WO2018205607A1 - Non-destructive assessment method for radiation damage of reactor pressure vessel in nuclear power plant - Google Patents
Non-destructive assessment method for radiation damage of reactor pressure vessel in nuclear power plant Download PDFInfo
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- G21C17/003—Remote inspection of vessels, e.g. pressure vessels
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- the invention belongs to the field of nuclear power, and more particularly to a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel.
- the reactor pressure vessel is one of the most critical large-scale equipment in the nuclear power plant nuclear island. Its main function is to contain and support the core nuclear fuel assembly, control components, internal components and reactor coolant steel pressure vessels. It is long-term service in strong radiation, high temperature and high pressure environment. Among them, neutron irradiation damage (specifically, the strength and toughness of the reactor pressure vessel steel during irradiation embrittlement) is one of the main failure modes.
- each irradiation supervision tube is loaded with a fission dose detector, usually including U 238 and Np 237.
- a fission dose detector usually including U 238 and Np 237.
- Two kinds of fission dose detecting components are then packaged into the titanium box respectively, and the titanium box is then placed in the boron nitride box, and then the boron nitride box is integrally placed in the irradiation supervisory tube.
- the irradiation supervision tube extraction plan formulated by the irradiation supervision program use the opportunity of refueling and maintenance of the nuclear power plant, periodically extract the irradiation supervision tube from the reactor pressure vessel, and then transport it to the fixed point after packaging according to the radiation protection requirements.
- the hot chamber mechanism cuts the fission dose detector and then analyzes the composition changes in the hot chamber to calculate the neutron irradiation damage fluence received by the fission dose detector.
- the neutron irradiation damage fluence of the reactor pressure vessel body is converted, and then the follow-up safety evaluation work is carried out on the operation of the reactor pressure vessel.
- the fission dose detectors (U 238 and Np 237 ) are radioactive sources. Their production, transportation and sales require professional qualifications. The procurement cost is very high, and subsequent transportation and compliance are extremely troublesome.
- the fission dose detector is a one-time product, and has strong radioactivity after use. At the same time, a large amount of radioactive waste is generated in the analysis and testing, and the subsequent three wastes are processed in a large amount and the cost is high;
- the above method can only monitor the neutron irradiation damage fluence of the reactor pressure vessel core area as a whole, and does not have the monitoring of other parts of the reactor pressure vessel, especially the radiation damage fluence at a specific location.
- the object of the present invention is to overcome the deficiencies of the prior art and provide a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel which can be tested in real time, online and continuously.
- the present invention provides a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel, which comprises the following steps:
- a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel comprises the following steps:
- S11, safety threshold value determination determine and record upper threshold no ductile transition temperature of the reactor pressure vessel steel (RT NDT) the upper and lower threshold values of the upper shelf energy (USE) limit;
- the non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel comprises the following steps:
- a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel comprises the following steps:
- the non-destructive evaluation method for the radiation damage of the nuclear power plant reactor pressure vessel has the following beneficial technical effects:
- Test equipment and operation do not require special radiation safety protection requirements, and there is basically no requirement for the external space of the equipment.
- the cost is low and the safety is good.
- no radioactive waste is generated, and there is basically no need for three waste disposal.
- FIG. 1 is a flow chart showing the steps of a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to the present invention.
- Figure 2 is a graph showing the relationship between the magnetic susceptibility of the core portion of the reactor pressure vessel and the neutron irradiation damage fluence.
- Figure 3 is a graph showing the relationship between the residual magnetization of the reactor core section of the reactor and the neutron irradiation damage fluence.
- Figure 4 is a graph showing the relationship between the coercivity of the reactor core section of the reactor and the neutron irradiation damage fluence.
- the present invention provides a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel, which comprises the following steps:
- the magnetic performance parameter being any one of a magnetic susceptibility ⁇ , a residual magnetization M R and a coercive force H C ;
- the magnetic susceptibility ⁇ , residual magnetization M R and coercive force H C of the material magnetic properties parameters are respectively correlated with the neutron irradiation damage fluence. Therefore, the neutron irradiation damage fluence ⁇ can be obtained by monitoring any one of the magnetic susceptibility ⁇ , the residual magnetization M R and the coercive force H C .
- the functional relationship between the magnetic susceptibility ⁇ and the neutron irradiation damage fluence ⁇ is the formula (01).
- the value of a 1 ranges from 0.75 to 1.38; the range of b 1 ranges from 8.78 to 16.75; and the range of c 1 ranges from 0.042 to 0.17.
- the values of a 1 , b 1 and c 1 are affected by the grain size of the initial state of the reactor pressure vessel, the type of dislocation, the quantity, the distribution of the second phase, 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, they can also be determined or corrected by conventional radiation monitoring fission detector test data.
- the magnetic performance parameter can also be selected as the residual magnetization M R , and the residual magnetization M R is a function of the neutron irradiation damage flu ⁇ as the formula (02):
- the value of a 2 ranges from 0.087 to 0.23; and the range of b 2 ranges from 0.12 to 0.31.
- the values of a 2 and b 2 are also affected by the grain size of the initial state of the reactor pressure vessel, the type of dislocation, the quantity, the distribution of the second phase, and the energy spectrum of the reactor neutron irradiation field during the operation of the nuclear power plant. influences. For specific nuclear power plants and reactor pressure vessels, they can also be determined or corrected by conventional radiation monitoring fission detector test data.
- the value of a 3 ranges from 1.79 to 3.21; the range of b 3 ranges from 0.19 to 0.41; the range of c 3 ranges from 0.007 to 0.19, and the range of D ranges from 5.64 to 9.23.
- the values of D, a 3 , b 3 and c 3 are also affected by the grain size of the initial state of the reactor pressure vessel, the type of dislocation, the quantity, the distribution of the second phase, and the reactor neutron irradiation field during the operation of the nuclear power plant.
- the influence of factors such as energy spectrum.
- they can also be determined or corrected by conventional radiation monitoring fission detector test data.
- the neutron irradiation damage fluence ⁇ obtained above is used as an input parameter for analysis, and it is used to carry out structural integrity safety evaluation and life prediction of radiation damage of reactor pressure vessel.
- the specific method is the same as the traditional irradiation supervision analysis method.
