method in nuclear power plant containment shell of the present invention is improved, and described method also comprises:
Described hydrogen measurement parts shell adopts sintered stainless steel material.
One as density of hydrogen measuring method in nuclear power plant containment shell of the present invention is improved, and described method also comprises:
The protective cover of anti-spray liquid spray is also provided with above described hydrogen measurement parts.
In order to realize foregoing invention object, present invention also offers density of hydrogen measurement mechanism in a kind of nuclear power plant containment shell, this device is arranged in nuclear power plant containment shell, and this device comprises:
Be coated with the probe of Pd-Ag alloy membrane, for absorbing the hydrogen in nuclear power plant containment shell;
Transmission unit, for the conductivity signal of described probe is transferred to process rack, to make described process rack according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in described conductivity signal and nuclear power plant containment shell.
One as density of hydrogen measurement mechanism in nuclear power plant containment shell of the present invention is improved, and described device also comprises:
Heating element, for heating to described probe, is in steady temperature state to make described probe.
One as density of hydrogen measurement mechanism in nuclear power plant containment shell of the present invention is improved, and described device also comprises: temperature element, measures the temperature value of described probe present position.
One as density of hydrogen measurement mechanism in nuclear power plant containment shell of the present invention is improved, and described device also comprises:
Protective cover, contacts described probe for preventing spray liquid.
One as density of hydrogen measurement mechanism in nuclear power plant containment shell of the present invention is improved, and the conductivity signal of described probe is transferred to process rack by described transmission unit, comprising:
Transmission unit by the conductivity signal of described probe by core level cable transmission on the electrical penetration of containment, then to be led to the process rack containment from described electrical penetration by the other end cable outside containment.
One as density of hydrogen measurement mechanism in nuclear power plant containment shell of the present invention is improved, and described probe is specially and palladium-silver is plated in the formation of resistant to elevated temperatures ceramic sheet.
One as density of hydrogen measurement mechanism in nuclear power plant containment shell of the present invention is improved, and described probe also comprises:
Adopt the shell of sintered stainless steel material.
One as density of hydrogen measurement mechanism in nuclear power plant containment shell of the present invention is improved, and described device also comprises:
Hydrogen measurement package shell, is coated with the probe of Pd-Ag alloy membrane and the top of described heating element described in covering on.
In order to realize foregoing invention object, present invention also offers density of hydrogen measuring system in a kind of nuclear power plant containment shell, system comprises: hydrogen measurement parts, for detecting the hydrogen in nuclear power plant containment shell;
Process rack, absorbs the conductivity signal after release hydrogen for gathering described hydrogen measurement parts, and according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell.
One as density of hydrogen measuring system in nuclear power plant containment shell of the present invention is improved, and described hydrogen measurement parts are arranged in nuclear power plant containment shell, and outside surface is coated with Pd-Ag alloy membrane.
One as density of hydrogen measuring system in nuclear power plant containment shell of the present invention is improved, described hydrogen measurement parts are connected with process rack by core level cable, and described process rack gathers hydrogen measurement parts by core level cable and absorbs the conductivity signal after release hydrogen.
One as density of hydrogen measuring system in nuclear power plant containment shell of the present invention is improved, and described system also comprises:
Heating element, is arranged in nuclear power plant containment shell, is in steady temperature state for making hydrogen measurement parts.
One as density of hydrogen measuring system in nuclear power plant containment shell of the present invention is improved, and described system also comprises: temperature element, is arranged in nuclear power plant containment shell, for measuring the temperature value of hydrogen measurement parts present position.
One as density of hydrogen measuring system in nuclear power plant containment shell of the present invention is improved, and described system also comprises:
Protective cover, contacts described hydrogen measurement parts for preventing spray liquid.
One as density of hydrogen measuring system in nuclear power plant containment shell of the present invention is improved, described process rack gathers the conductivity signal after described hydrogen measurement parts absorption release hydrogen, and according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell, comprising:
Described process rack is according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered, described temperature value and nuclear power plant containment shell.
One as density of hydrogen measuring system in nuclear power plant containment shell of the present invention is improved, and described hydrogen measurement parts are connected with process rack by core level cable, also comprise:
Hydrogen measurement parts are connected with core level cable by cable connector head.
