CN106092351A - nuclear power station pipeline inner wall temperature measuring method and device - Google Patents
nuclear power station pipeline inner wall temperature measuring method and device Download PDFInfo
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- CN106092351A CN106092351A CN201610364193.8A CN201610364193A CN106092351A CN 106092351 A CN106092351 A CN 106092351A CN 201610364193 A CN201610364193 A CN 201610364193A CN 106092351 A CN106092351 A CN 106092351A
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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 measuring method, including: set up unit transient heat conduction model；Utilize unit transient heat conduction model inference numerical computation method；Measure pipeline outer wall temperature；Pipeline outer wall temperature measurement obtained, as known quantity, uses numerical computation method to be calculated inner-walls of duct temperature.Compared with prior art, the present invention is without perforate on tested pipeline, on the premise of not destroying one loop of nuclear power station pipeline (including radioactivity liquid) structure, know the temperature distribution information of inner-walls of duct exactly, more effectively achieve radioactivity to contain, improve the safety that nuclear power station runs；Meanwhile, the present invention directly measures pipeline outer wall temperature and the temperature of liquid in non-measured pipeline, it is to avoid the calculating of the coefficient of heat transfer, significantly improves the calculating accuracy of tube wall temperature field.Additionally, the invention also discloses a kind of nuclear power station pipeline inner wall temperature measurement apparatus.
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 inwall
Thermometry and device.
Background technology
In the theoretical system with life-span management aging at nuclear power station, after the Supervision result that key equipment is aging to degrade is
The continuous basis carrying out ageing equipment state and assessment equipment life.The main agine mechaism that nuclear power station key equipment exists includes tired
Labor, corrosion, wear, radiation embrittlement and heat ageing etc., wherein fatigue is to cause the inefficacy of nuclear power station key equipment topmost former
One of because of.Current worldwide nuclear power station has occurred that the thing that series reaction reactor coolant pipeline causes because of tired
Part, these events create impact to nuclear plant safety, economically operation, and serious even causes nuclear power station unplanned shutdown.
Generally, nuclear power station, in project engineering stage, can carry out analysis of fatigue according to code requirement to core one-level pipeline, but
This analysis result can not truly reflect the active loss situation of pipeline, because using design transient to count during this analysis
Calculate, and nuclear power station actual motion transient state and design transient numerically compared with have a certain distance.In order to obtain the actual 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 margin of safety of key conduit Fatigue Design, examines for nuclear power station periodical safety or equipment is lengthened the life
Thering is provided real data supporting, part nuclear power country has carried out the R&D work of nuclear power station fatigue monitoring system.
One loop of nuclear power station pressure boundary pipeline and the fatigue of equipment, change the metal caused mainly due to operating condition
The thermal stress that alternating hot and cold causes causes, and therefore, the temperature alternating accurately 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 tubing
The collection of wall actual motion temperature data is by holing and inserting probe flow measurement matter temperature on pipeline.For obtaining heat exhaustion
The input data analyzed, fatigue monitoring system passes through the existing a small amount of measuring instruments on-line measurement data of one loop of nuclear power station, builds
The temperature data storehouse that point is corresponding with sensitizing range demand point is measured under a vertical different transient, indirect derivation sensitizing range point
Inner wall temperature.But, no matter from the point of view of safety or accuracy, all there is obvious defect: on the one hand, at quilt in this mode
Perforate on test tube road so that the stress that pipeline produces is concentrated, adds the probability that tube wall initial imperfection produces, and this will affect nuclear power
Stand the mechanical property of high energy pipeline of primary side, time serious, even result in pipeline generation fracture accident；On the other hand, need to pass through
Liquid temperature is via calculation of thermodynamics tube wall temperature field, but is difficult to determine owing to the coefficient of heat transfer of liquid with inner-walls of duct is one
Parameter so that the computational accuracy of tube wall temperature field receives and has a strong impact on.
In view of this, a kind of nuclear power station pipeline inner wall temperature measuring method that can solve the problem that the problems referred to above of necessary offer
And device.
Summary of the invention
It is an object of the invention to: overcome the deficiencies in the prior art, it is provided that a kind of nuclear power station pipeline inner wall temperature measurement side
Method and device.