- the magnetic performance parameters of the reactor core section of the reactor pressure vessel are monitored in real time at a specific time point.
- the neutron irradiation damage fluence ⁇ can be calculated according to the formula (01).
- the neutron irradiation damage ⁇ can be calculated according to the formula (02).
- the neutron irradiation damage fluence ⁇ can be calculated according to the formula (03).
- the calculated neutron irradiation damage fluence ⁇ is used as the input parameter to analyze the structural integrity of the reactor pressure vessel during the damage process.
- the specific process is the same as the traditional irradiation supervision analysis method.
- the non-destructive evaluation method of the radiation damage of the nuclear power plant reactor pressure vessel can be used instead of the traditional irradiation supervision analysis method, which is not only simple in method, accurate in data, but also real-time online evaluation, and the magnetic susceptibility and residual of the reactor pressure vessel steel.
- the magnetization and coercivity tests are non-destructive, so the data can be tested indefinitely during the full life of the nuclear power plant and during future life extension operations.
- Test equipment and operation do not require special radiation safety protection requirements, and there is basically no requirement for the external space of the equipment.
- the cost is low and the safety is good.
- no radioactive waste is generated, and there is basically no need for three waste disposal.
- a non-destructive evaluation method for irradiated damage of a nuclear power plant reactor pressure vessel using magnetic susceptibility comprising the following steps:
- Non-ductile transition temperature (RT NDT ) initial 241 K
- upper platform energy (USE) initial 335 J
- tensile strength (R m ) initial 483 MPa
- yield strength (R p0.2 ) initial 591 MPa.
- the specific value of the above critical threshold depends on the nuclear safety regulations of the country where the nuclear power plant is monitored, the nuclear safety program used in the operation of the nuclear power plant, and the specific location of the reactor pressure vessel.
- the specific values provided in this patent are derived from the requirements of the US Nuclear Regulatory Commission guidelines RG 1.99 (1988 edition) for the base material of the reactor pressure vessel core section.
- a 1 ranges from 450 to 680, and the value of b 1 ranges from -18 to -35;
- a 2 ranges from 270 to 420, and b 2 ranges from 45 to 75;
- a 3 and a 4 have a value ranging from 1200 to 2000, and b 3 and b 4 have a value ranging from -80 to -135.
- the measured real-time magnetic susceptibility ⁇ 10.15
- the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 can be calculated :
- the above calculated real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 are used as analytical input parameters to perform safety assessment or life prediction of the structural integrity of the reactor pressure vessel during irradiation damage; the specific process is the same as the traditional irradiation supervision analysis method.
- the pre-set warning value of the rate of decrease of the magnetic susceptibility is 1%/year.
- the rate of decrease of the magnetic susceptibility is 0.56%/year, which is lower than the safety warning value of 1%/year, so there is no need to further carry out the reactor pressure vessel. Security assessment argument.
- a conventional reactor pressure vessel having the same degree of radiation damage (generally referred to as having the same neutron irradiation cumulative fluence) is taken.
- the irradiated supervised samples were tested for destructive mechanical properties, and the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 were obtained .
- Table 2 lists the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 obtained in Example 1 and Comparative Example 1.
- the first embodiment adopts the non-ductile transition temperature RT NDT calculated by the non-destructive evaluation method for the radiation damage of the nuclear power plant reactor pressure vessel using the magnetic susceptibility, the real-time upper platform energy USE, and the real-time tensile strength R.
- the values of m and real-time yield strength R p0.2 are very close to those of the comparative example 1; the deviation values are within the acceptable range, and will not affect the safety evaluation of the subsequent reactor pressure vessel radiation damage, and
- the magnetic susceptibility test of reactor pressure vessel steel is non-destructive, so the data can be tested indefinitely during the full life of the nuclear power plant and during future life extension operations. Combined with the rate of decline of magnetic susceptibility, dual monitoring can ensure the safety of the pressure vessel during operation.
- the non-destructive evaluation method for irradiating damage of a nuclear power plant reactor pressure vessel using magnetic susceptibility has at least the following beneficial technical effects:
- Test equipment and operation do not require special radiation safety protection requirements, and there is basically no requirement for the external space of the equipment, and the safety is good, especially no radioactive waste is generated, and there is basically no need for three waste treatment;
- a non-destructive evaluation method for irradiated damage of a nuclear power plant reactor pressure vessel using residual magnetization includes the following steps:
- RT NDT unexpanded transition temperature
- USE upper platform energy
- R tensile strength
- the residual magnetization M R 0.99emu / g; according to equation (21) can be obtained in real time the residual magnetization M R with respect to the initial state of the non-irradiated residual magnetization (M R) of the initial rate of change of residual magnetization ⁇ M R :
- the processing technology of the material the type of defect distribution of the material, the irradiation temperature, and the size characteristics of the neutron irradiation field energy spectrum of the reactor core during the operation of the nuclear power plant, etc.
- RT NDT (1- ⁇ RT NDT ) ⁇ (RT NDT ) Initial (26)
- the conventional reactor pressure having the same degree of radiation damage (generally referred to as having the same neutron irradiation cumulative fluence) is taken.
- the container irradiation supervision sample was tested for destructive mechanical properties, and the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 were obtained .
- Table 3 lists the values of the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, the real-time tensile strength R m , and the real-time yield strength R p0.2 obtained in Example 1 and Comparative Example 1.
- the first embodiment adopts the non-ductile transition temperature RT NDT calculated by the non-destructive evaluation method for the radiation damage of the nuclear power plant reactor pressure vessel using the residual magnetization, the real-time upper platform energy USE, and the real-time tensile strength.
- R m and real-time yield strength R p0.2 are 279.19K, 253.66J, 722.42Mpa and 618.8Mpa, respectively, while the real-time non-ductile transition temperature RT NDT , real-time platform energy USE, real-time tensile strength measured in Comparative Example 1
- the values of R m and real-time yield strength R p0.2 are 274K, 260J, 717MPa, and 623MPa , respectively.
- the data calculated in the first embodiment is very close to the measured value of the comparative example 1, the deviation is about 6, and the deviation values are all within an acceptable range. Therefore, the present invention utilizes the residual magnetization of the nuclear power plant reactor pressure vessel spokes.