One as density of hydrogen measuring system in nuclear power plant containment shell of the present invention is improved, and described process rack gathers the conductivity signal after hydrogen measurement parts absorption release hydrogen, also comprises:
Hydrogen measurement parts are connected with core level cable by cable connector head, are transferred to by conductivity signal on the electrical penetration of nuclear power plant containment shell, and described conductivity signal is transferred in process rack by cable by described electrical penetration.
Compared with prior art, in nuclear power plant containment shell of the present invention, density of hydrogen measuring method, Apparatus and system have following Advantageous Effects: by process rack be captured in nuclear power plant containment shell arrange be coated with temperature signal in the hydrogen measurement parts conductivity signal of Pd-Ag alloy membrane, nuclear power plant containment shell and pressure signal situation, the measurement to density of hydrogen in nuclear power plant containment shell can be realized.Can realize the measurement of density of hydrogen under aerobic and oxygen-free environment, usable range is wider; Meanwhile, measure all applicable for the density of hydrogen under high temperature, high pressure, high radiation environment, overcome the impact that rugged surroundings are measured density of hydrogen well.In addition, implementation method is simple, obtains good technique effect.
Accompanying drawing explanation
Below in conjunction with the drawings and specific embodiments, density of hydrogen measuring method, Apparatus and system in nuclear power plant containment shell of the present invention are described in detail, wherein:
Figure 1A provides an existing scheme of density of hydrogen measuring method in nuclear power plant containment shell.
Figure 1B provides another existing scheme of density of hydrogen measuring method in nuclear power plant containment shell.
Fig. 2 provides an example flow chart of density of hydrogen measuring method in nuclear power plant containment shell of the present invention.
Fig. 3 provides an example schematic of density of hydrogen measurement mechanism in nuclear power plant containment shell of the present invention.
Fig. 4 provides an example schematic of density of hydrogen measuring system in nuclear power plant containment shell of the present invention.
Fig. 5 provides another example schematic of density of hydrogen measuring system in nuclear power plant containment shell of the present invention.
Embodiment
In order to make goal of the invention of the present invention, technical scheme and Advantageous Effects thereof more clear, below in conjunction with the drawings and specific embodiments, the present invention is further elaborated.It is emphasized that the embodiment described in this instructions is only used to explain the present invention, be not intended to limit use occasion of the present invention.
Incorporated by reference to providing density of hydrogen measuring method in a kind of nuclear power plant containment shell referring to Fig. 2, Fig. 2.Concrete:
Step 201, arranges the hydrogen measurement parts being coated with Pd-Ag alloy membrane in nuclear power plant containment shell.
In uniform temperature situation, the absorption of palladium-silver and the ability of release hydrogen comparatively fast will reach equilibrium state, and the conductivity of palladium-silver is proportional to density of hydrogen.Based on this principle, the hydrogen measurement parts being coated with Pd-Ag alloy membrane are set in nuclear power plant containment shell.By the hydrogen in hydrogen measurement parts detection nuclear power plant containment shell.
Further, hydrogen measurement parts can be made up of the thread metal film on carrier and carrier.Metal film adopts palladium-silver to make, and has absorb or the characteristic of its conductivity of internal hydrogen molecular changes after release hydrogen in mixed gas according to palladium-silver.
Step 203, process rack gathers the conductivity signal after hydrogen measurement parts absorption release hydrogen.
Further, hydrogen measurement parts are connected with process rack by core level cable, and described process rack gathers hydrogen measurement parts by core level cable and absorbs the conductivity signal after release hydrogen.
Concrete, hydrogen measurement parts are connected with core level cable by cable connector head, are transferred to by conductivity signal on the electrical penetration of nuclear power plant containment shell, and described conductivity signal is transferred in process rack by cable by described electrical penetration.Hydrogen measurement parts by the core level cable of tolerance major accident environmental baseline by electric signal transmission on the electrical penetration of containment, the other end cable then outside containment leads to from electrical penetration in the process rack containment.Adopt the core level cable of tolerance major accident in containment, the insulating material of cable inside adopts high temperature resistant, radiotolerant insulating material.
Further, heating element is used to make hydrogen measurement parts be in steady temperature state.Concrete, the conductivity of palladium-silver can reduce with the rising of temperature more than about 150 DEG C, and at the conductivity not temperature influence substantially of uniform temperature palladium-silver, in conjunction with the impact of temperature on measured value, ensures that hydrogen measurement parts are in steady temperature.
