CN106092351B - Nuclear power station pipeline inner wall temperature measurement method and device - Google Patents
Nuclear power station pipeline inner wall temperature measurement method and device Download PDFInfo
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- CN106092351B CN106092351B CN201610364193.8A CN201610364193A CN106092351B CN 106092351 B CN106092351 B CN 106092351B CN 201610364193 A CN201610364193 A CN 201610364193A CN 106092351 B CN106092351 B CN 106092351B
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
- G01K7/00—Measuring temperature based on the use of electric or magnetic elements directly sensitive to heat ; Power supply therefor, e.g. using thermoelectric elements
- G01K7/02—Measuring temperature based on the use of electric or magnetic elements directly sensitive to heat ; Power supply therefor, e.g. using thermoelectric elements using thermoelectric elements, e.g. thermocouples
Abstract
The invention discloses a kind of nuclear power station pipeline inner wall temperature measurement methods, comprising: establishes unit transient heat conduction model；Utilize unit transient heat conduction model inference numerical computation method；Measure pipeline outer wall temperature；Inner wall of the pipe temperature is calculated with numerical computation method as known quantity in the pipeline outer wall temperature that measurement is obtained.Compared with prior art, the present invention is not necessarily to the aperture on tested pipeline, under the premise of not destroying one loop of nuclear power station pipeline (including radioactivity liquid) structure, accurately know the temperature distribution information of inner wall of the pipe, radioactivity containing is more effectively realized, the safety of nuclear power station operation is improved；Meanwhile the present invention directly measures pipeline outer wall temperature rather than measures the temperature of liquid in pipeline, avoids the calculating of the coefficient of heat transfer, significantly improves the calculating accuracy of tube wall temperature field.In addition, the invention also discloses a kind of nuclear power station pipeline inner wall temperature measuring devices.
Description
Technical field
The invention belongs to nuclear power station field of temperature measurement, it is more particularly related to a kind of nuclear power station pipeline inner wall
Thermometry and device.
Background technique
In the theoretical system of nuclear power station aging and life-span management, Supervision that key equipment aging degrades the result is that after
The continuous basis for carrying out ageing equipment state and equipment life assessment.Main agine mechaism includes tired existing for nuclear power station key equipment
Labor, corrosion, wear, radiation embrittlement and heat ageing etc., wherein fatigue is to cause the most important original of nuclear power station key equipment failure
One of because.Current worldwide nuclear power station has occurred that series reaction reactor coolant pipeline thing because of caused by fatigue
Part, these events on nuclear plant safety, economically operation produce influence, it is serious or even cause nuclear power station unplanned shutdown.
In general, nuclear power station can carry out analysis of fatigue to core level-one pipeline according to code requirement, still in project engineering stage
The analysis result cannot really reflect the active loss situation of pipeline, because being counted in the analytic process using design transient
It calculates, and nuclear power station actual motion transient state has a certain distance compared with numerically with design transient.In order to obtain the practical fortune of pipeline
The data of row transient state, grasp the true fatigue state of pipeline, and actual damage state based on equipment, optimize operating standard and
Labour checks outline, rationally excavates the safety margin of key conduit fatigue design, examines for nuclear power station periodical safety or equipment is lengthened the life
True data supporting is provided, part nuclear power country has carried out the R&D work of nuclear power station fatigue monitoring system.
The fatigue of one loop of nuclear power station pressure boundary pipeline and equipment, metal caused by mainly changing due to operating condition
Caused by thermal stress caused by alternating hot and cold, therefore, the accurate temperature alternating for measuring primary Ioops pressure boundary pipeline is tired prison
The precondition of analysis of fatigue in examining system.
The fatigue monitoring system of known nuclear power station is to utilize existing DCS instrument monitoring temperature.Wherein, in pipe-line system
The acquisition of wall actual motion temperature data is by the way that probe flow measurement matter temperature is drilled and be inserted on pipeline.To obtain heat fatigue
The input data of analysis, fatigue monitoring system are built by the existing a small amount of measuring instrumentss on-line measurement data of one loop of nuclear power station
Measurement point temperature data corresponding with sensitizing range demand point library under a vertical different transient, derives sensitizing range point indirectly
Inner wall temperature.But all there is apparent defect no matter from the point of view of safety or accuracy in this mode: on the one hand, in quilt
Aperture on test tube road increases the probability of tube wall initial imperfection generation, this will affect nuclear power so that the stress that pipeline generates is concentrated
Stand primary side high energy pipeline mechanical property, even resulted in when serious pipeline occur fracture accident；On the other hand, it needs to pass through
Liquid temperature is difficult to determine via calculation of thermodynamics tube wall temperature field, but since the coefficient of heat transfer of liquid and inner wall of the pipe is one
Parameter so that the computational accuracy of tube wall temperature field is received and is seriously affected.
