CN109817357B - Method and device for evaluating radiation damage of reactor pressure vessel based on magnetization work - Google Patents
Method and device for evaluating radiation damage of reactor pressure vessel based on magnetization work Download PDFInfo
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Abstract
The invention provides a method for evaluating radiation damage of a reactor pressure vessel based on magnetization work, which comprises the following steps: s1 testing to obtain the initial magnetization work W of the reactor pressure vessel steel0(ii) a S2, obtaining the magnetization work W after the irradiation damage of the reactor pressure vessel steel during the normal operation of the nuclear power station through real-time testing; s3, according to the initial magnetization work W0Calculating the mechanical property data R of the reactor pressure vessel steel according to the magnetization work W; and S4, evaluating the irradiation damage degree of the reactor pressure vessel steel based on the mechanical property data R. According to the method and the device for evaluating the irradiation damage of the reactor pressure vessel, provided by the invention, the mechanical property change data of the reactor pressure vessel steel is obtained through the calculation of the magnetization work parameter, so that the real-time, online, continuous and intelligent monitoring of the irradiation damage degree of the reactor pressure vessel is realized, and the method and the device have good popularization and application values.
Description
Technical Field
The invention relates to the technical field of reactor pressure vessels of nuclear power stations, in particular to a method and a device for evaluating radiation damage of a reactor pressure vessel based on magnetization work.
Background
The reactor pressure vessel is one of the most critical large-scale devices in a nuclear island of a nuclear power station, is a steel pressure-bearing vessel used for containing and supporting a reactor core nuclear fuel assembly, a control assembly, an in-reactor component and a reactor coolant, and is used in a strong irradiation, high-temperature and high-pressure environment for a long time. Among them, neutron irradiation damage (specifically, increased strength and reduced toughness in the process of irradiation embrittlement of reactor pressure vessel steel) is one of the main failure modes.
In order to ensure the safety of the operation of the reactor pressure vessel, the conventional irradiation monitoring method is mainly adopted to monitor and evaluate the irradiation damage degree. The specific implementation steps are as follows: (1) before the first charging operation of a nuclear power station, 4 to 6 irradiation monitoring pipes are arranged in a reactor pressure vessel, and a certain amount of mechanical property samples such as tension, impact and the like are arranged in each irradiation monitoring pipe; (2) according to an irradiation supervision outline, regularly extracting an irradiation supervision pipe from a reactor pressure vessel by using the opportunity of refueling and overhauling of a nuclear power station, installing a hot chamber mechanism which requires irradiation protection for packaging and is transported to a fixed point in a long distance, dissecting, taking out, stretching, impacting and other tests to carry out mechanical property tests, obtaining the tensile property and ductile-brittle transition curve of an irradiation supervision sample, and further analyzing and obtaining mechanical property data of the irradiated reactor pressure vessel steel, such as the energy of a platform thereon, the non-ductile transition temperature parameter and the like; (3) and analyzing the irradiation damage degree of the reactor pressure vessel steel according to the mechanical property data, and further performing structural integrity evaluation of the reactor pressure vessel, timely adjusting the operating parameters of a reactor system and the like.
However, the above-described conventional method has the following disadvantages:
(1) due to the limitation of the internal space of the reactor pressure vessel, the number of the loaded irradiation monitoring tubes is very limited, and the irradiation monitoring tubes must be loaded at one time before the first loading operation (the irradiation monitoring tubes cannot be additionally installed after the operation for a period of time in the prior art), so that the irradiation monitoring requirements of the nuclear power station on the reactor pressure vessel during the service life extension in the future cannot be completely met;
(2) after the irradiation monitoring pipe is extracted from the reactor pressure vessel, the irradiation monitoring pipe must be transported to a fixed-point hot room mechanism (only a very individual unit in China has the hot room at present) from a long-distance province-crossing of the nuclear power station in a long distance, and because the irradiation monitoring pipe has very high strong radioactivity, the safety requirement in the transportation process is very high, the transportation cost is very high, and the period is long;
(3) because the mechanical property test of the irradiation supervision sample belongs to destructive test, a large amount of radioactive waste is generated after the test is finished, the subsequent three wastes treatment capacity is large, and the cost is high;
(4) the method can only monitor the irradiation damage degree of the reactor core area of the reactor pressure vessel as a whole, and does not monitor other parts of the reactor pressure vessel, especially the irradiation damage degree of a specific position.