Further, the temperature value of hydrogen measurement parts present position measured by temperature element.
The temperature value surveyed is for compensating palladium-silver measured value.
Step 205, process rack is according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell.
In the containment of nuclear power station, pressure signal is supplied to native system after can being measured by external system.Volumetric concentration due to gas is stressed impact comparatively greatly, particularly saturated vapour gaseous environment.Gas composition can be subject to the impact of water vapor component.Need the density of hydrogen value that the pressure signal introducing containment is measured for compensating it.
After the conductivity signal that process rack outside containment receives palladium-silver and temperature value, through particular algorithm calculation compensation, in algorithm, introduce temperature compensation.In addition, the density of hydrogen of measurement is volumetric concentration, and the volumetric concentration of measurement is comparatively large by the pressure influence of environment, therefore in treating apparatus part, receives outer containment pressure signal, for compensating measure Output rusults, improves precision.The density of hydrogen finally calculated can characterize the density of hydrogen in containment, and considers the impact of temperature and pressure in containment.
The embodiment of the present invention is captured in nuclear power plant containment shell the pressure signal situation in the hydrogen measurement parts conductivity signal and nuclear power plant containment shell that arrange and be coated with Pd-Ag alloy membrane by process rack, can realize the measurement to density of hydrogen in nuclear power plant containment shell.Can realize the measurement of density of hydrogen under aerobic and oxygen-free environment, usable range is wider; Meanwhile, measure all applicable for the density of hydrogen under high temperature, high pressure, high radiation environment, customer service rugged surroundings impact that density of hydrogen is measured well.
Incorporated by reference to the schematic diagram of an embodiment providing density of hydrogen measurement mechanism in a kind of nuclear power plant containment shell referring to Fig. 3, Fig. 3.This device is arranged in nuclear power plant containment shell, comprises probe 301 and transmission unit 303.Wherein,
Probe 301, is coated with Pd-Ag alloy membrane, for absorbing the hydrogen in nuclear power plant containment shell.
The absorption of palladium-silver and the ability of release hydrogen reach equilibrium state, and the conductivity of palladium-silver is proportional to density of hydrogen.
Transmission unit 303, for the conductivity signal of probe 301 is transferred to process rack, to make described process rack according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in described conductivity signal and nuclear power plant containment shell.
Further, this device also comprises heating element, for heating to probe 301, is in steady temperature state to make described probe.Concrete, the conductivity of palladium-silver is proportional to density of hydrogen, and in uniform temperature situation, the absorption of palladium-silver and the ability of release hydrogen comparatively fast will reach equilibrium state, and resistance response is faster.The conductivity of palladium-silver can reduce with the rising of temperature more than about 150 DEG C, and at the conductivity not temperature influence substantially of uniform temperature palladium-silver, in conjunction with the impact of temperature on measured value, in hydrogen measurement assembly, add heating element for ensureing that probe 301 is in steady temperature.
Further, this device also comprises temperature element, the temperature value of measuring sonde 301 present position.Concrete, probe comprises the temperature element of resistance to major accident, and the temperature value surveyed is for compensating palladium-silver measured value.
Further, this device also comprises protective cover, for preventing spray liquid contact sonde 301.
Further, probe 301 is specially and palladium-silver is plated in the formation of resistant to elevated temperatures ceramic sheet.Probe 301 is outer also has the shell adopting sintered stainless steel material.
The embodiment of the present invention is captured in nuclear power plant containment shell the pressure signal situation in the probe conductivity signal and nuclear power plant containment shell that arrange and be coated with Pd-Ag alloy membrane by process rack, can realize the measurement to density of hydrogen in nuclear power plant containment shell.
Incorporated by reference to the schematic diagram of an embodiment providing density of hydrogen measuring system in a kind of nuclear power plant containment shell referring to Fig. 4, Fig. 4.Comprise: hydrogen measurement parts 401 and process rack 403.Concrete:
Hydrogen measurement parts 401, for detecting the hydrogen in nuclear power plant containment shell.
The absorption of palladium-silver and the ability of release hydrogen reach equilibrium state, and the conductivity of palladium-silver is proportional to density of hydrogen.The absorption of the palladium-silver of certain forms and the ability of release hydrogen comparatively fast will reach equilibrium state, and the conductivity of palladium-silver is proportional to density of hydrogen.Based on this principle, the hydrogen measurement parts 401 being coated with Pd-Ag alloy membrane are set in nuclear power plant containment shell.The hydrogen in nuclear power plant containment shell is absorbed by hydrogen measurement parts 401.