In order to realize foregoing invention purpose, the invention provides a kind of nuclear power station pipeline inner wall temperature measuring method, including:
Set up unit transient heat conduction model；
Utilize unit transient heat conduction model inference numerical computation method；
Measure pipeline outer wall temperature；
Pipeline outer wall temperature measurement obtained, as known quantity, uses described numerical computation method to be calculated in pipeline
Wall temperature.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring method of the present invention, described set up unit transient heat conduction
Model, is to set up unit transient heat conduction model by finite element software.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring method of the present invention, described set up by finite element software
Unit transient heat conduction model, sets up FEM (finite element) model including according to pipeline section actual size.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring method of the present invention, described pipeline section actual size bag
Include outside dimension and the wall thickness dimension of pipeline.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring method of the present invention, described set up by finite element software
Unit transient heat conduction model, the inner-walls of duct being additionally included in described FEM (finite element) model loads a unit thermal shock load, profit
The pipeline outer wall unit transient temperature situation of change of described FEM (finite element) model is simulated with finite element software.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring method of the present invention, the thermal shock of one unit carries
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 method of the present invention, described unit transient heat conduction model
It is when the inner-walls of duct of described FEM (finite element) model loads a unit thermal shock load, the pipeline outer wall of described FEM (finite element) model
The time dependent situation of unit transient temperature.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring method of the present invention, described unit transient heat conduction model
It is when inner-walls of duct loads a unit thermal shock load, the time dependent situation of pipeline outer wall unit transient temperature.
As a kind of improvement of nuclear power station pipeline inner wall temperature measuring method of the present invention, described utilize unit transient heat conduction
Model inference numerical computation method is realized by following steps:
Assuming that time step is 1 second, when i-th second, inwall unit transient temperature is 0,10,10,10 ..., inwall reality temperature
Degree is T (i in real), wherein i=0,1,2,3 ... and, when the 0th second, outer wall actual temperature is T (real outer 0)；
When calculating i-th second, inwall actual temperature increment T (i in real)-T (i-1 in real), wherein i=0,1,2,3 ...；
When calculating i-th second, (T is (real interior for inwall actual temperature increment and the multiple proportion Ni=of inwall unit transient temperature
I)-T (i-1 in real))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature when obtaining i-th second according to inwall unit transient temperature and unit transient heat conduction model
T (single outer i), wherein i=1,2,3 ...；
Calculate outer wall actual temperature T (the real outer ij)=T (list that the inwall actual temperature increment of i-th second produces when 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
Solve inwall actual temperature T (real in i) of i-th second, wherein i=0,1,2,3 ..., in obtaining calculating according to outer wall actual temperature
The computing formula of wall actual temperature.
In order to realize foregoing invention purpose, present invention also offers a kind of nuclear power station pipeline inner wall temperature measurement apparatus, bag
Include:
MBM, is used for setting up unit transient heat conduction model, and utilizes unit transient heat conduction model inference numerical value
Computational methods；
Temperature-measuring module, is used for measuring pipeline outer wall temperature；
Computing module, is derived by as known quantity, utilization MBM for pipeline outer wall temperature measurement obtained
Numerical computation method calculate pipeline inner wall temperature.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement apparatus of the present invention, described MBM sets up unit wink
State heat conduction model, is to set up unit transient heat conduction model by finite element software.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement apparatus of the present invention, described set up by finite element software
Unit transient heat conduction model, sets up FEM (finite element) model including according to pipeline section actual size.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement apparatus of the present invention, described pipeline section actual size bag
Include outside dimension and the wall thickness dimension of pipeline.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement apparatus of the present invention, described set up by finite element software
Unit transient heat conduction model, the inner-walls of duct being additionally included in described FEM (finite element) model loads a unit thermal shock load, profit
The pipeline outer wall unit transient temperature situation of change of described FEM (finite element) model is simulated with finite element software.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement apparatus of the present invention, the thermal shock of one unit carries
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 apparatus of the present invention, described unit transient heat conduction model
It is when the inner-walls of duct of described FEM (finite element) model loads a unit thermal shock load, the pipeline outer wall of described FEM (finite element) model
The time dependent situation of unit transient temperature.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement apparatus of the present invention, the unit that described MBM is set up
Transient heat conduction model is that pipeline outer wall unit transient temperature is in time when inner-walls of duct loads a unit thermal shock load
The situation of change.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement apparatus of the present invention, described MBM utilizes unit wink
State heat conduction model derivation numerical computation method is realized by following steps:
Assuming that time step is 1 second, when i-th second, inwall unit transient temperature is 0,10,10,10 ..., inwall reality temperature
Degree is T (i in real), wherein i=0,1,2,3 ... and, when the 0th second, outer wall actual temperature is T (real outer 0)；
When calculating i-th second, inwall actual temperature increment T (i in real)-T (i-1 in real), wherein i=0,1,2,3 ...；
When calculating i-th second, (T is (real interior for inwall actual temperature increment and the multiple proportion Ni=of inwall unit transient temperature
I)-T (i-1 in real))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature when obtaining i-th second according to inwall unit transient temperature and unit transient heat conduction model
T (single outer i), wherein i=1,2,3 ...；
Calculate outer wall actual temperature T (the real outer ij)=T (list that the inwall actual temperature increment of i-th second produces when 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
Solve inwall actual temperature T (real in i) of i-th second, wherein i=0,1,2,3 ..., in obtaining calculating according to outer wall actual temperature
The computing formula of wall actual temperature.