(5) The method does not have the capability of monitoring the irradiation damage of the reactor pressure vessel steel, and only can obtain the irradiation damage degree of the reactor pressure vessel steel at certain specific time points (depending on the extraction time of the irradiation monitoring pipe).
Accordingly, there is a need for a method for assessing reactor pressure vessel radiation damage based on work of magnetization that overcomes the shortcomings of the prior art methods described above.
Disclosure of Invention
Aiming at the problems in the prior art, the invention provides a method and a device for evaluating the neutron irradiation damage of a reactor pressure vessel based on the magnetization work parameter, which can continuously monitor the neutron irradiation damage of a plurality of positions and certain specific positions of the reactor pressure vessel on line and simultaneously and meet the technical requirements of the reactor pressure vessel of a nuclear power station.
The technical scheme of the invention for solving the technical problems is as follows: the method for evaluating the irradiation damage of the reactor pressure vessel based on the magnetizing work comprises the following steps:
s1 testing to obtain the initial magnetization work W of the reactor pressure vessel steel0；
S2, obtaining the magnetization work W after the irradiation damage of the reactor pressure vessel steel during the normal operation of the nuclear power station through real-time testing;
s3, according to the initial magnetization work W0Calculating the mechanical property data R of the reactor pressure vessel steel according to the magnetization work W;
and S4, evaluating the irradiation damage degree of the reactor pressure vessel steel based on the mechanical property data R.
In the above method of the present invention, step S3 includes:
s31, according to the initial magnetization work W0And calculating the magnetizing work change rate (W) in the irradiation damage process of the reactor pressure vessel steel by using the magnetizing work W;
s32, calculating the change rate (R) of the mechanical property data in the radiation embrittlement process of the reactor pressure vessel steel according to the change rate (W) of the magnetizing power;
s33, acquiring initial mechanical property data R of the reactor pressure vessel steel in the non-irradiated state0And according to said initial mechanical property data R0And calculating the mechanical property data R in the irradiation damage process of the reactor pressure vessel steel according to the mechanical property data change rate (R).
In the method, the mechanical property data R comprises the real-time tensile strength R in the irradiation damage process of the reactor pressure vessel steelmReal time yield strength RP0.2Upper plateau energy USE and non-ductile transition temperature RTNDT。
In the method, after the reactor pressure vessel is installed in place, the initial magnetizing work W is tested and obtained before the first charging operation of the nuclear power station0。
In the above method of the present invention, the change rate (R) of the mechanical property data is calculated according to formula (2):
(R)＝λ·(W) (2)；
in formula (2), (W) is the magnetization power change rate; and lambda is a proportionality coefficient, and the influence factors of the proportionality coefficient lambda comprise the microstructure characteristics of the initial state of the reactor pressure vessel steel and the energy spectrum of the neutron irradiation field of the reactor during the operation of the nuclear power station.
In the above method of the present invention, the magnetization power change rate (W) is calculated according to formula (1):
(W)＝(W-W0)/W0(1)；
in formula (1), W is the work of magnetization; w0Is the initial work of magnetization.
In the above method of the present invention, the mechanical property data R is calculated according to formula (3):
(R)＝(R-R0)/R0(3)；
in formula (3), (R) is the rate of change of the mechanical property data; r0Is the initial mechanical property data.
In another aspect, an apparatus for evaluating radiation damage of a reactor pressure vessel based on work of magnetization is provided, comprising:
the acquisition module is arranged on the reactor pressure vessel and used for testing and obtaining the initial magnetization work W of the reactor pressure vessel steel0The method is also used for testing and obtaining the magnetization work W after the reactor pressure vessel steel is irradiated and damaged during the normal operation of the nuclear power station in real time;
a monitoring module connected with the acquisition module and used for monitoring the initial magnetization work W0And calculating mechanical property data R of the reactor pressure vessel steel by the magnetization work W, and evaluating the irradiation damage degree of the reactor pressure vessel steel based on the mechanical property data R.