Further, hydrogen measurement parts 401 can be made up of the thread metal film on carrier and carrier.Metal film adopts palladium-silver to make, and has absorb or the characteristic of its conductivity of internal hydrogen molecular changes after release hydrogen in mixed gas according to palladium-silver.
Process rack 403, absorbs the conductivity signal after release hydrogen for gathering described hydrogen measurement parts, and according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell.
Hydrogen measurement parts 401 are connected with process rack by core level cable, and process rack 403 gathers hydrogen measurement parts 401 by core level cable and absorbs the conductivity signal after release hydrogen.Hydrogen measurement parts 401 are connected with core level cable by cable connector head.
Hydrogen measurement parts 401 are connected with core level cable by cable connector head, are transferred to by conductivity signal on the electrical penetration of nuclear power plant containment shell, and conductivity signal is transferred in process rack 403 by cable by electrical penetration.Hydrogen measurement parts 401 by the core level cable of tolerance major accident environmental baseline by electric signal transmission on the electrical penetration of containment, the other end cable then outside containment leads to from electrical penetration in the process rack 403 containment.Adopt the core level cable of tolerance major accident in containment, the insulating material of cable inside adopts high temperature resistant, radiotolerant insulating material.
The embodiment of the present invention is captured in nuclear power plant containment shell the pressure signal situation in the hydrogen measurement parts conductivity signal and nuclear power plant containment shell that arrange and be coated with Pd-Ag alloy membrane by process rack, can realize the measurement to density of hydrogen in nuclear power plant containment shell.
Incorporated by reference to the schematic diagram of an embodiment providing density of hydrogen measuring system in a kind of nuclear power plant containment shell referring to Fig. 5, Fig. 5.Comprise: hydrogen measurement parts 501, process rack 503, temperature element 507, protective cover 509 and hydrogen measurement package shell 511.Wherein:
Hydrogen measurement parts 501, for absorbing the hydrogen in nuclear power plant containment shell.
In uniform temperature situation, the absorption of palladium-silver and the ability of release hydrogen comparatively fast will reach equilibrium state, and the conductivity of palladium-silver is proportional to density of hydrogen.Based on this principle, the hydrogen measurement parts 501 being coated with Pd-Ag alloy membrane are set in nuclear power plant containment shell.The hydrogen in nuclear power plant containment shell is absorbed by hydrogen measurement parts 501.
Further, hydrogen measurement parts 501 can be made up of the thread metal film on carrier and carrier.Metal film adopts palladium-silver to make, and has the characteristic absorbing release hydrogen from mixed gas, extract pure hydrogen concentration from mixed gas according to palladium-silver.
Concrete, hydrogen measurement parts 501 can be made up of the metal film on carrier and carrier.Metal film adopts palladium-silver to make, and utilizes palladium-silver to have the feature measurement density of hydrogen absorbing release hydrogen from mixed gas.Palladium-silver different mixing proportion, the corresponding relation under density of hydrogen can be variant, and porpezite existed absorbing phenomenon, and the hydrogen content in pure porpezite solid phase can not form good linear relationship with hydrogen partial pressure.Suitable palladium-silver component ratio will form good linear relationship, and solid phase hydrogen Gas content and conductivity proportional, hydrogen partial pressure and conductivity therefore can be made to form good linear relationship.
Process rack 503, absorbs the conductivity signal after release hydrogen for gathering described hydrogen measurement parts 501, and according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell.
Further, hydrogen measurement parts 501 are connected with process rack 503 by core level cable or the cable of resistance to major accident, and described process rack 503 gathers hydrogen measurement parts 501 by core level cable and absorbs the conductivity signal after release hydrogen.
Concrete, hydrogen measurement parts 501 are connected with core level cable by cable connector head, are transferred to by conductivity signal on the electrical penetration of nuclear power plant containment shell, and described conductivity signal is transferred in process rack 503 by cable by described electrical penetration.Hydrogen measurement parts 501 by the core level cable of tolerance major accident environmental baseline by electric signal transmission on the electrical penetration of containment, the other end cable then outside containment leads to from electrical penetration in the process rack 503 containment.Adopt the core level cable of tolerance major accident in containment, the insulating material of cable inside adopts high temperature resistant, radiotolerant insulating material.
