CN117954139A - Nuclear power station containment prestress measuring device and calculation evaluation method - Google Patents
Nuclear power station containment prestress measuring device and calculation evaluation method Download PDFInfo
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- CN117954139A CN117954139A CN202410059096.2A CN202410059096A CN117954139A CN 117954139 A CN117954139 A CN 117954139A CN 202410059096 A CN202410059096 A CN 202410059096A CN 117954139 A CN117954139 A CN 117954139A
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- 238000011156 evaluation Methods 0.000 title claims abstract description 11
- 238000004364 calculation method Methods 0.000 title claims abstract description 9
- 239000004567 concrete Substances 0.000 claims abstract description 60
- 238000005259 measurement Methods 0.000 claims abstract description 16
- 238000000034 method Methods 0.000 claims abstract description 16
- 238000002955 isolation Methods 0.000 claims abstract description 13
- 229910000831 Steel Inorganic materials 0.000 claims description 11
- 239000010959 steel Substances 0.000 claims description 11
- 230000008859 change Effects 0.000 claims description 9
- 230000009471 action Effects 0.000 claims description 2
- 238000012544 monitoring process Methods 0.000 abstract description 2
- 230000006835 compression Effects 0.000 description 2
- 238000007906 compression Methods 0.000 description 2
- 238000010276 construction Methods 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000009413 insulation Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 125000006850 spacer group Chemical group 0.000 description 2
- 230000001360 synchronised effect Effects 0.000 description 2
- 238000004873 anchoring Methods 0.000 description 1
- 238000005452 bending Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000011513 prestressed concrete Substances 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000000750 progressive effect Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 238000010008 shearing Methods 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a device and a method for measuring the prestress of a containment vessel of a nuclear power station, which relate to the technical field of the measurement of the prestress of the containment vessel of the nuclear power station and are arranged in the concrete of the containment vessel of the nuclear power station; divide into nuclear power station containment concrete interior through setting up isolating device: an unconstrained region inside the isolation device, and a constrained region outside the isolation device; the non-constraint area is internally provided with a non-constraint area horizontal strain sensor, and the constraint area is internally provided with a constraint area horizontal strain sensor and a constraint area vertical strain sensor. The method can accurately obtain temperature deformation, shrinkage and creep, and further can obtain the prestress of the containment concrete of the nuclear power station through certain calculation, provide basic parameters for the performance evaluation of the containment, realize the real-time monitoring and real-time evaluation of the containment concrete prestress, be a rapid and accurate scientific method, solve the core-most problem of the containment evaluation of the nuclear power station, and provide basic guarantee for the life extension of the containment of the nuclear power station.
Description
Technical Field
The invention relates to the technical field of nuclear power station containment prestress measurement, in particular to a nuclear power station containment prestress measuring device and a calculation evaluation method.
Background
The containment of the nuclear power station is a concrete prestress structure with protection and support functions, so that the leakage of radioactive elements can not occur under the condition that the reactor is leaked in a large scale. In order to prevent cracking of concrete, compressive stress, which is a compressive stress applied simultaneously in the horizontal and vertical directions of the containment, is called prestressing. The magnitude of the prestress is one of the most important performance indexes of the containment.
The magnitude of the prestress of the nuclear power plant is determined by design and is applied to the structure of the containment vessel by a special construction team by using a combination of prestressed steel bundles and anchoring systems. Therefore, the bending resistance, the compression resistance and the shearing resistance of the containment vessel can be enhanced, and the safety of the nuclear power station is ensured.
The prestressing force is applied in the horizontal and vertical directions simultaneously, and compressive stresses f 1 and f 2 are generated in the horizontal and vertical directions simultaneously. The containment is in a pressed state, so that cracks can not be generated in concrete, and the steel bars in the concrete can not be corroded by external air to be rusted and expanded. Because creep phenomenon of materials can occur to both the concrete and the steel strand exerting the pre-compression, the tension of the steel strand can be gradually reduced, and the pressure in the concrete can be synchronously reduced. Over time, the compressive stress of the containment concrete may decrease to a certain extent, and when the compressive stress is less than a certain value, the containment concrete will crack under a certain internal pressure, and the integrity of the containment concrete is damaged, thereby reducing the sealing performance and durability of the containment. In order to grasp the magnitude of the pre-stress in the containment concrete, it is necessary to perform a test analysis of the pre-stress of the containment concrete.