In the above apparatus of the present invention, the monitoring module includes:
a storage unit for storing initial mechanical property data R of the reactor pressure vessel steel in the non-irradiated state0；
A first calculation unit for calculating the initial magnetization work W0Calculating reactor pressure vessel steel irradiation by using magnetization work WRate of change of magnetization power (W) during damage;
the second calculation unit is used for calculating the change rate (R) of the mechanical property data in the radiation embrittlement process of the reactor pressure vessel steel according to the magnetization power change rate (W);
a third calculation unit for calculating the initial mechanical property data R0And calculating the mechanical property data R in the irradiation damage process of the reactor pressure vessel steel according to the mechanical property data change rate (R).
In the above apparatus of the present invention, the second calculation unit calculates the rate of change (R) of the mechanical property data according to formula (2):
(R)＝λ·(W) (2)；
in formula (2), (W) is the magnetization power change rate; and lambda is a proportionality coefficient, and the influence factors of the proportionality coefficient lambda comprise the microstructure characteristics of the initial state of the reactor pressure vessel steel and the energy spectrum of the neutron irradiation field of the reactor during the operation of the nuclear power station.
In summary, the method and the device for evaluating the irradiation damage of the reactor pressure vessel based on the magnetization work provided by the invention can calculate and obtain the mechanical property change data of the reactor pressure vessel steel in real time by testing the magnetization work of the reactor pressure vessel steel in real time during the operation of the nuclear power station, thereby realizing the real-time, on-line, continuous and intelligent monitoring of the irradiation damage degree of the reactor pressure vessel; because the magnetization work test of the reactor pressure vessel steel is nondestructive, the data can be obtained by infinite tests in the whole life period of the nuclear power station, including the life-prolonging operation period in the future; the test equipment and the operation have no special radiation safety protection requirements, basically have no requirements on the external space of the equipment, have low cost and better safety, and particularly do not generate radioactive waste and basically have no three-waste treatment requirements; the irradiation damage degree of a plurality of positions of the reactor pressure vessel can be monitored simultaneously, and the method is particularly suitable for monitoring the initiation and expansion behaviors of the micro-cracks or suspected micro-cracks discovered in-service inspection.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a flow chart illustrating steps of a method according to an embodiment of the present invention;
fig. 2 is a schematic structural diagram of an apparatus according to a second embodiment of the present invention.
Detailed Description
In order that those skilled in the art will more clearly understand the present invention, the present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
Aiming at the problems existing in the monitoring and evaluation of the radiation damage degree of the reactor pressure vessel mainly by adopting the traditional radiation supervision method, the invention aims to provide a method and a device for evaluating the radiation damage of the reactor pressure vessel based on the magnetizing work, and the core idea is as follows: the reactor pressure vessel steel of the existing in-service nuclear power station and the existing nuclear power station under construction is manganese-nickel-molybdenum low-alloy steel material, and experimental research shows that the change rate of the magnetization work parameter of the material in the neutron irradiation process presents better regularity and has better functional relation with the irradiation damage degree of the material. Therefore, the change condition of the mechanical property of the reactor pressure vessel steel can be analyzed and obtained by monitoring the change condition of the material magnetization work in the operating service process of the reactor pressure vessel, and then the irradiation damage degree of the reactor pressure vessel can be evaluated.
Example one
As shown in fig. 1, a method for evaluating radiation damage of a reactor pressure vessel based on magnetization work according to an embodiment of the present invention includes:
s1, testing and obtaining the initial magnetization work W of the reactor pressure vessel steel0；
Specifically, in step S1, after the reactor pressure vessel is installed in place, the initial magnetizing work W is obtained by testing before the first charging operation of the nuclear power plant0. It should be noted that the magnetization work can be obtained through testing by a magnetic property testing instrument installed on the outer surface of the reactor pressure vessel, and the specific operation process thereof may refer to the existing implementation manner, which is not described in detail in this embodiment.
