CN109817357B - Method and device for evaluating radiation damage of reactor pressure vessel based on magnetization work - Google Patents

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

Method and device for evaluating radiation damage of reactor pressure vessel based on magnetization work

technical field

The invention relates to the technical field of reactor pressure vessels in nuclear power plants, in particular to a method and a device for evaluating radiation damage of reactor pressure vessels based on magnetization work.

Background technique

The reactor pressure vessel is one of the most critical large-scale equipment in the nuclear island of a nuclear power plant. Strong irradiation, high temperature, high pressure environment. Among them, neutron irradiation damage (specifically manifested in the increase of strength and decrease of toughness in the process of irradiation embrittlement of reactor pressure vessel steel) is one of its main failure modes.

In order to ensure the safety of the operation of the reactor pressure vessel, the traditional radiation supervision method is mainly used to monitor and evaluate the radiation damage degree of the reactor pressure vessel. The specific implementation steps are as follows: (1) Before the first fuel loading operation of the nuclear power plant, install 4 to 6 irradiation supervision tubes inside the reactor pressure vessel, and each irradiation supervision tube is equipped with a certain number of tensile, impact and other mechanical properties test tubes. (2) According to the irradiation supervision program, take advantage of the opportunity of refueling and maintenance of the nuclear power plant, regularly extract the irradiation supervision tube from the reactor pressure vessel, install the radiation protection requirements, and then transport it to the designated hot cell mechanism for long-distance transportation after dissection and take out. Tensile, impact and other tests are carried out to test the mechanical properties, and the tensile properties and ductile-brittle transition curves of the irradiation supervised specimens are obtained, and then the mechanical properties of the reactor pressure vessel steel after irradiation are analyzed and obtained, such as the energy of the upper platform and the non-ductile transition temperature parameters. (3) According to the above mechanical performance data, the radiation damage degree of the reactor pressure vessel steel is analyzed, and then the structural integrity evaluation of the reactor pressure vessel is carried out, and the operating parameters of the reactor system are adjusted in a timely manner.

However, the above-mentioned existing methods have the following disadvantages:

(1) Due to the limitation of the internal space of the reactor pressure vessel, the number of irradiation supervision tubes to be loaded is very limited, and the loading must be completed at one time before the first charging operation (the existing technology cannot realize the supplementary installation of irradiation supervision after a period of operation). tube), which cannot fully meet the radiation supervision requirements for the reactor pressure vessel when the nuclear power plant life is extended in the future;

(2) After the irradiation supervision tube is extracted from the reactor pressure vessel, it must be transported from the nuclear power plant to a designated hot cell institution (currently only a few domestic units have this hot cell), because the irradiation supervision tube has Very high and strong radioactivity, so the security requirements during transportation are very high, the transportation cost is very high, and the cycle is long;

(3) Since the mechanical property test of the irradiation supervision sample is a destructive test, a large amount of radioactive waste will be generated after the test is completed, and the subsequent three wastes will be treated with a large amount and a high cost;

(4) The above method can only monitor the radiation damage degree of the reactor pressure vessel core area as a whole, and does not have the ability to monitor the radiation damage degree of other parts of the reactor pressure vessel, especially specific locations.

(5) The above method does not have the ability to monitor the radiation damage of the reactor pressure vessel steel, and can only obtain the radiation damage degree of the reactor pressure vessel steel at some specific time points (depending on the extraction time of the radiation supervisory tube).

Therefore, it is necessary to provide a method for evaluating the radiation damage of a reactor pressure vessel based on the magnetization work, which overcomes the shortcomings of the above-mentioned existing methods.

SUMMARY OF THE INVENTION

In view of the above problems in the prior art, the present invention provides a method and device for evaluating neutron irradiation damage of a reactor pressure vessel based on a magnetization work parameter, which can continuously, online and simultaneously monitor multiple positions of the reactor pressure vessel and some specific The neutron irradiation damage at the position meets the technical requirements of the reactor pressure vessel of the nuclear power plant.