In view of this, it is necessory to provide a kind of nuclear power station pipeline inner wall temperature measurement method for being able to solve the above problem
And device.
Summary of the invention
It is an object of the invention to: overcome the deficiencies of the prior art and provide a kind of nuclear power station pipeline inner wall temperature measurement side
Method and device.
In order to achieve the above-mentioned object of the invention, the present invention provides a kind of nuclear power station pipeline inner wall temperature measurement methods, comprising:
Establish unit transient heat conduction model；
Utilize unit transient heat conduction model inference numerical computation method；
Measure pipeline outer wall temperature；
The pipeline outer wall temperature that measurement is obtained is calculated in pipeline as known quantity with the numerical computation method
Wall temperature.
It is described to establish unit transient heat conduction as a kind of improvement of nuclear power station pipeline inner wall temperature measurement method of the present invention
Model is that unit transient heat conduction model is established by finite element software.
It is described to be established by finite element software as a kind of improvement of nuclear power station pipeline inner wall temperature measurement method of the present invention
Unit transient heat conduction model, including finite element model is established according to pipeline section actual size.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement method of the present invention, the pipeline section actual size packet
Include the outer diameter and wall thickness dimension of pipeline.
It is described to be established by finite element software as a kind of improvement of nuclear power station pipeline inner wall temperature measurement method of the present invention
Unit transient heat conduction model further includes the inner wall of the pipe one unit thermal shock load of load in the finite element model, benefit
The pipeline outer wall unit transient temperature situation of change of the finite element model is simulated with finite element software.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement method of the present invention, the thermal shock of one unit is carried
Lotus is to rise to 10 DEG C from 0 DEG C within the 1s time, and constant at 10 DEG C.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement method of the present invention, the unit transient heat conduction model
It is the pipeline outer wall of the finite element model when the inner wall of the pipe of the finite element model loads a unit thermal shock load
The case where unit transient temperature changes over time.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement method of the present invention, the unit transient heat conduction model
It is the case where pipeline outer wall unit transient temperature changes over time when inner wall of the pipe loads a unit thermal shock load.
It is described to utilize unit transient heat conduction as a kind of improvement of nuclear power station pipeline inner wall temperature measurement method of the present invention
Model inference numerical computation method is realized by following steps:
Assuming that inner wall unit transient temperature is 0,10,10,10 ... when time step is 1 second, i-th second, the practical temperature of inner wall
Degree is T (i in reality), wherein i=0, and at the 1,2,3 ..., the 0th second, outer wall actual temperature is (real outer 0) T；
When calculating i-th second, inner wall actual temperature increment T (i in reality)-T (i-1 in reality), wherein i=0,1,2,3 ...；
When calculating i-th second, (T is (in reality by the multiple proportion Ni=of inner wall actual temperature increment and inner wall unit transient temperature
I)-T (i-1 in reality))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature when being obtained i-th second according to inner wall unit transient temperature and unit transient heat conduction model
T (single outer i), wherein i=1,2,3 ...；
It is (single to calculate outer wall actual temperature T (real outer ij)=T that i-th second inner wall actual temperature increment is generated in the jth second
Outer j) * Ni, wherein i=1,2,3 ..., j=1,2,3 ...；
Calculate the outer wall actual temperature of jth secondWherein j
=1,2,3 ..., k=1,2,3 ..., j+1-k=1,2,3 ...；
Simultaneous T (real outer ij)=T (single outer j) * Ni with
I-th second inner wall actual temperature T (i in reality) is solved, wherein i=0,1,2,3 ..., obtained according in the calculating of outer wall actual temperature
The calculation formula of wall actual temperature.