S2, testing and acquiring the magnetization work W after the reactor pressure vessel steel is irradiated and damaged during the normal operation of the nuclear power station in real time;
it should be noted that the test position of the magnetization work W and the initial magnetization work W0The test positions are in one-to-one correspondence; testing to obtain initial magnetization work W when a specific position of a reactor pressure vessel is selected0And the magnetization work W, namely, the irradiation damage degree of certain specific positions of the reactor pressure vessel steel is monitored; testing to obtain initial magnetization work W when selecting multiple positions of reactor pressure vessel steel0And the magnetization work W, namely, the irradiation damage degrees of a plurality of positions of the reactor pressure vessel steel are monitored simultaneously, so that the problem that the conventional irradiation monitoring method can only monitor the irradiation damage degree of the reactor core area of the reactor pressure vessel on the whole, does not monitor other parts of the reactor pressure vessel, and particularly the irradiation damage degree of a specific position is solved.
S3, according to the initial magnetization work W0Calculating the mechanical property data R of the reactor pressure vessel steel according to the magnetization work W; specifically, step S3 includes steps S31, S32, and S33:
s31, based on the initial magnetization work W0And calculating the magnetizing work change rate (W) in the irradiation damage process of the reactor pressure vessel steel by using the magnetizing work W;
in this embodiment, the magnetization power change rate (W) is calculated according to formula (1):
(W)＝(W-W0)/W0(1)；
in formula (1), W is the work of magnetization; w0Is the initial work of magnetization.
S32, calculating the change rate (R) of the mechanical property data in the radiation embrittlement process of the reactor pressure vessel steel based on the change rate (W) of the magnetizing power;
in this embodiment, the mechanical property data change rate (R) is calculated according to formula (2):
(R)＝λ·(W) (2)；
in formula (2), (W) is the magnetization power change rate; λ is a proportionality coefficient.
S33, acquiring initial mechanical property data R of the reactor pressure vessel steel in the non-irradiated state0And according to said initial mechanical property data R0And calculating the mechanical property data R in the irradiation damage process of the reactor pressure vessel steel according to the mechanical property data change rate (R).
In this embodiment, the mechanical property data R is calculated according to formula (3):
(R)＝(R-R0)/R0(3)；
in formula (3), (R) is the rate of change of the mechanical property data; r0Is the initial mechanical property data.
It should be noted that the mechanical property data R includes real-time tensile strength R during radiation damage of reactor pressure vessel steelmReal time yield strength RP0.2Upper plateau energy USE and non-ductile transition temperature RTNDTAnd mechanical performance parameters are equal.
The initial mechanical property data R0The mechanical property data of the initial unirradiated state of the reactor pressure vessel steel can be obtained by referring relevant data in a completion report provided by a device manufacturer.
The influencing factors of the proportionality coefficient lambda comprise the microstructure characteristics (such as grain size, dislocation type, quantity, second phase distribution characteristics and the like) of the initial state of the reactor pressure vessel steel and the neutron irradiation field energy spectrum of the reactor during the operation of the nuclear power station. For specific nuclear power stations and reactor pressure vessels, the mechanical property of the obtained mechanical property data can be determined or corrected through a traditional irradiation supervision sample mechanical property test, so that the finally obtained mechanical property data is more representative, and the judgment result is more accurate.
Specifically, when the proportional coefficient of the reactor pressure vessel of a specific nuclear power station needs to be calculated, because the microstructure characteristics of the initial state of the reactor pressure vessel steel and the energy spectrum of the neutron irradiation field of the reactor during the operation of the nuclear power station are all measurable, the value of the corresponding coefficient can be calculated by using the grain size, the dislocation type, the quantity, the second phase distribution characteristics of the initial state of the reactor pressure vessel, the energy spectrum of the neutron irradiation field of the reactor during the operation of the nuclear power station and the like as analysis input parameters and using a material irradiation damage phase field simulation calculation method.
And the test data of the traditional irradiation supervision fission detector is determined or corrected, so that the nuclear power station in service at present is aimed at. As described in the background of the present application, the irradiation monitoring tube of the existing nuclear power station can be taken out within a certain period of time, so that the coefficient value in the formula can be obtained by using the data of the taken-out irradiation monitoring tube and by using data fitting.