- the non-destructive evaluation method of the damage can replace the traditional irradiation supervision and analysis method, and can be monitored in real time, which can be applied to the full life of the nuclear power plant. At the same time, there are no special requirements for the conditions required for monitoring, and the monitoring cost is low and more practical.
- the non-destructive evaluation method for irradiating damage of a nuclear power plant reactor pressure vessel utilizing residual magnetization has at least the following beneficial technical effects:
- a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel using coercivity comprising the following steps:
- RT NDT unexpanded transition temperature
- USE upper platform energy
- R tensile strength
- the rate of change ⁇ (R p0.2 ) of 2 has a function relationship with the rate of change of coercive force ⁇ H C , and the rate of change of the above mechanical property parameters can be calculated according to formulas (32) to (35):
- ⁇ 1 , ⁇ 2 , ⁇ 3 and ⁇ 4 are proportional coefficients, and the specific values are the alloying element content of the material of the reactor pressure vessel steel, the defect distribution type and quantity concentration of the material, and the actual heat treatment process when the material is manufactured. And the influence of the size characteristics of the neutron irradiation field energy spectrum of the reactor core during the operation of the nuclear power plant.
- the rate of change ⁇ (RT NDT ) of the real-time non-ductile transition temperature RT NDT in this embodiment, the rate of change ⁇ (USE) of the real-time upper platform energy USE, and the rate of change ⁇ (R) of the real-time tensile strength R m can be calculated.
- m ) and the rate of change ⁇ (R p0.2 ) of the real-time yield strength R p0.2 can be calculated.
- RT NDT (1- ⁇ RT NDT ) ⁇ (RT NDT ) Initial (36)
- the calculation process of the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, the real-time tensile strength R m , and the real-time yield strength R p0.2 is:
- the conventional reactor pressure having the same degree of radiation damage (generally referred to as having the same neutron irradiation cumulative fluence) is taken.
- the container irradiation supervision sample was tested for destructive mechanical properties, and the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 were obtained .
- Table 4 lists the values of the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, the real-time tensile strength R m , and the real-time yield strength R p0.2 obtained in Example 1 and Comparative Example 1.
- the non-destructive evaluation method of the radiation damage of the nuclear power plant reactor pressure vessel using the coercive force can be used instead of the traditional irradiation supervision analysis method, which is not only simple in method, accurate in data, but also real-time online evaluation, and reactor pressure vessel steel
- the coercivity test is non-destructive, so the data can be tested indefinitely during the full life of the nuclear power plant and during future life extension operations.
- the non-destructive evaluation method of the radiation damage of the nuclear power plant reactor pressure vessel using the coercive force has at least the following beneficial technical effects:
- Test equipment and operation do not require special radiation safety protection requirements, and there is basically no requirement for the external space of the equipment, and the safety is good, especially no radioactive waste is generated, and there is basically no need for three waste treatment;
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Abstract
A non-destructive assessment method for the radiation damage of a reactor pressure vessel in a nuclear power plant, comprising the following steps: S01, monitoring in real time magnetic performance parameters of a certain monitored part of the steel of a reactor pressure vessel during a normal operation period of a nuclear power plant, the magnetic performance parameters being any one from among magnetic susceptibility χ, residual magnetization MR and coercivity HC; S02, on the basis of the measured magnetic performance parameters, calculating neutron radiation damage fluence Φ or mechanical properties of the reactor pressure vessel; S03, using the neutron radiation damage fluence Φ or the mechanical properties as analysis input parameters, performing safety assessment or service life prediction for the structural integrity of the reactor pressure vessel during a radiation damage process. The method may achieve real-time repeated non-destructive measurement, while data is accurate and test operations are safe; the present invention may simultaneously monitor the degree of radiation damage at multiple positions of the reactor pressure vessel.
Description
本发明属于核电领域，更具体地说，本发明涉及一种核电站反应堆压力容器辐照损伤的无损评估方法。The invention belongs to the field of nuclear power, and more particularly to a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel.
反应堆压力容器是核电站核岛内最为关键的大型设备之一，主要功能是包容和支承堆芯核燃料组件、控制组件、堆内构件和反应堆冷却剂的钢制承压容器。它长期服役于强辐照、高温、高压环境，其中，中子辐照损伤(具体表现为反应堆压力容器钢辐照脆化过程中强度升高、韧性下降)是其主要失效方式之一。The reactor pressure vessel is one of the most critical large-scale equipment in the nuclear power plant nuclear island. Its main function is to contain and support the core nuclear fuel assembly, control components, internal components and reactor coolant steel pressure vessels. It is long-term service in strong radiation, high temperature and high pressure environment. Among them, neutron irradiation damage (specifically, the strength and toughness of the reactor pressure vessel steel during irradiation embrittlement) is one of the main failure modes.
为了确保反应堆压力容器运行的安全性，对其辐照损伤注量进行监测与评价是常用的方法之一。具体实施步骤如下：(1)在核电站首次装料运行之前，在反应堆压力容器内部安装4到6根辐照监督管，每根辐照监督管内装载裂变剂量探测器，通常包括U
238和Np
237两种裂变剂量探测元件，然后将探测元件分别封装到钛盒内，钛盒再装入氮化硼盒内，然后氮化硼盒再整体装入辐照监督管内。(2)根据辐照监督大纲制定的辐照监督管抽取计划，利用核电站换料检修的机会，定期从反应堆压力容器中抽取出辐照监督管，然后按照辐照防护要求包装后长途运输至定点的热室机构，切割解剖取出裂变剂量探测器，然后在热室内对其成分的变化等开展分析化验，进而计算获得裂变剂量探测器所接受的中子辐照损伤注量。(3)根据辐照监督管的超前因子，换算得到反应堆压力容器本体的中子辐照损伤注量，进而对反应堆压力容器的运行开展后续安全评价工作。
In order to ensure the safety of reactor pressure vessel operation, it is one of the commonly used methods to monitor and evaluate the radiation damage fluence. The specific implementation steps are as follows: (1) Before the first charge operation of the nuclear power plant, install 4 to 6 irradiation supervision tubes inside the reactor pressure vessel, and each irradiation supervision tube is loaded with a fission dose detector, usually including U 238 and Np 237. Two kinds of fission dose detecting components are then packaged into the titanium box respectively, and the titanium box is then placed in the boron nitride box, and then the boron nitride box is integrally placed in the irradiation supervisory tube. (2) According to the irradiation supervision tube extraction plan formulated by the irradiation supervision program, use the opportunity of refueling and maintenance of the nuclear power plant, periodically extract the irradiation supervision tube from the reactor pressure vessel, and then transport it to the fixed point after packaging according to the radiation protection requirements. The hot chamber mechanism cuts the fission dose detector and then analyzes the composition changes in the hot chamber to calculate the neutron irradiation damage fluence received by the fission dose detector. (3) According to the advance factor of the irradiation supervision tube, the neutron irradiation damage fluence of the reactor pressure vessel body is converted, and then the follow-up safety evaluation work is carried out on the operation of the reactor pressure vessel.