In order to achieve the above-mentioned object of the invention, the present invention also provides a kind of nuclear power station pipeline inner wall temperature measuring device, packets
It includes:
Modeling module for establishing unit transient heat conduction model, and utilizes unit transient heat conduction model inference numerical value
Calculation method；
Temperature-measuring module, for measuring pipeline outer wall temperature；
Computing module is derived by for that will measure obtained pipeline outer wall temperature as known quantity with modeling module
Numerical computation method calculate pipeline inner wall temperature.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring device of the present invention, the modeling module establishes unit wink
State heat conduction model is that unit transient heat conduction model is established by finite element software.
It is described to be established by finite element software as a kind of improvement of nuclear power station pipeline inner wall temperature measuring device of the present invention
Unit transient heat conduction model, including finite element model is established according to pipeline section actual size.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring device of the present invention, the pipeline section actual size packet
Include the outer diameter and wall thickness dimension of pipeline.
It is described to be established by finite element software as a kind of improvement of nuclear power station pipeline inner wall temperature measuring device of the present invention
Unit transient heat conduction model further includes the inner wall of the pipe one unit thermal shock load of load in the finite element model, benefit
The pipeline outer wall unit transient temperature situation of change of the finite element model is simulated with finite element software.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring device of the present invention, the thermal shock of one unit is carried
Lotus is to rise to 10 DEG C from 0 DEG C within the 1s time, and constant at 10 DEG C.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring device of the present invention, the unit transient heat conduction model
It is the pipeline outer wall of the finite element model when the inner wall of the pipe of the finite element model loads a unit thermal shock load
The case where unit transient temperature changes over time.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring device of the present invention, the unit of the modeling module foundation
Transient heat conduction model is when inner wall of the pipe loads a unit thermal shock load, and pipeline outer wall unit transient temperature is at any time
The case where variation.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring device of the present invention, the modeling module utilizes unit wink
State heat conduction model derives numerical computation method and is realized by following steps:
Assuming that inner wall unit transient temperature is 0,10,10,10 ... when time step is 1 second, i-th second, the practical temperature of inner wall
Degree is T (i in reality), wherein i=0, and at the 1,2,3 ..., the 0th second, outer wall actual temperature is (real outer 0) T；
When calculating i-th second, inner wall actual temperature increment T (i in reality)-T (i-1 in reality), wherein i=0,1,2,3 ...；
When calculating i-th second, (T is (in reality by the multiple proportion Ni=of inner wall actual temperature increment and inner wall unit transient temperature
I)-T (i-1 in reality))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature when being obtained i-th second according to inner wall unit transient temperature and unit transient heat conduction model
T (single outer i), wherein i=1,2,3 ...；
It is (single to calculate outer wall actual temperature T (real outer ij)=T that i-th second inner wall actual temperature increment is generated in the jth second
Outer j) * Ni, wherein i=1,2,3 ..., j=1,2,3 ...；
Calculate the outer wall actual temperature of jth secondWherein j
=1,2,3 ..., k=1,2,3 ..., j+1-k=1,2,3 ...；
Simultaneous T (real outer ij)=T (single outer j) * Ni with
I-th second inner wall actual temperature T (i in reality) is solved, wherein i=0,1,2,3 ..., obtained according in the calculating of outer wall actual temperature
The calculation formula of wall actual temperature.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring device of the present invention, the temperature-measuring module includes heat
Galvanic couple, the installation of TC is in pipeline outer wall face.
Compared with prior art, the present invention is by measurement pipeline outer wall temperature, and pipeline is calculated in founding mathematical models
Inner wall temperature, the present invention are not necessarily to the aperture on tested pipeline, under the premise of not destroying one loop of nuclear power station pipeline configuration, accurately
The temperature distribution information of inner wall of the pipe is known on ground, more effectively realizes radioactivity containing, improves the safety of nuclear power station operation
Property；Meanwhile the present invention directly measures pipeline outer wall temperature rather than measures the temperature of liquid in pipeline, avoids the meter of the coefficient of heat transfer
It calculates, significantly improves the calculating accuracy in inner wall of the pipe temperature field.
Detailed description of the invention
With reference to the accompanying drawings and detailed description, to nuclear power station pipeline inner wall temperature measurement method of the present invention, device and
Its advantageous effects is described in detail.