As a kind of improvement of nuclear power station pipeline inner wall temperature measurement apparatus of the present invention, described 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 measuring pipeline outer wall temperature, and founding mathematical models is calculated pipeline
Inner wall temperature, the present invention is without perforate on tested pipeline, on the premise of not destroying one loop of nuclear power station pipeline configuration, accurately
The temperature distribution information of inner-walls of duct is known on ground, more effectively achieves radioactivity and contains, improves the safety that nuclear power station runs
Property；Meanwhile, the present invention directly measures pipeline outer wall temperature and the temperature of liquid in non-measured pipeline, it is to avoid the meter of the coefficient of heat transfer
Calculate, significantly improve the calculating accuracy in inner-walls of duct temperature field.
Accompanying drawing explanation
Below in conjunction with the accompanying drawings and detailed description of the invention, to nuclear power station pipeline inner wall temperature measuring 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 measuring method of the present invention.
Fig. 2 is the structural representation of the FEM (finite element) model of nuclear power station pipeline inner wall temperature measuring method of the present invention.
Fig. 3 is the signal of the FEM (finite element) model loading thermal shock load of nuclear power station pipeline inner wall temperature measuring method of the present invention
Figure.
Fig. 4 is the schematic diagram of the unit transient heat conduction model of nuclear power station pipeline inner wall temperature measuring method of the present invention.
Detailed description of the invention
In order to make the purpose of the present invention, technical scheme and Advantageous Effects become apparent from understanding, below in conjunction with accompanying drawing and
Detailed description of the invention, is further elaborated to the present invention.It should be appreciated that being embodied as described in this specification
Mode is only used to explain the present invention, is not intended to limit the present invention.
Referring to Fig. 1, nuclear power station pipeline inner wall temperature measuring method of the present invention includes:
Step 101, sets up unit transient heat conduction model；
Step 103, utilizes unit transient heat conduction model inference numerical computation method；
Step 105, measures pipeline outer wall temperature；
Step 107, pipeline outer wall temperature measurement obtained, as known quantity, uses described numerical computation method to calculate
To inner-walls of duct temperature.
It it is below an embodiment of nuclear power station pipeline inner wall temperature measuring method of the present invention.
Refer to Fig. 2 and Fig. 3, in finite element software, set up such as according to pipeline section actual size (external diameter and wall thickness)
FEM (finite element) model shown in Fig. 2, the inner-walls of duct in FEM (finite element) model loads a unit thermal shock load as shown in Figure 3,
The pipeline outer wall unit transient temperature situation of change of simulation FEM (finite element) model.Wherein, a unit thermal shock load is when 1s
In rise to 10 DEG C from 0 DEG C, and constant at 10 DEG C.
Referring to Fig. 4, the unit transient heat conduction model set up by finite element software is the pipeline in FEM (finite element) model
When inwall loads a unit thermal shock load, the pipeline outer wall time dependent feelings of unit transient temperature of FEM (finite element) model
Condition.In Fig. 4, the longitudinal axis represents temperature, horizontal axis representing time, and zone circle curve represents outer wall unit transient temperature, and dendrite represents
Unit thermal shock load, i.e. inwall unit transient temperature.