现有方法的缺点归纳如下：The shortcomings of the existing methods are summarized as follows:
1)裂变剂量探测器(U
238和Np
237)属于放射源，其生产、运输、销售等均需要专业资质，采购成本非常高，后续运输、按照等也极其麻烦；
1) The fission dose detectors (U 238 and Np 237 ) are radioactive sources. Their production, transportation and sales require professional qualifications. The procurement cost is very high, and subsequent transportation and compliance are extremely troublesome.
2)不能直接获得反应堆压力容器本体的辐照损伤注量，需通过超前因子换算，存在一定的误差，当超前因子较大时，该误差愈加明显，届时得到的中子辐照损伤注量的代表性较差；2) The radiation damage fluence of the reactor pressure vessel body cannot be directly obtained, and there is a certain error by the lead factor conversion. When the lead factor is large, the error becomes more and more obvious, and the neutron irradiation damage fluence obtained at that time is Poor representation;
3)由于辐照监督管的数量非常有限(通常只有4～6根，且必须在首次装料运行前一次性装载完毕，现有技术也不能实现运行一段时间后再补充安装辐照监督管，未来核电站延寿时该问题愈加突出)，相应的裂变剂量探测器数量也只有4～6个，因此，通过这种方法不能连续获得反应堆压力容器钢的中子辐照损伤注量；同时由于辐照监督管抽取、运输、切割解剖、裂变剂量探测器化验分析等工作至少需要1年时间，通过该方法获得反应堆压力容器钢的中子辐照损伤注量在时间上也存在明显的滞后性；3) Since the number of irradiation supervision tubes is very limited (usually only 4 to 6 and must be loaded once before the first loading operation, the prior art cannot realize the operation of the irradiation supervision tube after a certain period of operation, In the future, the problem is more prominent when the nuclear power plant is extended. The number of corresponding fission dose detectors is only 4-6. Therefore, the neutron irradiation damage fluence of the reactor pressure vessel steel cannot be continuously obtained by this method; It takes at least one year to supervise the extraction, transportation, cutting anatomy, and fission dose detector analysis and analysis. The neutron irradiation damage fluence of the reactor pressure vessel steel is also obviously hysteretic in time;
4)裂变剂量探测器属于一次性产品，且使用之后具有较强的放射性，同时在分析化验环节也产生大量放射性废物，后续三废处理量较大，成本较高；4) The fission dose detector is a one-time product, and has strong radioactivity after use. At the same time, a large amount of radioactive waste is generated in the analysis and testing, and the subsequent three wastes are processed in a large amount and the cost is high;
5)上述方法仅能从整体上监控反应堆压力容器堆芯区的中子辐照损伤注量，不具备监控反应堆压力容器其他零部件，尤其是特定位置的辐照损伤注量。5) The above method can only monitor the neutron irradiation damage fluence of the reactor pressure vessel core area as a whole, and does not have the monitoring of other parts of the reactor pressure vessel, especially the radiation damage fluence at a specific location.
有鉴于此，确有必要提供一种可实时、在线、连续测试的核电站反应堆压力容器辐照损伤的无损评估方法。In view of this, it is indeed necessary to provide a non-destructive evaluation method for radiation damage of nuclear power plant reactor pressure vessels that can be tested in real time, online, and continuously.
发明内容Summary of the invention
本发明的发明目的在于：克服现有技术的不足，提供一种可实时、在线、连续测试的核电站反应堆压力容器辐照损伤的无损评估方法。The object of the present invention is to overcome the deficiencies of the prior art and provide a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel which can be tested in real time, online and continuously.
大量实验研究发现，反应堆压力容器钢在服役时辐照脆化的过程中，其材料磁性能参数的变化规律与其中子辐照损伤注量有较好的关联性，通过监测反 应堆压力容器钢磁性能参数的变化，可获得其中子辐照损伤注量，进而以中子辐照损伤注量作为分析输入参数，对反应堆压力容器辐照损伤过程中其结构完整性进行安全评估或寿命预测。A large number of experimental studies have found that during the process of irradiation embrittlement of reactor pressure vessel steel, the variation of the magnetic properties of the material has a good correlation with the neutron irradiation damage fluence, and the magnetic properties of the reactor pressure vessel steel are monitored. The change of energy parameters can obtain the neutron irradiation damage fluence, and then use the neutron irradiation damage fluence as the input parameter to carry out safety assessment or life prediction of the structural integrity of the reactor pressure vessel during irradiation damage.
为了实现上述发明目的，本发明提供一种核电站反应堆压力容器辐照损伤的无损评估方法，其包括以下步骤：In order to achieve the above object, the present invention provides a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel, which comprises the following steps:
S01、实时监测核电站正常运行期间的反应堆压力容器钢某一监测部位的磁性能参数，所述磁性能参数为磁化率χ、剩余磁化强度M
R和矫顽力H
C中的任意一种；
S01, real-time monitoring magnetic performance parameters of a monitoring portion of the reactor pressure vessel steel during normal operation of the nuclear power plant, wherein the magnetic performance parameter is any one of a magnetic susceptibility χ, a residual magnetization M R and a coercive force H C ;
S02、基于实时测得的磁性能参数计算出反应堆压力容器的中子辐照损伤注量Φ或力学性能；以及S02, calculating a neutron irradiation damage Φ or mechanical property of the reactor pressure vessel based on the measured magnetic property parameters in real time;
S03、以中子辐照损伤注量Φ或力学性能作为分析输入参数，对反应堆压力容器辐照损伤过程中其结构完整性进行安全评估或寿命预测。S03, using neutron irradiation damage fluence Φ or mechanical properties as the input parameters of the analysis, the safety assessment or life prediction of the structural integrity of the reactor pressure vessel during the radiation damage process.