However, the prestress of the containment concrete is related to the temperature deformation, shrinkage and creep of the concrete, so that the magnitude of the prestress of the containment concrete cannot be accurately determined at present. And the exact value of this prestress is critical for the operation and maintenance of the nuclear power plant.
To solve this problem, how to provide a device and a corresponding algorithm, which can accurately measure temperature deformation, shrinkage and creep, and further obtain the prestress of the containment concrete, is a problem that needs to be solved by those skilled in the art.
Disclosure of Invention
In view of the above, the present invention provides a device for measuring the prestress of a containment vessel of a nuclear power plant and a method for evaluating the prestress of the containment vessel of the nuclear power plant.
In order to achieve the above purpose, the present invention adopts the following technical scheme:
The prestress measuring device for the containment of the nuclear power plant is arranged in the containment concrete of the nuclear power plant; dividing the containment concrete of the nuclear power station into the containment concrete by arranging an isolating device: an unconstrained region inside the isolation device, and a constrained region outside the isolation device; the non-constraint area is internally provided with a non-constraint area horizontal strain sensor, and the constraint area is internally provided with a constraint area horizontal strain sensor and a constraint area vertical strain sensor.
According to the technical scheme, in the device for measuring the prestress of the containment vessel of the nuclear power station, the constraint area is formed in the concrete of the containment vessel of the nuclear power station, and the horizontal strain sensor and the vertical strain sensor are arranged in the constraint area, so that the measured values of the two sensors are related to the applied prestress; the unconstrained region is an isolated region inside the containment concrete of the nuclear power station, the applied prestress cannot cause the strain change of the concrete in the unconstrained region, and meanwhile, the measured value of the internal sensor is irrelevant to the applied prestress; therefore, the invention can accurately obtain temperature deformation, shrinkage and creep, and further can accurately obtain the prestress value of the containment concrete, thereby providing basic parameters for the performance evaluation of the containment and providing basic guarantee for the life extension of the containment of the nuclear power station.
Preferably, in the above-mentioned device for measuring prestress of containment vessel of a nuclear power plant, a data collector is disposed outside the concrete of the containment vessel of the nuclear power plant, and the data collector is connected with the horizontal strain sensor of the non-constraint zone, the horizontal strain sensor of the constraint zone and the vertical strain sensor of the constraint zone through wires respectively. The data acquisition device is connected with the strain sensors in the constraint area and the non-constraint area through wires, and can obtain the strain value in the concrete in real time.
Preferably, in the above-mentioned nuclear power station containment vessel prestress measurement device, the isolation device includes a steel shell, and a foamed plastic inner layer disposed inside the steel shell; and one side of the steel shell in the horizontal direction is opened. This design allows the concrete inside the insulation to deform freely without external restraint; however, the temperature, humidity changes inside the device and the increase in concrete strength are completely synchronized with the surrounding concrete.
Preferably, in the above-mentioned containment pre-stress measuring device for a nuclear power plant, the measurement value of the strain sensor in the horizontal direction is related to a strain component of the internal strain of the containment concrete in the horizontal direction, and is unrelated to a strain component in the vertical direction; the measurement value of the strain sensor in the vertical direction is related to the strain component of the strain in the vertical direction in the containment concrete of the nuclear power station, and is unrelated to the strain component in the horizontal direction.