Heating element 505, is arranged in nuclear power plant containment shell, is in steady temperature state for making hydrogen measurement parts.
Further, heating element 505 is used to make hydrogen measurement parts 501 be in steady temperature state.Concrete, the conductivity of palladium-silver can reduce with the rising of temperature more than about 150 DEG C, and at the conductivity not temperature influence substantially of uniform temperature palladium-silver, in conjunction with the impact of temperature on measured value, for ensureing that hydrogen measurement parts 501 are in steady temperature.Temperature element 507, is arranged in nuclear power plant containment shell, for measuring the temperature value of hydrogen measurement parts present position.
Further, the temperature value of hydrogen measurement parts 501 present position measured by temperature element 507.
The temperature value surveyed is for compensating palladium-silver measured value.
Protective cover 509, contacts described hydrogen measurement parts for preventing spray liquid.
Hydrogen measurement package shell 511, covers on the top of probe and the described heating element being coated with Pd-Ag alloy membrane.Namely cover on and measure above hydrogen measurement parts 501.Can prevent outside gasoloid from entering covering palladium-silver surface and affect measurement effect.Also add the anti-spray measure of protective cover, prevent spray liquid from entering, affect measurement result.
Further, after the conductivity signal that the process rack 503 outside containment receives palladium-silver and temperature value, through particular algorithm calculation compensation, in algorithm, temperature compensation is introduced.In addition, the density of hydrogen of measurement is volumetric concentration, and the volumetric concentration of measurement is comparatively large by the pressure influence of environment, therefore in treating apparatus part, receives outer containment pressure signal, for compensating measure Output rusults, improves precision.The density of hydrogen finally calculated can characterize the density of hydrogen in containment, and considers the impact of temperature and pressure in containment.
The implementation method of system and flow process see the embodiment of the method introduced in previous embodiment, can repeat no more herein.
Can find out in conjunction with above detailed description of the present invention, relative to prior art, the present invention at least has following Advantageous Effects: be captured in nuclear power plant containment shell the pressure signal situation in the hydrogen measurement parts conductivity signal and nuclear power plant containment shell arranging and be coated with Pd-Ag alloy membrane by process rack, can realize the measurement to density of hydrogen in nuclear power plant containment shell.Can realize the measurement of density of hydrogen under aerobic and oxygen-free environment, usable range is wider; Meanwhile, measure all applicable for the density of hydrogen under high temperature, high pressure, high radiation environment, customer service rugged surroundings impact that density of hydrogen is measured well.In addition, implementation method is simple, obtains good technique effect.
According to above-mentioned principle, the present invention can also carry out suitable change and amendment to above-mentioned embodiment.Therefore, the present invention is not limited to embodiment disclosed and described above, also should fall in the protection domain of claim of the present invention modifications and changes more of the present invention.In addition, although employ some specific terms in this instructions, these terms just for convenience of description, do not form any restriction to the present invention.

Claims (26)

1. a density of hydrogen measuring method in nuclear power plant containment shell, is characterized in that, described method comprises:
The hydrogen measurement parts being coated with Pd-Ag alloy membrane are set in nuclear power plant containment shell;
Process rack gathers the conductivity signal after hydrogen measurement parts absorption release hydrogen;
Process rack is according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell.
2. method according to claim 1, is characterized in that, described method also comprises:
Described hydrogen measurement parts are connected with process rack by core level cable, and described process rack gathers hydrogen measurement parts by core level cable and absorbs the conductivity signal after release hydrogen.
3. method according to claim 2, is characterized in that, described method also comprises:
Heating element is used to make hydrogen measurement parts be in steady temperature state.
4. method according to claim 3, is characterized in that, described method also comprises:
The temperature value of hydrogen measurement parts present position measured by temperature element.
5. method according to claim 4, is characterized in that, described process rack, according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell, comprising:
Process rack is according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered, described temperature value and nuclear power plant containment shell.
6. method according to claim 5, is characterized in that, described process rack, according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered, described temperature value and nuclear power plant containment shell, also comprises:
Process rack is according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered, described temperature value, temperature compensation value and nuclear power plant containment shell.