Fig. 1 is the flow chart of nuclear power station pipeline inner wall temperature measurement method of the present invention.
Fig. 2 is the structural schematic diagram of the finite element model of nuclear power station pipeline inner wall temperature measurement method of the present invention.
Fig. 3 is that the finite element model of nuclear power station pipeline inner wall temperature measurement method of the present invention loads the signal of thermal shock load
Figure.
Fig. 4 is the schematic diagram of the unit transient heat conduction model of nuclear power station pipeline inner wall temperature measurement method of the present invention.
Specific embodiment
It is clear in order to be more clear the purpose of the present invention, technical solution and advantageous effects, below in conjunction with attached drawing and
Specific embodiment, the present invention will be described in further detail.It should be understood that specific implementation described in this specification
Mode is not intended to limit the present invention just for the sake of explaining the present invention.
Referring to Fig. 1, nuclear power station pipeline inner wall temperature measurement method of the present invention includes:
Step 101, unit transient heat conduction model is established；
Step 103, unit transient heat conduction model inference numerical computation method is utilized；
Step 105, pipeline outer wall temperature is measured；
Step 107, pipeline outer wall temperature measurement obtained is calculated as known quantity with the numerical computation method
To inner wall of the pipe temperature.
The following are an embodiments of nuclear power station pipeline inner wall temperature measurement method of the present invention.
Fig. 2 and Fig. 3 are please referred to, in finite element software, is established such as according to pipeline section actual size (outer diameter and wall thickness)
Finite element model shown in Fig. 2 loads a unit thermal shock load as shown in Figure 3 in the inner wall of the pipe of finite element model,
Simulate the pipeline outer wall unit transient temperature situation of change of finite element model.Wherein, a unit thermal shock load is in 1s
It is interior that 10 DEG C are risen to from 0 DEG C and constant at 10 DEG C.
Referring to Fig. 4, being the pipeline in finite element model by the unit transient heat conduction model that finite element software is established
When inner wall loads a unit thermal shock load, feelings that the pipeline outer wall unit transient temperature of finite element model changes over time
Condition.In Fig. 4, the longitudinal axis indicates temperature, and horizontal axis indicates the time, and zone circle curve indicates that outer wall unit transient temperature, dendrite indicate
Unit thermal shock load, i.e. inner wall unit transient temperature.
Below with unit transient heat conduction model inference numerical computation method.
Assuming that inner wall unit transient temperature is 0,10,10,10 ... when time step is 1 second, i-th second, the practical temperature of inner wall
Degree is T (i in reality), wherein i=0, and at the 1,2,3 ..., the 0th second, outer wall actual temperature is (real outer 0) T；
When calculating i-th second, inner wall actual temperature increment T (i in reality)-T (i-1 in reality), wherein i=0,1,2,3 ...；
When calculating i-th second, (T is (in reality by the multiple proportion Ni=of inner wall actual temperature increment and inner wall unit transient temperature
I)-T (i-1 in reality))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature when being obtained i-th second according to inner wall unit transient temperature and unit transient heat conduction model
T (single outer i), wherein i=1,2,3 ...；
Due in the case where different thermal shock load, the ratio between outer wall actual temperature increment and outer wall unit transient temperature etc.
In the ratio between inner wall actual temperature increment and inner wall unit transient temperature, therefore i-th second inner wall actual temperature increment can be calculated
Outer wall actual temperature T (real outer ij)=T (singly outer j) the * Ni generated in the jth second, wherein i=1,2,3 ..., j=1,2,
3……；
Calculate the outer wall actual temperature of jth secondWherein j
=1,2,3 ..., k=1,2,3 ..., j+1-k=1,2,3 ...；
Simultaneous T (real outer ij)=T (single outer j) * Ni with
I-th second inner wall actual temperature T (i in reality) is solved, wherein i=0,1,2,3 ..., obtained according in the calculating of outer wall actual temperature
The calculation formula of wall actual temperature.
In order to illustrate more clearly of using unit transient heat conduction model inference numerical computation method process, below by way of
Table 1 provides preceding 3 seconds derivation processes.It is deduced from step 1 to step 12 in table 1, the result of step 11 is substituted into step 12, just
To the formula for the numerical computation method for calculating inner wall of the pipe actual temperature according to pipeline outer wall actual temperature.