根据本发明的一个方面，本发明核电站反应堆压力容器辐照损伤的无损评估方法包括以下步骤：According to one aspect of the invention, a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel comprises the following steps:
S11、安全阈值确定：确定并记录反应堆压力容器钢的无延性转变温度的上限临界值(RT
NDT)
上限和上平台能量的下限临界值(USE)
下限；
S11, safety threshold value determination: determine and record upper threshold no ductile transition temperature of the reactor pressure vessel steel (RT NDT) the upper and lower threshold values of the upper shelf energy (USE) limit;
S12、实时监测：核电站正常运行期间，测得任意时间点反应堆压力容器监测部位辐照损伤后的磁化率χ；S12. Real-time monitoring: During the normal operation of the nuclear power plant, the magnetic susceptibility after irradiation damage of the monitoring part of the reactor pressure vessel at any time point is measured;
S13、分析计算：根据实时测得的磁化率χ，计算反应堆压力容器钢辐照损伤过程中的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2；
S13. Analytical calculation: Calculate the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R in the process of irradiation damage of reactor pressure vessel steel according to the measured magnetic susceptibility χ P0.2 ;
S14、安全评估：基于磁化率的下降速率和获得的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2，对反应堆压力容器钢辐照损伤程度进行安全评估。
S14. Safety assessment: Irradiation of reactor pressure vessel steel based on the rate of decline of magnetic susceptibility and the obtained real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 The degree of damage is assessed for safety.
根据本发明的一个方面，本发明核电站反应堆压力容器辐照损伤的无损评 估方法包括以下步骤：According to one aspect of the invention, the non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel comprises the following steps:
S21、实时监测核电站正常运行期间的反应堆压力容器钢同一监测部位的剩余磁化强度M
R，根据实时剩余磁化强度M
R相对于未辐照初始状态的剩余磁化强度(M
R)
初始的剩余磁化强度变化率ΔM
R，计算反应堆压力容器钢辐照损伤过程中的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2；
S21, the same parts of the monitored reactor pressure vessel steel nuclear power plant during normal operation of the real-time monitoring of the residual magnetization M R, with respect to the residual magnetization (M R) in the initial state according to the non-irradiated real residual magnetization M R of the initial residual magnetization The rate of change ΔM R is calculated for the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 during the irradiation damage of the reactor pressure vessel steel.
S22、基于获得的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2，对反应堆压力容器钢辐照损伤程度进行分析评估。
S22. Analyze and evaluate the degree of radiation damage of the reactor pressure vessel steel based on the obtained real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 .
根据本发明的一个方面，本发明核电站反应堆压力容器辐照损伤的无损评估方法包括以下步骤：According to one aspect of the invention, a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel comprises the following steps:
S31、初始监测：核电站首次装料运行之前，测得反应堆压力容器钢监测部位的初始矫顽力(H
C)
初始；
S31, IDP: Before loading the first nuclear power plant operation, monitoring of the measured portion of the reactor pressure vessel steel initial coercivity (H C) Initial;
S32、在线监控：核电站正常运行期间，测得任意时间点反应堆压力容器钢同一监测部位辐照损伤后的矫顽力H
C；
S32. On-line monitoring: During normal operation of the nuclear power plant, the coercive force H C after irradiation damage of the same monitoring part of the reactor pressure vessel steel at any time point is measured;
S33、实时分析：基于所述初始矫顽力(H
C)
初始和任意时间点测得的矫顽力H
C，根据公式(1)计算反应堆压力容器钢辐照损伤过程中的矫顽力变化率ΔH
C：
S33. Real-time analysis: based on the initial coercive force (H C ) initial and any time point measured coercive force H C , according to formula (1), the coercive force change during the irradiation damage of the reactor pressure vessel steel is calculated. Rate ΔH C :
ΔH
C＝[H
C-(H
C)
初始]/(H
C)
初始 (31)
ΔH C =[H C -(H C ) initial ]/(H C ) initial (31)
根据得出的矫顽力变化率ΔH
C计算反应堆压力容器钢辐照损伤过程中的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2；
Calculate the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 in the process of irradiation damage of reactor pressure vessel steel according to the obtained coercivity change rate ΔH C ;
S34、损伤评估：基于获得的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2，对反应堆压力容器钢辐照损伤程度进行安全评估。
S34. Damage assessment: Based on the obtained real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 , the degree of radiation damage of reactor pressure vessel steel is evaluated safely.
相对于现有技术，本发明核电站反应堆压力容器辐照损伤的无损评估方法 具有以下有益技术效果：Compared with the prior art, the non-destructive evaluation method for the radiation damage of the nuclear power plant reactor pressure vessel has the following beneficial technical effects:
1)可实时、在线、连续测试核电站运行期间反应堆压力容器钢的磁性能参数，并实时计算获得反应堆压力容器钢的中子辐损伤注量数据；1) The magnetic performance parameters of the reactor pressure vessel steel during the operation of the nuclear power plant can be tested in real time, online and continuously, and the neutron radiation damage fluence data of the reactor pressure vessel steel can be calculated in real time;
2)可同时监测反应堆压力容器多个位置的中子辐照损伤注量；2) Simultaneous monitoring of neutron irradiation damage fluence at multiple locations of the reactor pressure vessel;
3)由于反应堆压力容器钢的磁性能测试是无损的，在核电站全寿期，包括未来延寿运行期间可无限次测试获取数据；3) Since the magnetic performance test of the reactor pressure vessel steel is non-destructive, the data can be obtained indefinitely during the full life of the nuclear power plant, including during the future life extension operation;
4)测试设备及操作不需要特殊的辐射安全防护要求，且对设备外界空间基本无要求，成本低廉、安全性较好，尤其是不产生放射性废物，基本无三废处理需求。4) Test equipment and operation do not require special radiation safety protection requirements, and there is basically no requirement for the external space of the equipment. The cost is low and the safety is good. Especially, no radioactive waste is generated, and there is basically no need for three waste disposal.