7. method according to claim 6, is characterized in that, described in nuclear power plant containment shell arrange be coated with the hydrogen measurement parts of Pd-Ag alloy membrane before, also comprise:
Palladium-silver is plated in resistant to elevated temperatures ceramic sheet.
8. method according to claim 7, is characterized in that, described method also comprises:
Described hydrogen measurement parts shell adopts sintered stainless steel material.
9. method according to claim 8, is characterized in that, described method also comprises:
The protective cover of anti-spray liquid spray is also provided with above described hydrogen measurement parts.
10. a density of hydrogen measurement mechanism in nuclear power plant containment shell, is characterized in that, described device is arranged in nuclear power plant containment shell, and this device comprises:
Be coated with the probe of Pd-Ag alloy membrane, for detecting the hydrogen in nuclear power plant containment shell;
Transmission unit, for the conductivity signal of described probe is transferred to process rack, to make described process rack according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in described conductivity signal and nuclear power plant containment shell.
11. devices according to claim 10, is characterized in that, described device also comprises:
Heating element, for heating to described probe, is in steady temperature state to make described probe.
12. devices according to claim 11, is characterized in that, described device also comprises:
Temperature element, measures the temperature value of described probe present position.
13. devices according to claim 12, is characterized in that, described device also comprises:
Protective cover, contacts described probe for preventing spray liquid.
14. devices according to claim 13, is characterized in that, the conductivity signal of described probe is transferred to process rack by described transmission unit, comprising:
Transmission unit by the conductivity signal of described probe by core level cable transmission on the electrical penetration of containment, then to be led to the process rack containment from described electrical penetration by the other end cable outside containment.
15. devices according to any one of claim 10-14, is characterized in that, described probe is specially and palladium-silver is plated in resistant to elevated temperatures ceramic sheet is formed.
16. devices according to claim 15, is characterized in that, described probe also comprises:
Adopt the shell of sintered stainless steel material.
17. devices according to claim 16, is characterized in that, described device also comprises:
Hydrogen measurement package shell, is coated with the probe of Pd-Ag alloy membrane and the top of described heating element described in covering on.
Density of hydrogen measuring system in 18. 1 kinds of nuclear power plant containment shells, is characterized in that, described system comprises:
Hydrogen measurement parts, for detecting the hydrogen in nuclear power plant containment shell;
Process rack, absorbs the conductivity signal after release hydrogen for gathering described hydrogen measurement parts, and according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell.
19. systems according to claim 18, is characterized in that, described hydrogen measurement parts are arranged in nuclear power plant containment shell, and outside surface is coated with Pd-Ag alloy membrane.
20. systems according to claim 19, is characterized in that, described hydrogen measurement parts are connected with process rack by core level cable, and described process rack gathers hydrogen measurement parts by core level cable and absorbs the conductivity signal after release hydrogen.
21. systems according to claim 20, is characterized in that, described system also comprises:
Heating element, is arranged in nuclear power plant containment shell, is in steady temperature state for making hydrogen measurement parts.
22. systems according to claim 21, is characterized in that, described system also comprises: temperature element, are arranged in nuclear power plant containment shell, for measuring the temperature value of hydrogen measurement parts present position.
23. systems according to claim 21, is characterized in that, described system also comprises:
Protective cover, contacts described hydrogen measurement parts for preventing spray liquid.
24. systems according to claim 23, it is characterized in that, described process rack gathers the conductivity signal after described hydrogen measurement parts absorption release hydrogen, and according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered and nuclear power plant containment shell, comprising:
Described process rack is according to density of hydrogen in the pressure signal determination nuclear power plant containment shell in the described conductivity signal gathered, described temperature value and nuclear power plant containment shell.
25. systems according to claim 24, is characterized in that, described hydrogen measurement parts are connected with process rack by core level cable, also comprise:
Hydrogen measurement parts are connected with core level cable by cable connector head.
26. systems according to claim 25, is characterized in that, described process rack gathers the conductivity signal after hydrogen measurement parts absorption release hydrogen, also comprises:
Hydrogen measurement parts are connected with core level cable by cable connector head, are transferred to by conductivity signal on the electrical penetration of nuclear power plant containment shell, and described conductivity signal is transferred in process rack by cable by described electrical penetration.
CN201410742292.6A 2014-12-08 2014-12-08 Method, device and system for measuring concentration of hydrogen in nuclear power station containment vessel Pending CN104538070A (en)

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