The invention also provides a prestress measurement calculation evaluation method of the nuclear power station containment prestress measurement device, which is characterized by comprising the following steps of:
S1, before prestress tensioning, measuring the strain of an unconstrained region through a horizontal strain sensor of the unconstrained region Measuring strain/>, of a confinement region by a confinement region horizontal strain sensor and a confinement region vertical strain sensorStrains S ch 0 and S cv 0 in the horizontal direction and the vertical direction of the confinement region;
S2, after prestress tensioning, measuring the strain of the unconstrained region through a horizontal strain sensor of the unconstrained region Measuring strain/>, of a confinement region by a confinement region horizontal strain sensor and a confinement region vertical strain sensorHorizontal and vertical components of (a): strains in the horizontal and vertical directions are S ch i and S cv i, respectively, where i=1, 2, & gt, n;
S3, calculating the relative values of the horizontal strain and the vertical strain of the prestressed concrete of the containment of the nuclear power station through the measured values in the steps S1 and S2, and respectively marking as e h and e v:
According to the technical scheme, the shrinkage and creep of the containment concrete of the nuclear power station can be measured by using a simpler method, the prestress of the containment concrete of the nuclear power station can be obtained through certain calculation, the real-time monitoring and real-time evaluation of the prestress of the containment concrete are realized, the method is a rapid and accurate scientific method, and the problem of the most core of the containment evaluation of the nuclear power station is solved.
Preferably, in the method for calculating and evaluating the prestress of the containment vessel prestress measuring device of a nuclear power plant, in step S1, the absolute value of the strain of the unconstrained region before tensioning is related to the temperature and the strain change caused by the shrinkage of the concrete; the absolute value of the strain in the restraint zone is related to the temperature and the strain change caused by the shrinkage of the concrete.
Preferably, in the method for calculating and evaluating the prestress of the containment vessel prestress measuring device of a nuclear power plant, in step S2, the absolute value of the strain of the unconstrained region after stretching is related to the temperature and the strain change caused by the shrinkage of the concrete; the absolute value of the strain in the restraint zone is related to the temperature, the shrinkage of the concrete itself, the creep action of the concrete and the strain change caused by the application of prestressing force.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings that are required to be used in the embodiments or the description of the prior art will be briefly described below, and it is obvious that the drawings in the following description are only embodiments of the present invention, and that other drawings can be obtained according to the provided drawings without inventive effort for a person skilled in the art.
Fig. 1 is a schematic structural diagram of a device for measuring prestress of a containment vessel of a nuclear power station.
Wherein:
1-nuclear power station containment concrete; 2-isolating means; 3-unconstrained region; 4-confinement region; 5-unconstrained region horizontal strain sensor; 6-a confinement region horizontal strain sensor; 7-a confinement zone vertical strain sensor; 8-a data collector; 9-conducting wires.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
Referring to fig. 1, the embodiment of the invention discloses a prestress measuring device of a containment vessel of a nuclear power station, which is arranged in containment vessel concrete 1 of the nuclear power station; the containment concrete 1 of the nuclear power station is divided into the following parts by arranging an isolating device 2: an unconstrained region 3 inside the isolation device 2, and a constrained region 4 outside the isolation device 2; the unconstrained region 3 is internally provided with an unconstrained region horizontal strain sensor 5, and the constrained region 4 is internally provided with a constrained region horizontal strain sensor 6 and a constrained region vertical strain sensor 7.
The outside of the containment concrete 1 of the nuclear power station is provided with a data collector 8, and the data collector 8 is respectively connected with the horizontal strain sensor 5 of the non-restraint area, the horizontal strain sensor 6 of the restraint area and the vertical strain sensor 7 of the restraint area through wires 9.
Example 1:
taking a containment as an example, a flexible isolation device 2 is buried in the containment concrete 1 of the nuclear power station in advance in the process of pouring the containment concrete. In this embodiment, the spacer 2 is of a double-layer construction, consisting of steel material on the outside and filled with foamed plastic on the inside, which allows the concrete inside the spacer 2 to deform freely without being constrained by the outside. However, the temperature, humidity changes inside the insulation 2 and the increase of the concrete strength are completely synchronized with the surrounding concrete. The strain value measured by the sensor inside the isolation device 2 is thus the strain value in the unconstrained state under all external conditions and with the same strain sensor in other constrained regions within the working area.
Measuring readings of the horizontal strain sensor 5 in the unconstrained region simultaneously after the containment is concreted and before stretching is startedAnd readings S ch 0 and S cv 0 on the confinement region horizontal strain sensor 6 and the confinement region vertical strain sensor 7.
After the prestress tensioning is finished, the reading of the horizontal strain sensor 5 of the unconstrained region is measured at any timeAnd readings S ch 1 and S cv 1 on the confinement region horizontal strain sensor 6 and the confinement region vertical strain sensor 7.