The technical solution of the present invention for solving the above technical problems is to provide a method for evaluating the radiation damage of a reactor pressure vessel based on magnetization work, comprising the steps of:

S1. Test to obtain the initial magnetization work W ₀ of the reactor pressure vessel steel;

S2. Real-time test to obtain the magnetization work W after the radiation damage of the reactor pressure vessel steel during the normal operation of the nuclear power plant;

S3. Calculate the mechanical property data R of the reactor pressure vessel steel according to the initial magnetization work W ₀ and magnetization work W;

S4. Evaluate the radiation 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. Calculate the magnetization power change rate δ(W) during the irradiation damage of the reactor pressure vessel steel according to the initial magnetization work W ₀ and the magnetization work W;

S32, calculating the change rate δ(R) of the mechanical property data during the irradiation embrittlement process of the reactor pressure vessel steel according to the magnetization power change rate δ(W);

S33. Obtain the initial mechanical property data R ₀ of the unirradiated state of the reactor pressure vessel steel, and calculate the irradiated damage to the reactor pressure vessel steel according to the initial mechanical property data R ₀ and the mechanical property data change rate δ(R) Mechanical Properties Data R.

In the above method of the present invention, the mechanical property data R includes the real-time tensile strength R _m , the real-time yield strength R _P0.2 , the upper platform energy USE and the non-ductile transition temperature RT _NDT during the irradiation damage process of the reactor pressure vessel steel .

In the above-mentioned method of the present invention, after the reactor pressure vessel is installed in place, the initial magnetization work W ₀ is obtained by testing before the nuclear power plant is initially charged for operation.

In the above method of the present invention, the change rate δ(R) of the mechanical property data is calculated according to the formula (2):

δ(R)=λ·δ(W) (2);

In formula (2), δ(W) is the rate of change of the magnetizing power; λ is the proportional coefficient, and the influencing factors of the proportional coefficient λ include the microstructure characteristics of the initial state of the reactor pressure vessel steel and the reactor neutron radiation during the operation of the nuclear power plant. Light field energy spectrum.

In the above method of the present invention, the magnetization power change rate δ(W) is calculated according to formula (1):

δ(W)=(WW ₀ )/W ₀ (1);

In formula (1), W is the magnetization work; W ₀ is the initial magnetization work.

In the above method of the present invention, the mechanical property data R is calculated according to formula (3):

δ(R)=(RR ₀ )/R ₀ (3);

In formula (3), δ(R) is the change rate of the mechanical property data; R ₀ is the initial mechanical property data.

In another aspect, an apparatus for evaluating radiation damage of a reactor pressure vessel based on magnetization work is provided, comprising:

The acquisition module, installed on the reactor pressure vessel, is used for testing to obtain the initial magnetization work W ₀ of the reactor pressure vessel steel, and also for real-time testing to obtain the magnetization work W of the reactor pressure vessel steel after irradiation damage during the normal operation of the nuclear power plant;

A monitoring module, connected to the acquisition module, used to calculate the mechanical property data R of the reactor pressure vessel steel according to the initial magnetization work W ₀ and the magnetization work W, and to irradiate the reactor pressure vessel steel based on the mechanical property data R Assess the extent of damage.

In the above device of the present invention, the monitoring module includes:

a storage unit for storing the initial mechanical property data R ₀ of the unirradiated state of the reactor pressure vessel steel;

a first calculation unit, configured to calculate the magnetization power change rate δ(W) during the irradiation damage process of the reactor pressure vessel steel according to the initial magnetization power W ₀ and the magnetization work W;

The second calculation unit is configured to calculate the change rate δ(R) of mechanical property data during the irradiation embrittlement process of the reactor pressure vessel steel according to the magnetization power change rate δ(W);

The third calculation unit is configured to calculate the mechanical property data R during the irradiation damage of the reactor pressure vessel steel according to the initial mechanical property data R ₀ and the mechanical property data change rate δ(R).