Below with unit transient heat conduction model inference numerical computation method.
Assuming that time step is 1 second, when i-th second, inwall unit transient temperature is 0,10,10,10 ..., inwall reality temperature
Degree is T (i in real), wherein i=0,1,2,3 ... and, when the 0th second, outer wall actual temperature is T (real outer 0)；
When calculating i-th second, inwall actual temperature increment T (i in real)-T (i-1 in real), wherein i=0,1,2,3 ...；
When calculating i-th second, (T is (real interior for inwall actual temperature increment and the multiple proportion Ni=of inwall unit transient temperature
I)-T (i-1 in real))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature when obtaining i-th second according to inwall unit transient temperature and unit transient heat conduction model
T (single outer i), wherein i=1,2,3 ...；
Due in the case of different thermal shock load, the ratio etc. of outer wall actual temperature increment and outer wall unit transient temperature
In the ratio of inwall actual temperature increment with inwall unit transient temperature, the inwall actual temperature increment of i-th second therefore can be calculated
Outer wall actual temperature T (real outer ij)=T (single outer j) * Ni, the wherein i=1 produced when the jth second, 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
Solve inwall actual temperature T (real in i) of i-th second, wherein i=0,1,2,3 ..., in obtaining calculating according to outer wall actual temperature
The computing formula of wall actual temperature.
In order to be illustrated more clearly that the process utilizing unit transient heat conduction model inference numerical computation method, below by way of
Table 1 provides the derivation of first 3 seconds.Table 1 is deduced to the 12nd step from the 1st step, the result of the 11st step is substituted into the 12nd step, just obtains
Formula to the numerical computation method calculating inner-walls of duct actual temperature according to pipeline outer wall actual temperature.
Table 1, numerical computation method derivation step example
Nuclear power station pipeline inner wall temperature measurement apparatus of the present invention includes:
MBM, is used for setting up unit transient heat conduction model, and utilizes unit transient heat conduction model inference numerical value
Computational methods；
Temperature-measuring module, is used for measuring pipeline outer wall temperature；
Computing module, is derived by as known quantity, utilization MBM for pipeline outer wall temperature measurement obtained
Numerical computation method calculate pipeline inner wall temperature.
Wherein, MBM is used for realizing step 101 and step in nuclear power station pipeline inner wall temperature measuring method of the present invention
The method of 103, its embodiment is identical with step 101 and step 103, and here is omitted.
Temperature-measuring module includes thermocouple, and the installation of TC is in pipeline outer wall face.
Computing module is for realizing the method for step 107 in nuclear power station pipeline inner wall temperature measuring method of the present invention, in fact
Executing mode identical with step 107, here is omitted.
In conjunction with above detailed description of the present invention it can be seen that relative to prior art, in nuclear power station pipeline of the present invention
The Advantageous Effects of wall temperature measuring method and device includes but not limited to:
(1) without perforate on tested pipeline, on the premise of not destroying one loop of nuclear power station pipeline configuration, obtain exactly
Know the temperature distribution information of inner-walls of duct, more effectively achieve radioactivity and contain, improve the safety that nuclear power station runs；
(2) pipeline outer wall temperature is directly measured and the temperature of liquid in non-measured pipeline, it is to avoid the calculating of the coefficient of heat transfer,
And using computational accuracy higher FInite Element founding mathematical models, the calculating significantly improving inner-walls of duct temperature field is accurate
Property；
(3) obtain inner-walls of duct temperature information in real time, and then calculate monitoring point pipeline tired coefficient of utilization in real time, right
Nuclear power station optimization runs directive significance；
(4) tube wall temperature by obtaining provides convenient for the frequency identifying design transient, it is simple to observation technique
The transient changing that the system reform or upgrading cause；
(5) upstream master, penetrate pipeline need to use valve to dam because running time, according to the change of pipe interior temperature, make
The aid qualitatively judged for upstream line valve (gate valve, stop valve etc.) leakage.