下面结合附图和具体实施方式，对本发明核电站反应堆压力容器辐照损伤的无损评估方法进行详细说明，其中：The non-destructive evaluation method for the radiation damage of the nuclear power plant reactor pressure vessel of the present invention will be described in detail below with reference to the accompanying drawings and specific embodiments, wherein:
图1为本发明核电站反应堆压力容器辐照损伤的无损评估方法的步骤流程图。1 is a flow chart showing the steps of a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to the present invention.
图2为反应堆压力容器钢堆芯段部位磁化率与中子辐照损伤注量之间的函数关系图。Figure 2 is a graph showing the relationship between the magnetic susceptibility of the core portion of the reactor pressure vessel and the neutron irradiation damage fluence.
图3为反应堆压力容器钢堆芯段部位剩余磁化强度与中子辐照损伤注量之间的函数关系图。Figure 3 is a graph showing the relationship between the residual magnetization of the reactor core section of the reactor and the neutron irradiation damage fluence.
图4为反应堆压力容器钢堆芯段部位矫顽力与中子辐照损伤注量之间的函数关系图。Figure 4 is a graph showing the relationship between the coercivity of the reactor core section of the reactor and the neutron irradiation damage fluence.
为了使本发明的发明目的、技术方案及其技术效果更加清晰，以下结合附图和具体实施方式，对本发明进行进一步详细说明。应当理解的是，本说明书 中描述的具体实施方式仅仅是为了解释本发明，并非为了限定本发明。The present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments. The specific embodiments described in the specification are to be construed as illustrative only and not limiting.
请参照图1所示，本发明提供了一种核电站反应堆压力容器辐照损伤的无损评估方法，其包括以下步骤：Referring to FIG. 1, the present invention provides a non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel, which comprises the following steps:
S01、实时监测核电站正常运行期间的反应堆压力容器钢某一监测部位的磁性能参数，磁性能参数为磁化率χ、剩余磁化强度M
R和矫顽力H
C中的任意一种；
S01, real-time monitoring magnetic property parameters of a monitoring part of the reactor pressure vessel steel during normal operation of the nuclear power plant, the magnetic performance parameter being any one of a magnetic susceptibility χ, a residual magnetization M R and a coercive force H C ;
S02、基于实时测得的磁性能参数计算出反应堆压力容器的中子辐照损伤注量Φ；S02, calculating a neutron irradiation damage flu of the reactor pressure vessel based on the measured magnetic property parameters in real time;
S03、以中子辐照损伤注量Φ作为分析输入参数，对反应堆压力容器辐照损伤过程中其结构完整性进行安全评估或寿命预测。S03, using the neutron irradiation damage fluence Φ as the input parameter for analysis, the safety assessment or life prediction of the structural integrity of the reactor pressure vessel during the irradiation damage process.
反应堆压力容器钢在服役时辐照脆化的过程中，材料磁性能参数中磁化率χ、剩余磁化强度M
R和矫顽力H
C都分别与其中子辐照损伤注量有较好的关联性，因此，可通过监测磁化率χ、剩余磁化强度M
R和矫顽力H
C中任何一个参数来获得其中子辐照损伤注量Φ。
In the process of irradiation embrittlement of reactor pressure vessel steel, the magnetic susceptibility χ, residual magnetization M R and coercive force H C of the material magnetic properties parameters are respectively correlated with the neutron irradiation damage fluence. Therefore, the neutron irradiation damage fluence Φ can be obtained by monitoring any one of the magnetic susceptibility χ, the residual magnetization M R and the coercive force H C .
当实时监测的磁性能参数为磁化率χ时，磁化率χ与中子辐照损伤注量Φ之间的函数关系为公式(01)，When the magnetic performance parameter monitored in real time is the magnetic susceptibility χ, the functional relationship between the magnetic susceptibility χ and the neutron irradiation damage fluence Φ is the formula (01).
Φ＝c
1·㏑(b
1-a
1·χ) (01)
Φ=c 1 ·ln(b 1 -a 1 ·χ) (01)
其中，a
1的取值范围为0.75-1.38；b
1的取值范围为8.78-16.75；c
1的取值范围为0.042-0.17。a
1、b
1和c
1的取值会受到反应堆压力容器初始状态的晶粒度、位错类型、数量、第二相分布特点以及核电站运行期间反应堆中子辐照场能谱等因素的影响。对于特定的核电站与反应堆压力容器，也可通过传统的辐照监督裂变探测器测试数据加以确定或者修正。
Wherein, the value of a 1 ranges from 0.75 to 1.38; the range of b 1 ranges from 8.78 to 16.75; and the range of c 1 ranges from 0.042 to 0.17. The values of a 1 , b 1 and c 1 are affected by the grain size of the initial state of the reactor pressure vessel, the type of dislocation, the quantity, the distribution of the second phase, 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, they can also be determined or corrected by conventional radiation monitoring fission detector test data.
磁性能参数也可选择为剩余磁化强度M
R，剩余磁化强度M
R与中子辐照损伤注量Φ的函数关系为公式(02)：
The magnetic performance parameter can also be selected as the residual magnetization M R , and the residual magnetization M R is a function of the neutron irradiation damage flu Φ as the formula (02):
Φ＝b
2-a
2·M
R (02)
Φ=b 2 -a 2 ·M R (02)
其中，a
2的取值范围为0.087-0.23；b
2的取值范围为0.12-0.31。同样的，a
2和b
2的取值也会受到反应堆压力容器初始状态的晶粒度、位错类型、数量、第二相分布特点以及核电站运行期间反应堆中子辐照场能谱等因素的影响。对于特定的核电站与反应堆压力容器，也可通过传统的辐照监督裂变探测器测试数据加以确定或者修正。
Wherein, the value of a 2 ranges from 0.087 to 0.23; and the range of b 2 ranges from 0.12 to 0.31. Similarly, the values of a 2 and b 2 are also affected by the grain size of the initial state of the reactor pressure vessel, the type of dislocation, the quantity, the distribution of the second phase, and the energy spectrum of the reactor neutron irradiation field during the operation of the nuclear power plant. influences. For specific nuclear power plants and reactor pressure vessels, they can also be determined or corrected by conventional radiation monitoring fission detector test data.