In the above-mentioned device of the present invention, the second calculation unit calculates the change rate δ(R) of the mechanical property data according to the formula (2):

δ(R)=λ·δ(W) (2);

In formula (2), δ(W) is the rate of change of the magnetizing power; λ is the proportional coefficient, and the influencing factors of the proportional coefficient λ include the microstructure characteristics of the initial state of the reactor pressure vessel steel and the reactor neutron radiation during the operation of the nuclear power plant. Light field energy spectrum.

To sum up, the present invention provides a method and device for evaluating the radiation damage of a reactor pressure vessel based on the magnetization work. By testing the magnetization work of the reactor pressure vessel steel in real time during the operation of the nuclear power plant, it is possible to calculate and obtain the real time value of the reactor pressure vessel steel. The mechanical properties change data, and then realize the real-time, online, continuous and intelligent monitoring of the radiation damage degree of the reactor pressure vessel; since the magnetization work test of the reactor pressure vessel steel is non-destructive, it can be used during the whole life of the nuclear power plant, including the future life extension operation. Data can be obtained from unlimited tests; the test equipment and operation have no special radiation safety protection requirements, and there is basically no requirement for the external space of the equipment, low cost, good safety, especially no radioactive waste, basically no three waste treatment needs; It can monitor the radiation damage degree of multiple positions of the reactor pressure vessel at the same time, and is especially suitable for monitoring the initiation and propagation of micro-cracks or suspected micro-cracks found during in-service inspections.

Description of drawings

The present invention will be further described below in conjunction with the accompanying drawings and embodiments, in which:

1 is a schematic flowchart of steps of a method provided in Embodiment 1 of the present invention;

FIG. 2 is a schematic structural diagram of an apparatus provided by Embodiment 2 of the present invention.

Detailed ways

In order to enable those skilled in the art to understand the present invention more clearly, the present invention will be described in further detail below with reference to the accompanying drawings and specific embodiments.

Aiming at the problems existing in monitoring and evaluating the radiation damage degree of the current reactor pressure vessel mainly using the traditional irradiation supervision method, the present invention aims to provide a method and device for evaluating the radiation damage of the reactor pressure vessel based on the magnetization work, The core idea is: the reactor pressure vessel steels in the nuclear power plants currently in service and under construction are all manganese-nickel-molybdenum low-alloy steel materials. The experimental study shows that the change rate of the magnetization power parameters of this material during the neutron irradiation process is presented. It has a good regularity and has a good functional relationship with the radiation damage degree of the material. Therefore, by monitoring the change of the magnetization work of the material during the operation and service of the reactor pressure vessel, the changes in the mechanical properties of the reactor pressure vessel steel can be analyzed and obtained, and then the radiation damage degree of the reactor pressure vessel can be evaluated.

Example 1

As shown in FIG. 1 , the method for assessing radiation damage of a reactor pressure vessel based on magnetization work provided in Embodiment 1 of the present invention includes the steps of:

S1. Test to obtain the initial magnetization work W ₀ of the steel of the reactor pressure vessel;

Specifically, in step S1 , after the reactor pressure vessel is installed in place, the initial magnetization work W ₀ is obtained by testing before the nuclear power plant is charged and operated for the first time. It should be noted that the magnetization work can be obtained by testing a magnetic performance testing instrument installed on the outer surface of the reactor pressure vessel, and the specific operation process can refer to the existing implementation, which will not be repeated in this embodiment.