It should be noted that the proportionality coefficient λ remains substantially constant for a particular reactor pressure vessel material over its lifetime. Therefore, the mechanical property data R can be obtained from an infinite number of tests over the life of the nuclear power plant, including during future life-extending operations.
The real-time tensile strength R in the process of irradiation damage of reactor pressure vessel steel is adoptedmAs mechanical property data, the calculation process is described by taking a nuclear power plant which runs for 10 years as an example:
firstly, after the reactor pressure vessel is installed in place, the initial work of magnetization W is measured before the first filling operation of the nuclear power plant0Is 246KJ3And then the magnetizing work W at the same position is measured to be 342KJ3And finally substituting the formula (1) to calculate the change rate (W) of the magnetizing power to be 39.02 percent.
Secondly, the corresponding real-time tensile strength R can be determined according to the influence factors of the proportionality coefficientmCoefficient of proportionality λmThe value range of (1) is 0.55-0.89, and the optimal proportion coefficient lambda is selected by referring to the data of the irradiation monitoring tubemIs 0.66, and then is substituted into the formula (2) to calculate that the change rate (R) of the mechanical property data is 25.55 percent.
Finally, the initial tensile strength R is obtained according to the review in the completion report provided by the equipment manufacturerm0591Mpa, then substituting into formula (3) to obtain real-time tensile strength Rm742 MPa.
Meanwhile, the tensile strength of the same reactor pressure vessel at the same time and the same position is 739Mpa according to the traditional irradiation supervision test data. It can be seen that the real-time tensile strength 742Mpa calculated by the formulas (1), (2) and (3) of the present invention is very close to the measured value 739Mpa of the tensile strength measured by the conventional method, and the deviation thereof is completely within the acceptable range.
It should be noted that, the invention obtains the quantitative relation between the magnetization work parameter and the mechanical property data through the formulas (1), (2) and (3), which is obtained through repeated verification and creative work by the inventor, is one of the important invention points of the invention, and no same or similar scheme is disclosed in the prior art.
Further, the method for evaluating the irradiation damage of the reactor pressure vessel further comprises the following steps:
and S4, evaluating the irradiation damage degree of the reactor pressure vessel steel based on the mechanical property data. In this embodiment, the mechanical property data R is used as an analysis input parameter, so that the irradiation damage degree of the reactor pressure vessel can be evaluated, and the evaluation content includes safety evaluation of structural integrity, life prediction, and the like. For a specific evaluation method, a conventional irradiation supervision analysis method can be referred to, and details are not repeated in this embodiment.
Example two
As shown in fig. 2, the embodiment provides an apparatus for evaluating radiation damage of a reactor pressure vessel based on magnetization work, which includes an acquisition module 10 and a monitoring module 20, wherein the acquisition module 10 is installed on the reactor pressure vessel and is used for testing and obtaining initial magnetization work W of reactor pressure vessel steel0The method is also used for testing and obtaining the magnetization work W after the reactor pressure vessel steel is irradiated and damaged during the normal operation of the nuclear power station in real time;
specifically, the acquisition module 10 may employ an existing magnetic performance testing instrument and test to obtain the initial magnetization work W after the reactor pressure vessel is installed in place and before the first charging operation of the nuclear power plant0。
The monitoring module 20 is connected with the acquisition module 10 and is used for acquiring the initial magnetization work W0And calculating mechanical property data R of the reactor pressure vessel steel by the magnetization work W, and evaluating the irradiation damage degree of the reactor pressure vessel steel based on the mechanical property data R.