According to above-mentioned principle, the present invention can also carry out suitable change and amendment to above-mentioned embodiment.Therefore, this
Bright it is not limited to detailed description of the invention disclosed and described above, some modifications and changes of the present invention be should also be as falling into this
In the scope of the claims of invention.Although additionally, employ some specific terms in this specification, but these terms
Merely for convenience of description, the present invention is not constituted any restriction.
Claims (19)
1. a nuclear power station pipeline inner wall temperature measuring method, it is characterised in that said method comprising the steps of:
Set up unit transient heat conduction model；
Utilize unit transient heat conduction model inference numerical computation method；
Measure pipeline outer wall temperature；
Pipeline outer wall temperature measurement obtained, as known quantity, uses described numerical computation method to be calculated inner-walls of duct temperature
Degree.
Nuclear power station pipeline inner wall temperature measuring method the most according to claim 1, it is characterised in that described set up unit wink
State heat conduction model, is to set up unit transient heat conduction model by finite element software.
Nuclear power station pipeline inner wall temperature measuring method the most according to claim 2, it is characterised in that described in pass through finite element
Unit transient heat conduction model set up by software, sets up FEM (finite element) model including according to pipeline section actual size.
Nuclear power station pipeline inner wall temperature measuring method the most according to claim 3, it is characterised in that described pipeline section is real
Border size includes outside dimension and the wall thickness dimension of pipeline.
Nuclear power station pipeline inner wall temperature measuring method the most according to claim 3, it is characterised in that described in pass through finite element
Unit transient heat conduction model set up by software, and the inner-walls of duct being additionally included in described FEM (finite element) model loads a unit thermal shock
Load, utilizes finite element software to simulate the pipeline outer wall unit transient temperature situation of change of described FEM (finite element) model.
Nuclear power station pipeline inner wall temperature measuring method the most according to claim 5, it is characterised in that one 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.
Nuclear power station pipeline inner wall temperature measuring method the most according to claim 5, it is characterised in that described unit thermal transient
Conduction model is when the inner-walls of duct of described FEM (finite element) model loads a unit thermal shock load, described FEM (finite element) model
The time dependent situation of pipeline outer wall unit transient temperature.
Nuclear power station pipeline inner wall temperature measuring method the most according to claim 1, it is characterised in that described unit thermal transient
Conduction model is that pipeline outer wall unit transient temperature is time dependent when inner-walls of duct loads a unit thermal shock load
Situation.
Nuclear power station pipeline inner wall temperature measuring method the most according to claim 8, it is characterised in that described utilize unit wink
State heat conduction model derivation numerical computation method is realized by following steps:
Assuming that time step is 1 second, when i-th second, inwall unit transient temperature is 0,10,10,10 ..., inwall actual temperature is
T (i in real), wherein i=0,1,2,3 ..., when the 0th second, outer wall actual temperature is T (real outer 0)；
When calculating i-th second, inwall actual temperature increment T (i in real)-T (i-1 in real), wherein i=0,1,2,3 ...；
When calculating i-th second, inwall actual temperature increment and the multiple proportion Ni=of inwall unit transient temperature (T (real interior i)-T
(i-1 in real))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature T when obtaining i-th second according to inwall unit transient temperature and unit transient heat conduction model is (single
Outer i), wherein i=1,2,3 ...；
Calculate outer wall actual temperature T (real outer ij)=T that the inwall actual temperature increment of i-th second produces when the jth second (outside Dan
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 ...；
Solve inwall actual temperature T (real in i) of i-th second, wherein i=0,1,2,3 ..., in obtaining calculating according to outer wall actual temperature
The computing formula of wall actual temperature.
10. a nuclear power station pipeline inner wall temperature measurement apparatus, it is characterised in that described device includes:
MBM, is used for setting up unit transient heat conduction model, and utilizes unit transient heat conduction model inference numerical computations
Method；
Temperature-measuring module, is used for measuring pipeline outer wall temperature；
Computing module, the pipeline outer wall temperature being used for obtaining measurement, as known quantity, uses the number that MBM is derived by
Value calculating method calculates pipeline inner wall temperature.
11. nuclear power station pipeline inner wall temperature measurement apparatus according to claim 10, it is characterised in that described MBM
Set up unit transient heat conduction model, be to set up unit transient heat conduction model by finite element software.
12. nuclear power station pipeline inner wall temperature measurement apparatus according to claim 11, it is characterised in that described by limited
Meta software sets up unit transient heat conduction model, sets up FEM (finite element) model including according to pipeline section actual size.