S2. Real-time test to obtain the magnetization work W of the reactor pressure vessel steel after irradiation damage during the normal operation of the nuclear power plant;

It should be noted that the test position of the magnetization work W corresponds to the test position of the initial magnetization work W ₀ one-to-one; when a specific position of the reactor pressure vessel is selected for testing to obtain the initial magnetization work W ₀ and the magnetization work W The irradiation damage degree of some specific positions of the pressure vessel steel is monitored; when multiple positions of the reactor pressure vessel steel are selected for testing to obtain the initial magnetization work W ₀ and magnetization work W, that is, the irradiation of multiple positions of the reactor pressure vessel steel The damage degree is monitored at the same time, which overcomes the fact that the traditional radiation supervision method can only monitor the radiation damage degree of the reactor pressure vessel core area as a whole, and does not have the ability to monitor other parts of the reactor pressure vessel, especially the radiation damage at specific locations. a matter of degree.

S3. Calculate the mechanical property data R of the reactor pressure vessel steel according to the initial magnetization work W ₀ and the magnetization work W; specifically, step S3 includes steps S31, S32 and S33:

S31. Calculate the magnetization power change rate δ(W) during the irradiation damage of the reactor pressure vessel steel based on the initial magnetization work W ₀ and the magnetization work W;

In this embodiment, the magnetization power change rate δ(W) is calculated according to formula (1):

δ(W)=(WW ₀ )/W ₀ (1);

In formula (1), W is the magnetization work; W ₀ is the initial magnetization work.

S32, calculating the change rate δ(R) of mechanical property data during the irradiation embrittlement process of the reactor pressure vessel steel based on the magnetization power change rate δ(W);

In this embodiment, the change rate δ(R) of the mechanical property data is calculated according to formula (2):

δ(R)=λ·δ(W) (2);

In formula (2), δ(W) is the rate of change of the magnetization power; λ is the proportionality coefficient.

S33. Obtain the initial mechanical property data R ₀ of the unirradiated state of the reactor pressure vessel steel, and calculate the irradiated damage to the reactor pressure vessel steel according to the initial mechanical property data R ₀ and the mechanical property data change rate δ(R) Mechanical Properties Data R.

In this embodiment, the mechanical property data R is calculated according to formula (3):

δ(R)=(RR ₀ )/R ₀ (3);

In formula (3), δ(R) is the change rate of the mechanical property data; R ₀ is the initial mechanical property data.

It should be noted that the mechanical performance data R includes the real-time tensile strength R _m , real-time yield strength R _P0.2 , upper platform energy USE and non-ductile transition temperature RT _NDT during the irradiation damage process of the reactor pressure vessel steel. performance parameters.

The initial mechanical property data R ₀ is the mechanical property data of the initial unirradiated state of the reactor pressure vessel steel, which can be obtained by consulting the relevant data in the completion report provided by the equipment manufacturer.

The influencing factors of the proportional coefficient λ include the microstructure characteristics of the initial state of the reactor pressure vessel steel (such as grain size, dislocation type, quantity, distribution characteristics of the second phase, etc.) and the energy spectrum of the reactor neutron irradiation field during the operation of the nuclear power plant. . For specific nuclear power plants and reactor pressure vessels, it can be determined or corrected through the traditional mechanical performance test of the irradiation supervision sample, so that the final mechanical performance data is more representative and the evaluation results are more accurate.

Specifically, when the proportional coefficient of the reactor pressure vessel of a specific nuclear power plant needs to be calculated, because the microstructure characteristics of the initial state of the steel of the reactor pressure vessel and the energy spectrum of the reactor neutron irradiation field during the operation of the nuclear power plant can be measured, it is only necessary to calculate the The grain size, dislocation type, quantity, distribution characteristics of the second phase in the initial state of the reactor pressure vessel, and the energy spectrum of the neutron irradiation field of the reactor during the operation of the nuclear power plant are used as the analysis input parameters, and the simulation calculation method of the phase field of the material irradiation damage is used. , the value of the corresponding coefficient can be calculated.

And through the traditional radiation supervision fission detector test data to determine or correct, for the nuclear power plants currently in service. As described in the background art of this application, the radiation supervisory tubes of the existing nuclear power plant will be taken out within a certain period of time, so the data of the taken out irradiation supervisory tubes can be used to obtain the values of the coefficients in the formula by data fitting.