当磁性能参数选择为矫顽力H
C时，矫顽力H
C与中子辐照损伤注量Φ的函数关系为公式(3)：
When the magnetic property parameter is selected as the coercive force H C , the relationship between the coercive force H C and the neutron irradiation damage flu is Φ (3):
Φ＝D-a
3·H
C+b
3·(H
C)
2-c
3·(H
C)
3 (03)
Φ=Da 3 ·H C +b 3 ·(H C ) 2 -c 3 ·(H C ) 3 (03)
其中，a
3的取值范围为1.79-3.21；b
3的取值范围为0.19-0.41；c
3的取值范围为0.007-0.19，D的取值范围为5.64-9.23。
Wherein, the value of a 3 ranges from 1.79 to 3.21; the range of b 3 ranges from 0.19 to 0.41; the range of c 3 ranges from 0.007 to 0.19, and the range of D ranges from 5.64 to 9.23.
同样的，D、a
3、b
3和c
3的取值也会受到反应堆压力容器初始状态的晶粒度、位错类型、数量、第二相分布特点以及核电站运行期间反应堆中子辐照场能谱等因素的影响。对于特定的核电站与反应堆压力容器，也可通过传统的辐照监督裂变探测器测试数据加以确定或者修正。
Similarly, the values of D, a 3 , b 3 and c 3 are also affected by the grain size of the initial state of the reactor pressure vessel, the type of dislocation, the quantity, the distribution of the second phase, and the reactor neutron irradiation field during the operation of the nuclear power plant. The influence of factors such as energy spectrum. For specific nuclear power plants and reactor pressure vessels, they can also be determined or corrected by conventional radiation monitoring fission detector test data.
将上述获得的中子辐照损伤注量Φ作为分析输入参数，用于开展反应堆压力容器辐照损伤的结构完整性安全评价、寿命预测等。具体方法与传统的辐照监督分析方法相同。The neutron irradiation damage fluence Φ obtained above is used as an input parameter for analysis, and it is used to carry out structural integrity safety evaluation and life prediction of radiation damage of reactor pressure vessel. The specific method is the same as the traditional irradiation supervision analysis method.
实施例1Example 1
以特定时间点实时监测反应堆压力容器钢堆芯段部位的磁性能参数为例。For example, the magnetic performance parameters of the reactor core section of the reactor pressure vessel are monitored in real time at a specific time point.
当特定时间点监测的磁性能参数为磁化率χ＝3.290，根据公式(01)可计算出中子辐照损伤注量Φ。When the magnetic performance parameter monitored at a specific time point is the magnetic susceptibility χ=3.290, the neutron irradiation damage fluence Φ can be calculated according to the formula (01).
考虑了反应堆压力容器钢初始状态的微观组织特征和核电站运行期间反应堆中子辐照场能谱的影响因素后，得出公式(01)中a
1、b
1和c
1的取值分别为1.07、13.15和0.07，则中子辐照损伤注量Φ的计算过程如下：
Considering the microstructure characteristics of the initial state of the reactor pressure vessel steel and the influencing factors of the reactor neutron irradiation field energy spectrum during the operation of the nuclear power plant, the values of a 1 , b 1 and c 1 in the formula (01) are respectively 1.07. 13.15 and 0.07, the calculation process of neutron irradiation damage Φ is as follows:
Φ＝0.07ln(13.15-1.07χ)＝0.07ln(13.15-1.07×3.290)＝0.15860dpaΦ=0.07ln(13.15-1.07χ)=0.07ln(13.15-1.07×3.290)=0.15860dpa
当磁性能参数为剩余磁化强度M
R，同一时间点测得的剩余磁化强度M
R＝0.24emu/g，根据公式(02)可计算出中子辐照损伤注量Φ。
When the magnetic performance parameter is the residual magnetization M R and the residual magnetization M R = 0.24emu/g measured at the same time point, the neutron irradiation damage Φ can be calculated according to the formula (02).
考虑各种影响因素后，公式(02)中，a
2和b
2的取值分别为0.14和0.19，则中子辐照损伤注量Φ的计算过程如下：
After considering various influencing factors, in formula (02), the values of a 2 and b 2 are 0.14 and 0.19, respectively, and the calculation process of neutron irradiation damage Φ is as follows:
Φ＝0.19-0.14·M
R＝0.19-0.14×0.24＝0.15640dpa
Φ=0.19-0.14·M R =0.19-0.14×0.24=0.15640dpa
当磁性能参数为矫顽力H
C，同一时间点测得的矫顽力H
C＝7.1Oe，根据公式(03)可计算出中子辐照损伤注量Φ。
When the magnetic property parameter is the coercive force H C and the coercive force measured at the same time point is H C =7.1 Oe, the neutron irradiation damage fluence Φ can be calculated according to the formula (03).
考虑各种影响因素后，公式(03)中，D、a
3、b
3和c
3的取值分别为7.65、2.56、0.29和0.01，则中子辐照损伤注量Φ的计算过程如下：
After considering various influencing factors, in formula (03), the values of D, a 3 , b 3 and c 3 are 7.65, 2.56, 0.29 and 0.01 respectively, then the calculation process of neutron irradiation damage Φ is as follows:
Φ＝7.65-2.56H
C+0.29(H
C)
2-0.01(H
C)
3＝0.15304dpa
Φ=7.65-2.56H C +0.29(H C ) 2 -0.01(H C ) 3 =0.15304dpa
本实施例中磁化率χ、剩余磁化强度M
R和矫顽力H
C分别与中子辐照损伤注量Φ的函数关系图如图2、图3和图4所示。
The relationship between the magnetic susceptibility χ, the residual magnetization M R and the coercive force H C in the present embodiment as a function of the neutron irradiation damage flu, respectively, is shown in Figs. 2, 3 and 4.