13. nuclear power station pipeline inner wall temperature measurement apparatus according to claim 12, it is characterised in that described pipeline section
Actual size includes outside dimension and the wall thickness dimension of pipeline.
14. nuclear power station pipeline inner wall temperature measurement apparatus according to claim 12, it is characterised in that described by limited
Meta software sets up unit transient heat conduction model, and the inner-walls of duct being additionally included in described FEM (finite element) model loads a unit heat punching
Hit load, utilize finite element software to simulate the pipeline outer wall unit transient temperature situation of change of described FEM (finite element) model.
15. nuclear power station pipeline inner wall temperature measurement apparatus according to claim 14, it is characterised in that one unit
Thermal shock load be to rise to 10 DEG C from 0 DEG C within the 1s time, and constant at 10 DEG C.
16. nuclear power station pipeline inner wall temperature measurement apparatus according to claim 14, it is characterised in that described unit transient state
Heat conduction model is when the inner-walls of duct of described FEM (finite element) model loads a unit thermal shock load, described FEM (finite element) model
The pipeline outer wall time dependent situation of unit transient temperature.
17. nuclear power station pipeline inner wall temperature measurement apparatus according to claim 10, it is characterised in that described MBM
The unit transient heat conduction model set up is when inner-walls of duct loads a unit thermal shock load, pipeline outer wall unit transient state
The time dependent situation of temperature.
18. nuclear power station pipeline inner wall temperature measurement apparatus according to claim 17, it is characterised in that described MBM
Unit transient heat conduction model inference numerical computation method is utilized to be realized by following steps:
Assuming that time step is 1 second, when i-th second, inwall unit transient temperature is 0,10,10,10 ..., inwall actual temperature is
T (i in real), wherein i=0,1,2,3 ..., when the 0th second, outer wall actual temperature is T (real outer 0)；
When calculating i-th second, inwall actual temperature increment T (i in real)-T (i-1 in real), wherein i=0,1,2,3 ...；
When calculating i-th second, inwall actual temperature increment and the multiple proportion Ni=of inwall unit transient temperature (T (real interior i)-T
(i-1 in real))/10, wherein i=1,2,3 ...；
Outer wall unit transient temperature T when obtaining i-th second according to inwall unit transient temperature and unit transient heat conduction model is (single
Outer i), wherein i=1,2,3 ...；
Calculate outer wall actual temperature T (real outer ij)=T that the inwall actual temperature increment of i-th second produces when the jth second (outside Dan
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 ...；
Solve inwall actual temperature T (real in i) of i-th second, wherein i=0,1,2,3 ..., in obtaining calculating according to outer wall actual temperature
The computing formula of wall actual temperature.
19. nuclear power station pipeline inner wall temperature measurement apparatus according to claim 10, it is characterised in that described temperature survey
Module includes thermocouple, and the installation of TC is in pipeline outer wall face.
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| CN109800458A (en) * | 2018-12-17 | 2019-05-24 | 中国原子能科学研究院 | A method of assessment reactor safety operation |
| CN111141400A (en) * | 2019-12-04 | 2020-05-12 | 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 |
| 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 |
| WO2022147978A1 (en) * | 2021-01-08 | 2022-07-14 | 深圳中广核工程设计有限公司 | Straight pipeline inner wall surface temperature measurement and transient identification method and computer terminal |
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| CN109800458A (en) * | 2018-12-17 | 2019-05-24 | 中国原子能科学研究院 | A method of assessment reactor safety operation |
| CN109800458B (en) * | 2018-12-17 | 2020-10-09 | 中国原子能科学研究院 | Method for evaluating safe operation of reactor |
| CN111141400A (en) * | 2019-12-04 | 2020-05-12 | 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 |
| 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 |
| WO2022147978A1 (en) * | 2021-01-08 | 2022-07-14 | 深圳中广核工程设计有限公司 | Straight pipeline inner wall surface temperature measurement and transient identification method and computer terminal |
| EP4071655A4 (en) * | 2021-01-08 | 2023-07-19 | China Nuclear Power Design Company Ltd. (Shenzhen) | Straight pipeline inner wall surface temperature measurement and transient identification 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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