It should be noted that, for a specific reactor pressure vessel material, the proportionality coefficient λ remains basically unchanged during the whole life. Therefore, the mechanical property data R can be obtained by unlimited tests during the whole life of the nuclear power plant, including the future life extension operation.

The following uses the real-time tensile strength R _m of the reactor pressure vessel steel in the process of radiation damage as the mechanical property data, and takes a nuclear power plant that has been in operation for 10 years as an example to illustrate the above calculation process:

First, after the reactor pressure vessel is installed in place, the initial magnetization work W ₀ is measured to be 246KJ/ ³ before the first charging operation of the nuclear power plant, and then the magnetization work W of the same position is measured to be 342KJ/ ³ during the normal operation of the nuclear power plant. Finally, the magnetization power change rate δ(W) is calculated to be 39.02% by substituting the formula (1).

Secondly, according to the influencing factors of the proportional coefficient, it can be determined that the value range of the proportional coefficient λ _m corresponding to the real-time tensile strength R _m is 0.55 to 0.89, and the optimal proportional coefficient λ _m is 0.66 with reference to the radiation supervision tube data, and then substituted into the formula (2) The change rate δ(R) of the mechanical property data is calculated to be 25.55%.

Finally, according to the completion report provided by the equipment manufacturer, the initial tensile strength _Rm0 is 591Mpa, and then the real-time tensile strength _Rm is calculated as 742Mpa by substituting into formula (3).

At the same time, in this embodiment, the tensile strength of the same reactor pressure vessel at the same time and at the same position is obtained as 739Mpa through 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 of the tensile strength 739Mpa measured by the traditional method, and its deviation is completely within the acceptable range. within the range.

It should be noted that the quantitative relationship between the magnetization work parameter and the mechanical property data obtained by the present invention through formulas (1), (2) and (3) is obtained by the inventor through repeated verification and creative work, which is the invention of the present invention. One of the important invention points, no same or similar solutions have been disclosed in the prior art.

Further, the method for evaluating the radiation damage of the reactor pressure vessel further comprises the steps of:

S4. Evaluate the radiation 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, and the radiation damage degree of the reactor pressure vessel can be evaluated, and the evaluation content includes safety evaluation of structural integrity and life prediction. For the specific evaluation method, reference may be made to the traditional irradiation supervision and analysis method, which will not be repeated in this embodiment.

Embodiment 2

As shown in FIG. 2 , this embodiment provides an apparatus for evaluating radiation damage of a reactor pressure vessel based on magnetization work, including an acquisition module 10 and a monitoring module 20 . The acquisition module 10 is installed on the reactor pressure vessel and is used to obtain the reactor pressure by testing. The initial magnetization work W ₀ of the container steel is also used for real-time testing to obtain the magnetization work W after the radiation damage of the reactor pressure container steel during the normal operation of the nuclear power plant;

Specifically, the acquisition module 10 can use an existing magnetic performance testing instrument, and after the reactor pressure vessel is installed in place, and before the nuclear power plant is charged for the first time, the initial magnetization work W ₀ is obtained by testing.

The monitoring module 20 is connected to the acquisition module 10, and is configured to calculate the mechanical property data R of the reactor pressure vessel steel according to the initial magnetization work W ₀ and the magnetization work W, and based on the mechanical property data R, the irradiation damage to the reactor pressure vessel steel degree is assessed.