Calculating the prestress of containment concrete, wherein the horizontal strain and the vertical strain are respectively as follows:
in the present specification, each embodiment is described in a progressive manner, and each embodiment is mainly described in a different point from other embodiments, and identical and similar parts between the embodiments are all enough to refer to each other. For the device disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and the relevant points refer to the description of the method section.
The previous description of the disclosed embodiments is provided to enable any person skilled in the art to make or use the present invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the invention. Thus, the present invention is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.
Claims (7)
1. The device for measuring the prestress of the containment of the nuclear power plant is arranged in the containment concrete (1) of the nuclear power plant; the method is characterized in that: the isolation device (2) is arranged to divide the containment concrete (1) of the nuclear power station into: -an unconstrained zone (3) inside the isolation device (2), and-a constrained zone (4) outside the isolation device (2); an unconstrained region horizontal strain sensor (5) is arranged in the unconstrained region (3), and a constrained region horizontal strain sensor (6) and a constrained region vertical strain sensor (7) are arranged in the constrained region (4).
2. The nuclear power station containment pre-stress measurement device according to claim 1, wherein a data collector (8) is arranged on the outer side of the nuclear power station containment concrete (1), and the data collector (8) is respectively connected with the non-restraint area horizontal strain sensor (5), the restraint area horizontal strain sensor (6) and the restraint area vertical strain sensor (7) through leads (9).
3. A nuclear power plant containment pre-stress measurement device according to claim 1, characterized in that the isolation device (2) comprises a steel shell and an inner layer of foamed plastic provided inside the steel shell.
4. A nuclear power plant containment pre-stress measurement device according to claim 3, wherein the steel shell is open on one side in the horizontal direction.
5. A method of prestress measurement calculation evaluation using the containment prestress measurement device of a nuclear power plant of any one of claims 1-3, comprising the steps of:
S1, before prestress tensioning, measuring the strain S f 0 of an unconstrained region (3) through an unconstrained region horizontal strain sensor (5), and measuring the strain S C 0 of a constrained region (4) through a constrained region horizontal strain sensor (6) and a constrained region vertical strain sensor (7), wherein the strains S ch 0 and S cv 0 of the constrained region (4) in the horizontal direction and the vertical direction are measured;
S2, after prestress tensioning, measuring the strain S f i of the unconstrained region (3) through an unconstrained region horizontal strain sensor (5), and measuring the horizontal and vertical components of the strain S C i of the constrained region (4) through a constrained region horizontal strain sensor (6) and a constrained region vertical strain sensor (7): strains in the horizontal and vertical directions are S ch i and S cv i, respectively, where i=1, 2, & gt, n;
s3, calculating the relative values of the horizontal strain and the vertical strain of the prestress of the containment concrete (1) of the nuclear power station through the measured values in the steps S1 and S2, wherein the relative values are respectively recorded as e h and e v:
6. the method for evaluating the prestress measurement calculation of a containment prestress measurement device of a nuclear power plant according to claim 5, wherein in step S1, the absolute value of the strain of an unconstrained region before tensioning is related to the temperature and the strain change caused by the shrinkage of the concrete itself; the absolute value of the strain in the restraint zone is related to the temperature and the strain change caused by the shrinkage of the concrete.
7. The method for evaluating the prestress measurement calculation of a containment prestress measurement device of a nuclear power plant according to claim 5, wherein in step S2, the absolute value of the strain of the tensioned unconstrained region is related to the temperature and the strain change caused by the shrinkage of the concrete itself; the absolute value of the strain in the restraint zone is related to the temperature, the shrinkage of the concrete itself, the creep action of the concrete and the strain change caused by the application of prestressing force.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202410059096.2A CN117954139A (en) | 2024-01-16 | 2024-01-16 | Nuclear power station containment prestress measuring device and calculation evaluation method |
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| CN202410059096.2A CN117954139A (en) | 2024-01-16 | 2024-01-16 | Nuclear power station containment prestress measuring device and calculation evaluation method |
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| CN202410059096.2A Pending CN117954139A (en) | 2024-01-16 | 2024-01-16 | Nuclear power station containment prestress measuring device and calculation evaluation method |
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