Specifically, the monitoring module 20 includes a first calculating unit 21, a second calculating unit 22, a third calculating unit 23, a storage unit 24 and a judging unitA breaking unit 25 and a storage unit 24 for storing initial mechanical property data R of the steel of the reactor pressure vessel in the non-irradiated state0；
The first calculating unit 21 is connected with the acquisition module 10 and the storage unit 24 and is used for calculating the initial magnetization work W0Calculating the change rate (W) of the magnetizing power in the irradiation damage process of the reactor pressure vessel steel by the magnetizing power W, and storing the change rate (W) of the magnetizing power in the storage unit 24;
the second calculating unit 22 is connected with the storage unit 24 and is used for calculating the change rate (R) of the mechanical property data in the radiation embrittlement process of the reactor pressure vessel steel according to the change rate (W) of the magnetizing power and storing the change rate (R) of the mechanical property data in the storage unit 24;
the third calculating unit 23 is connected to the storage unit 24 for calculating the initial mechanical property data R0And calculating the mechanical property data R in the irradiation damage process of the reactor pressure vessel steel according to the mechanical property data change rate (R), and storing the mechanical property data R in the storage unit 24.
The judging unit 25 is connected with the storage unit 24, and is used for evaluating the irradiation damage degree of the reactor pressure vessel by using the mechanical property data R as an analysis input parameter.
Specifically, the first calculation unit 21 calculates the magnetization power change rate (W) according to formula (1):
(W)＝(W-W0)/W0(1)；
in formula (1), W is the work of magnetization; w0Is the initial work of magnetization.
The second calculation unit 22 calculates the mechanical property data change rate (R) according to formula (2):
(R)＝λ·(W) (2)；
in formula (2), (W) is the magnetization power change rate; and lambda is a proportionality coefficient, and the influence factors of the proportionality coefficient lambda comprise the microstructure characteristics of the initial state of the reactor pressure vessel steel and the energy spectrum of the neutron irradiation field of the reactor during the operation of the nuclear power station.
The third calculation unit 23 calculates the mechanical property data R according to formula (3):
(R)＝(R-R0)/R0(3)；
in formula (3), (R) is the rate of change of the mechanical property data; r0Is the initial mechanical property data.
It can be clearly understood by those skilled in the art that, for convenience and brevity of description, the above-mentioned evaluation apparatus may refer to the implementation steps corresponding to the evaluation method provided in the first embodiment, and details of this embodiment are not repeated herein.
In summary, the invention provides a method and a device for evaluating radiation damage of a reactor pressure vessel based on magnetization work, and the method and the device have the following beneficial effects:
(1) by testing the magnetization work of the reactor pressure vessel steel in real time during the operation of the nuclear power station, the mechanical property change data of the reactor pressure vessel steel can be calculated and obtained in real time, so that the real-time, online, continuous and intelligent monitoring of the irradiation damage degree of the reactor pressure vessel is realized;
(2) because the magnetization work test of the reactor pressure vessel steel is nondestructive, the data can be obtained by infinite tests in the whole life period of the nuclear power station, including the life-prolonging operation period in the future;
(3) the test equipment and the operation have no special radiation safety protection requirements, basically have no requirements on the external space of the equipment, have low cost and better safety, and particularly do not generate radioactive waste and basically have no three-waste treatment requirements;
(4) the irradiation damage degree of a plurality of positions of the reactor pressure vessel can be monitored simultaneously, and the method is particularly suitable for monitoring the initiation and expansion behaviors of the micro-cracks or suspected micro-cracks discovered in-service inspection.
It will be understood that modifications and variations can be made by persons skilled in the art in light of the above teachings and all such modifications and variations are intended to be included within the scope of the invention as defined in the appended claims.