Specifically, the monitoring module 20 includes a first calculation unit 21, a second calculation unit 22, a third calculation unit 23, a storage unit 24 and a judgment unit 25. The storage unit 24 is used to store the initial mechanics of the unirradiated state of the reactor pressure vessel steel performance data R ₀ ;

The first calculation unit 21 is connected to the acquisition module 10 and the storage unit 24, and is configured to calculate the magnetization power change rate δ(W) during the irradiation damage of the reactor pressure vessel steel according to the initial magnetization power W ₀ and the magnetization work W, and calculate The magnetization power change rate δ(W) is stored in the storage unit 24;

The second calculation unit 22 is connected to the storage unit 24, and is configured to calculate the change rate δ(R) of the mechanical property data during the irradiation embrittlement process of the reactor pressure vessel steel according to the magnetization power change rate δ(W), and calculate the mechanical property data change rate δ(R). The performance data change rate δ(R) is stored in the storage unit 24;

The third calculation unit 23 is connected to the storage unit 24, and is configured to calculate the mechanical property data R during the irradiation damage process of the reactor pressure vessel steel according to the initial mechanical property data R ₀ and the mechanical property data change rate δ(R), The mechanical property data R is stored in the storage unit 24 .

The judging unit 25 is connected to the storage unit 24, and is configured to use the mechanical property data R as an analysis input parameter to evaluate the radiation damage degree of the reactor pressure vessel.

Specifically, the first calculation unit 21 calculates the magnetization power change rate δ(W) according to formula (1):

δ(W)=(WW ₀ )/W ₀ (1);

In formula (1), W is the magnetization work; W ₀ is the initial magnetization work.

The second calculation unit 22 calculates the mechanical property data change rate δ(R) according to formula (2):

δ(R)=λ·δ(W) (2);

In formula (2), δ(W) is the rate of change of the magnetizing power; λ is the proportional coefficient, and the influencing factors of the proportional coefficient λ include the microstructure characteristics of the initial state of the reactor pressure vessel steel and the reactor neutron radiation during the operation of the nuclear power plant. Light field energy spectrum.

The third calculation unit 23 calculates the mechanical property data R according to formula (3):

δ(R)=(RR ₀ )/R ₀ (3);

In formula (3), δ(R) is the change rate of the mechanical property data; R ₀ is the initial mechanical property data.

Those skilled in the art can clearly understand that, for the convenience and brevity of description, the foregoing evaluation apparatus may refer to the implementation steps corresponding to the evaluation method provided in Embodiment 1, which will not be repeated in this embodiment.

In summary, the present invention provides a method and device for evaluating radiation damage of a reactor pressure vessel based on magnetization work, which has 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 plant, the change data of the mechanical properties of the reactor pressure vessel steel can be obtained by real-time calculation, and the real-time, online, continuous and intelligent monitoring of the radiation damage degree of the reactor pressure vessel can be realized;

(2) Since the magnetization work test of the reactor pressure vessel steel is non-destructive, the data can be obtained by unlimited tests during the whole life of the nuclear power plant, including the future life extension operation;

(3) There are no special radiation safety protection requirements for the test equipment and operation, and there is basically no requirement for the external space of the equipment, the cost is low, the safety is good, especially no radioactive waste is generated, and there is basically no need for the three wastes treatment;

(4) The radiation damage degree of multiple positions of the reactor pressure vessel can be monitored at the same time, and it is especially suitable for monitoring the initiation and propagation of micro-cracks or suspected micro-cracks found during in-service inspections.

It should be understood that, for those skilled in the art, improvements or changes can be made according to the above description, and all these improvements and changes should fall within the protection scope of the appended claims of the present invention.

Claims (8)