Table 1, numerical computation method derive step example
Nuclear power station pipeline inner wall temperature measuring device of the present invention includes:
Modeling module for establishing unit transient heat conduction model, and utilizes unit transient heat conduction model inference numerical value
Calculation method；
Temperature-measuring module, for measuring pipeline outer wall temperature；
Computing module is derived by for that will measure obtained pipeline outer wall temperature as known quantity with modeling module
Numerical computation method calculate pipeline inner wall temperature.
Wherein, modeling module is for realizing step 101 and step in nuclear power station pipeline inner wall temperature measurement method of the present invention
103 method, embodiments thereof are identical as step 101 and step 103, and details are not described herein again.
Temperature-measuring module includes thermocouple, and the installation of TC is in pipeline outer wall face.
Computing module for realizing step 107 in nuclear power station pipeline inner wall temperature measurement method of the present invention method, in fact
It is identical as step 107 to apply mode, details are not described herein again.
It can be seen that compared with the existing technology in conjunction with the above detailed description of the present invention, in nuclear power station pipeline of the present invention
The advantageous effects of wall temperature measurement method and device include but is not limited to:
(1) it is accurately obtained under the premise of not destroying one loop of nuclear power station pipeline configuration without the aperture on tested pipeline
Know the temperature distribution information of inner wall of the pipe, more effectively realizes radioactivity containing, improve the safety of nuclear power station operation；
(2) it directly measures pipeline outer wall temperature rather than measures the temperature of liquid in pipeline, avoid the calculating of the coefficient of heat transfer,
And the higher FInite Element founding mathematical models of computational accuracy are used, the calculating for significantly improving inner wall of the pipe temperature field is accurate
Property；
(3) inner wall of the pipe temperature information is obtained in real time, and then calculates monitoring point pipeline tired coefficient of utilization in real time, it is right
Nuclear power station optimization operation has directive significance；
(4) observation technique is convenient for identify that it is convenient that the frequency of design transient provides by the tube wall temperature of acquisition
The system reform upgrades caused transient changing；
(5) when upstream master, penetrating pipeline and needing to shut off using valve because of operation, according to the variation of pipeline internal temperature, make
The auxiliary tool qualitatively judged for upstream line valve (gate valve, shut-off valve etc.) leakage.
According to above-mentioned principle, the present invention can also be made appropriate changes and modifications to the above embodiments.Therefore, this hair
It is bright to be not limited to specific embodiment disclosed and described above, some modifications and changes of the invention should also be as to fall into this
In the scope of protection of the claims of invention.In addition, although being used some specific terms in this specification, these terms
Merely for convenience of description, it does not limit the present invention in any way.
Claims (7)
1. a kind of nuclear power station pipeline inner wall temperature measurement method, which is characterized in that the described method comprises the following steps:
Unit transient heat conduction model is established by finite element software, loads a list including the inner wall of the pipe in finite element model
Position thermal shock load, is changed over time using the pipeline outer wall unit transient temperature that finite element software simulates the finite element model
The case where, wherein a unit thermal shock load is to rise to 10 DEG C from 0 DEG C within the 1s time, and constant at 10 DEG C；
Using unit transient heat conduction model inference numerical computation method, step is realized are as follows:
Assuming that inner wall unit transient temperature is 0,10,10,10 ... when time step is 1 second, i-th second, inner wall actual temperature is
T (i in reality), wherein i=0, at the 1,2,3 ..., the 0th second, outer wall actual temperature is (real outer 0) T；
When calculating i-th second, inner wall actual temperature increment T (i in reality)-T (i-1 in reality), wherein i=0,1,2,3 ...；
When calculating i-th second, multiple proportion Ni=(T (i in reality)-T of inner wall actual temperature increment and inner wall unit transient temperature
(i-1 in reality))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature T when being obtained i-th second according to inner wall unit transient temperature and unit transient heat conduction model is (single
It is outer i), wherein i=1,2,3 ...；
It is (single outer to calculate outer wall actual temperature T (real outer ij)=T that i-th second inner wall actual temperature increment is generated in the jth second
J) * Ni, wherein i=1,2,3 ..., j=1,2,3 ...；
Wherein
J=1,2,3 ..., k=1,2,3 ..., j+1-k=1,2,3 ...；
I-th second inner wall actual temperature T (i in reality) is solved, wherein i=0,1,2,3 ..., obtain according to outer wall actual temperature meter
Calculate the calculation formula of inner wall actual temperature；
Measure pipeline outer wall temperature；
Inner wall of the pipe temperature is calculated with the numerical computation method as known quantity in the pipeline outer wall temperature that measurement is obtained
Degree.