Claims (8)
1. A method for evaluating radiation damage of a reactor pressure vessel based on magnetization work is characterized by comprising the following steps:
s1, testing and obtaining the inverseInitial work of magnetization of steel for reactor pressure vesselW 0 ；
S2, testing and obtaining the magnetization work of the reactor pressure vessel steel after radiation damage in the normal operation period of the nuclear power station in real timeW；
S3, according to the initial magnetization workW 0 And work of magnetizationWCalculating the mechanical property data of reactor pressure vessel steelR；
S4, based on the mechanical property dataREvaluating the irradiation damage degree of the reactor pressure vessel steel;
step S3 includes:
s31, according to the initial magnetization workW 0 And work of magnetizationWCalculating the magnetizing work change rate in the process of irradiation damage of reactor pressure vessel steel (W)；
S32, according to the change rate of magnetization power (W) Calculating the change rate of the mechanical property data in the irradiation embrittlement process of the reactor pressure vessel steel (R)；
S33, acquiring initial mechanical property data of the reactor pressure vessel steel in the non-irradiated stateR 0 And according to said initial mechanical property dataR 0 And rate of change of mechanical property data: (R) Calculating mechanical property data in the process of irradiation damage of reactor pressure vessel steelR。
2. The method of claim 1, wherein the mechanical property dataRIncluding real-time tensile strength during irradiation damage of reactor pressure vessel steelR m Real time yield strengthR P0.2 Upper platform energyUSEAnd no ductile transition temperatureRT NDT 。
3. The method of claim 1, wherein in step S1, after the reactor pressure vessel is installed in place, the initial magnetizing work is tested and obtained before the first charging operation of the nuclear power plantW 0 。
4. The method according to claim 1, wherein in step S32, the mechanical property data change rate is calculated according to formula (2) (i.e., (i: (2))R)：
(R)= λ·(W) （2）；
In the formula (2) <W) Is the rate of change of the magnetizing power; and lambda is a proportionality coefficient, and the influence factors of the proportionality coefficient lambda comprise the microstructure characteristics of the initial state of the reactor pressure vessel steel and the energy spectrum of the neutron irradiation field of the reactor during the operation of the nuclear power station.
5. The method according to claim 1, wherein in step S31, the magnetizing power change rate (S) is calculated according to formula (1)W)：
(W)= （W-W 0）/W 0（1）；
In the formula (1), the first and second groups,Wis the work of magnetization;W 0 is the initial work of magnetization.
6. The method according to claim 1, characterized in that in step S33, the mechanical property data is calculated according to formula (3)R：
(R)= （R-R 0 ）/R 0 （3）；
In the formula (3) <R) Is the rate of change of the mechanical property data;R 0 is the initial mechanical property data.
7. An apparatus for evaluating radiation damage of a reactor pressure vessel based on work of magnetization, comprising:
the acquisition module is arranged on the reactor pressure vessel and used for testing and obtaining the initial magnetization work of the reactor pressure vessel steelW 0 And the method is also used for testing and obtaining the magnetization work of the reactor pressure vessel steel after radiation damage in the normal operation period of the nuclear power station in real timeW；
A monitoring module connected with the collecting moduleA block for generating an initial magnetization work based on the initial magnetization workW 0 And work of magnetizationWCalculating the mechanical property data of reactor pressure vessel steelRAnd based on said mechanical property dataREvaluating the irradiation damage degree of the reactor pressure vessel steel;
the monitoring module includes:
a storage unit for storing initial mechanical property data of the reactor pressure vessel steel in the non-irradiated stateR 0 ；
A first calculation unit for calculating the initial magnetization workW 0 And work of magnetizationWCalculating the magnetizing work change rate in the process of irradiation damage of reactor pressure vessel steel (W)；
A second calculation unit for calculating a second ratio of magnetization work change (c)W) Calculating the change rate of the mechanical property data in the irradiation embrittlement process of the reactor pressure vessel steel (R)；
A third calculation unit for calculating the initial mechanical property dataR 0 And rate of change of mechanical property data: (R) Calculating mechanical property data in the process of irradiation damage of reactor pressure vessel steelR。
8. The apparatus according to claim 7, wherein the second calculation unit calculates the mechanical property data change rate according to formula (2) ((R)：
(R)= λ·(W) （2）；
In the formula (2) <W) Is the rate of change of the magnetizing power; and lambda is a proportionality coefficient, and the influence factors of the proportionality coefficient lambda comprise the microstructure characteristics of the initial state of the reactor pressure vessel steel and the energy spectrum of the neutron irradiation field of the reactor during the operation of the nuclear power station.
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| GB2493772B (en) * | 2011-08-18 | 2014-01-01 | Gridon Ltd | Fault current limiter |
| CN105810262B (en) * | 2014-12-30 | 2018-03-16 | 中核武汉核电运行技术股份有限公司 | A kind of nuclear plant pressure vessels automatic checkout equipment control system |
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