1. A method for evaluating radiation damage of a reactor pressure vessel based on magnetization work, characterized in that, comprising the steps of: S1. Test to obtain the initial magnetization work W ₀ of the reactor pressure vessel steel; S2. Real-time test to obtain the magnetization work W after the radiation damage of the reactor pressure vessel steel during the normal operation of the nuclear power plant; S3. Calculate the mechanical property data R of the reactor pressure vessel steel according to the initial magnetization work W ₀ and magnetization work W ; S4, evaluating the radiation damage degree of the reactor pressure vessel steel based on the mechanical property data R ; Step S3 includes: S31, according to the initial magnetization work W ₀ and the magnetization work W , calculate the magnetization power change rate δ( W ) during the irradiation damage of the reactor pressure vessel steel; S32, calculating the change rate δ( R ) of mechanical property data during the irradiation embrittlement process of the reactor pressure vessel steel according to the magnetization power change rate δ( W ); S33. Obtain the initial mechanical property data R ₀ of the unirradiated state of the reactor pressure vessel steel, and calculate the irradiated damage of the reactor pressure vessel steel according to the initial mechanical property data R ₀ and the mechanical property data change rate δ( R ). Mechanical properties data R. 2 . The method according to claim 1 , wherein the mechanical performance data R comprises the real-time tensile strength R _m , real-time yield strength R _P0.2 , and upper platform energy during the irradiation damage process of the reactor pressure vessel steel. 3 . USE and non-ductile transition temperature RT _NDT . 3 . The method according to claim 1 , wherein, in step S1 , after the reactor pressure vessel is installed in place, the initial magnetization work W ₀ is obtained by testing before the nuclear power plant is charged for the first time for operation. 4 . 4. The method according to claim 1, wherein in step S32, the mechanical property data change rate δ( R ) is calculated according to formula (2): δ( R ) = λ·δ( W ) (2); In formula (2), δ( W ) is the rate of change of the magnetization power; λ is the proportional coefficient, and the influencing factors of the proportional coefficient λ include the microstructure characteristics of the initial state of the reactor pressure vessel steel and the reactor neutron radiation during the operation of the nuclear power plant. Light field energy spectrum. 5 . The method according to claim 1 , wherein in step S31 , the magnetization power change rate δ ( W ) is calculated according to formula (1): 6 . δ( W ) = ( WW ₀ )/ W ₀ (1); In formula (1), W is the magnetization work; W ₀ is the initial magnetization work. 6. The method according to claim 1, wherein in step S33, the mechanical property data R is calculated according to formula (3): δ( R ) = ( RR ₀ )/ R ₀ (3); In formula (3), δ( R ) is the change rate of the mechanical property data; R ₀ is the initial mechanical property data. 7. A device for evaluating radiation damage of a reactor pressure vessel based on magnetization work, characterized in that it comprises: The acquisition module, installed on the reactor pressure vessel, is used for testing to obtain the initial magnetization work W ₀ of the reactor pressure vessel steel, and also for real-time testing to obtain the magnetization work W of the reactor pressure vessel steel after irradiation damage during the normal operation of the nuclear power plant; a monitoring module, connected to the acquisition module, for calculating the mechanical property data R of the reactor pressure vessel steel according to the initial magnetization work W ₀ and the magnetization work W , and irradiating the reactor pressure vessel steel based on the mechanical property data R assessment of the extent of damage; The monitoring module includes: a storage unit for storing the initial mechanical property data R ₀ of the unirradiated state of the reactor pressure vessel steel; a first calculation unit, configured to calculate the magnetization power change rate δ( W ) during the irradiation damage process of the reactor pressure vessel steel according to the initial magnetization power W ₀ and the magnetization work W ; a second calculation unit, configured to calculate the change rate δ( R ) of mechanical property data during the irradiation embrittlement process of the reactor pressure vessel steel according to the magnetization power change rate δ( W ); The third calculation unit is configured to calculate the mechanical property data R during the irradiation damage process of the reactor pressure vessel steel according to the initial mechanical property data R ₀ and the mechanical property data change rate δ( R ). 8 . The device according to claim 7 , wherein the second calculation unit calculates the mechanical property data change rate δ( R ) according to formula (2): δ( R ) = λ·δ( W ) (2); In formula (2), δ( W ) is the rate of change of the magnetization power; λ is the proportional coefficient, and the influencing factors of the proportional coefficient λ include the microstructure characteristics of the initial state of the reactor pressure vessel steel and the reactor neutron radiation during the operation of the nuclear power plant. Light field energy spectrum.

Images