2. nuclear power station pipeline inner wall temperature measurement method according to claim 1, which is characterized in that described to pass through finite element
Software establishes unit transient heat conduction model, including establishes finite element model according to pipeline section actual size.
3. nuclear power station pipeline inner wall temperature measurement method according to claim 2, which is characterized in that the pipeline section is real
Border size includes the outer diameter and wall thickness dimension of pipeline.
4. a kind of nuclear power station pipeline inner wall temperature measuring device, which is characterized in that described device includes:
Modeling module for establishing unit transient heat conduction model by finite element software, and utilizes unit transient heat conduction mould
Type derives numerical computation method；It is described that establish unit transient heat conduction model by finite element software include in finite element model
Inner wall of the pipe loads a unit thermal shock load, and the pipeline outer wall unit of the finite element model is simulated using finite element software
The case where transient temperature changes over time, wherein a unit thermal shock load is to rise to 10 DEG C from 0 DEG C within the 1s time,
And it is constant at 10 DEG C；
Temperature-measuring module, for measuring pipeline outer wall temperature；
Computing module, for obtained pipeline outer wall temperature will to be measured as known quantity, the number being derived by with modeling module
Value calculating method calculates pipeline inner wall temperature；
The modeling module is realized using unit transient heat conduction model inference numerical computation method by following steps:
Assuming that inner wall unit transient temperature is 0,10,10,10 ... when time step is 1 second, i-th second, inner wall actual temperature is
T (i in reality), wherein i=0, at the 1,2,3 ..., the 0th second, outer wall actual temperature is (real outer 0) T；
When calculating i-th second, inner wall actual temperature increment T (i in reality)-T (i-1 in reality), wherein i=0,1,2,3 ...；
When calculating i-th second, multiple proportion Ni=(T (i in reality)-T of inner wall actual temperature increment and inner wall unit transient temperature
(i-1 in reality))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature T when being obtained i-th second according to inner wall unit transient temperature and unit transient heat conduction model is (single
It is outer i), wherein i=1,2,3 ...；
It is (single outer to calculate outer wall actual temperature T (real outer ij)=T that i-th second inner wall actual temperature increment is generated in the jth second
J) * Ni, wherein i=1,2,3 ..., j=1,2,3 ...；
Wherein
J=1,2,3 ..., k=1,2,3 ..., j+1-k=1,2,3 ...；
I-th second inner wall actual temperature T (i in reality) is solved, wherein i=0,1,2,3 ..., obtain according to outer wall actual temperature meter
Calculate the calculation formula of inner wall actual temperature.
5. nuclear power station pipeline inner wall temperature measuring device according to claim 4, which is characterized in that described to pass through finite element
Software establishes unit transient heat conduction model, including establishes finite element model according to pipeline section actual size.
6. nuclear power station pipeline inner wall temperature measuring device according to claim 5, which is characterized in that the pipeline section is real
Border size includes the outer diameter and wall thickness dimension of pipeline.
7. nuclear power station pipeline inner wall temperature measuring device according to claim 4, which is characterized in that the temperature measures mould
Block includes thermocouple, and the installation of TC is in pipeline outer wall face.
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| CN111141400B (en) * | 2019-12-04 | 2021-08-24 | 深圳中广核工程设计有限公司 | Method for measuring temperature of pipe wall of thermal fatigue sensitive area of bent pipe of nuclear power station |
| CN112765797A (en) * | 2021-01-08 | 2021-05-07 | 深圳中广核工程设计有限公司 | Straight pipeline inner wall surface temperature measurement and transient recognition method and computer terminal |
| CN114061835A (en) * | 2021-10-22 | 2022-02-18 | 中核核电运行管理有限公司 | Nuclear power station nuclear island valve leakage monitoring system and method |
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