将计算出的中子辐照损伤注量Φ作为分析输入参数，对反应堆压力容器辐照损伤过程中的结构完整性进行安全评估或寿命预测；具体过程与传统的辐照监督分析方法相同。The calculated neutron irradiation damage fluence Φ is used as the input parameter to analyze the structural integrity of the reactor pressure vessel during the damage process. The specific process is the same as the traditional irradiation supervision analysis method.
对比例1Comparative example 1
为验证本发明核电站反应堆压力容器辐照损伤的无损评估方法的有效性，取具有相同辐照损伤程度(一般指具有相同的中子辐照累积注量)的传统的反应堆压力容器辐照监督试样进行破坏性力学性能试验，实测并获得堆芯段部位的中子辐照损伤注量Φ。In order to verify the effectiveness of the non-destructive evaluation method for the radiation damage of the reactor pressure vessel of the nuclear power plant of the present invention, a conventional reactor pressure vessel irradiation supervision test having the same degree of radiation damage (generally referring to the same neutron irradiation cumulative fluence) is taken. The destructive mechanical properties test was carried out, and the neutron irradiation damage Φ of the core section was obtained.
表1实施例1不同磁性能参数与对比例1得出的中子辐照损伤注量Φ的数值Table 1 Example 1 Different magnetic property parameters and the value of neutron irradiation damage Φ obtained by Comparative Example 1
通过表1可以看出，实施例1分别采用不同磁性能参数(磁化率χ、剩余磁化强度M
R和矫顽力H
C)计算得到的堆芯段部位的中子辐照损伤注量Φ的数值与对比例1实测值非常接近；偏差值在可接受的范围之内，不会对后续反应堆压力容器辐照损伤的安全评价带来影响。
It can be seen from Table 1 that the neutron irradiation damage Φ of the core portion calculated by the example 1 using different magnetic performance parameters (magnetic susceptibility χ, residual magnetization M R and coercive force H C ) The values are very close to the measured values of Comparative Example 1. The deviation values are within the acceptable range and will not affect the safety evaluation of the subsequent reactor pressure vessel irradiation damage.
因此，可采用本发明核电站反应堆压力容器辐照损伤的无损评估方法代替传统的辐照监督分析方法，不仅方法简单，数据精确，而且可实现实时在线评估，同时反应堆压力容器钢的磁化率、剩余磁化强度和矫顽力测试是无损的，因此在核电站全寿期以及未来延寿运行期间可无限次测试获取数据。Therefore, the non-destructive evaluation method of the radiation damage of the nuclear power plant reactor pressure vessel can be used instead of the traditional irradiation supervision analysis method, which is not only simple in method, accurate in data, but also real-time online evaluation, and the magnetic susceptibility and residual of the reactor pressure vessel steel. The magnetization and coercivity tests are non-destructive, so the data can be tested indefinitely during the full life of the nuclear power plant and during future life extension operations.
结合以上对本发明的详细描述可以看出，相对于现有技术，本发明至少具有以下有益技术效果：In combination with the above detailed description of the present invention, it can be seen that the present invention has at least the following beneficial technical effects with respect to the prior art:
1)可实时、在线、连续测试核电站运行期间反应堆压力容器钢的磁性能参数，并实时计算获得反应堆压力容器钢的中子辐损伤注量数据；1) The magnetic performance parameters of the reactor pressure vessel steel during the operation of the nuclear power plant can be tested in real time, online and continuously, and the neutron radiation damage fluence data of the reactor pressure vessel steel can be calculated in real time;
2)可同时监测反应堆压力容器多个位置的中子辐照损伤注量；2) Simultaneous monitoring of neutron irradiation damage fluence at multiple locations of the reactor pressure vessel;
3)由于反应堆压力容器钢的磁性能测试是无损的，因此在核电站全寿期，包括未来延寿运行期间可无限次测试获取数据；3) Since the magnetic performance test of the reactor pressure vessel steel is non-destructive, the data can be obtained indefinitely during the full life of the nuclear power plant, including during the future life extension operation;
4)测试设备及操作不需要特殊的辐射安全防护要求，且对设备外界空间基本无要求，成本低廉、安全性较好，尤其是不产生放射性废物，基本无三废处理需求。4) Test equipment and operation do not require special radiation safety protection requirements, and there is basically no requirement for the external space of the equipment. The cost is low and the safety is good. Especially, no radioactive waste is generated, and there is basically no need for three waste disposal.
利用磁化率χ的核电站反应堆压力容器辐照损伤的无损评估方法Non-destructive evaluation method for irradiation damage of nuclear power plant reactor pressure vessel using magnetic susceptibility
实施例1Example 1
一种利用磁化率的核电站反应堆压力容器辐照损伤的无损评估方法，其包括以下步骤：A non-destructive evaluation method for irradiated damage of a nuclear power plant reactor pressure vessel using magnetic susceptibility, comprising the following steps:
核电站首次装料运行之前，测得反应堆压力容器钢监测部位的初始磁化率(χ)
初始＝11.42，并从反应堆压力容器钢设备制造厂提供的设备完工报告中查询并记录未辐照初始状态的无延性转变温度(RT
NDT)
初始＝241K、上平台能量(USE)
初始 ＝335J、抗拉强度(R
m)
初始＝483MPa和屈服强度(R
p0.2)
初始＝591MPa。
Before the first charge operation of the nuclear power plant, the initial magnetic susceptibility (χ) of the reactor pressure vessel steel monitoring site was measured initially = 11.42, and the initial state of the unirradiated was inquired and recorded from the equipment completion report provided by the reactor pressure vessel steel equipment manufacturer. Non-ductile transition temperature (RT NDT ) initial = 241 K, upper platform energy (USE) initial = 335 J, tensile strength (R m ) initial = 483 MPa, and yield strength (R p0.2 ) initial = 591 MPa.
S11、安全阈值确定：确定并记录反应堆压力容器的无延性转变温度上限临界值(RT
NDT)
上限＝366K和上平台能量下限临界值(USE)
下限＝68J。
S11. Safety Threshold Determination: Determine and record the non-ductile transition temperature upper limit threshold (RT NDT ) upper limit = 366K of the reactor pressure vessel and the upper platform energy lower limit threshold (USE) lower limit = 68J.
上述临界阈值的具体数值取决于所监测的核电站所在国家的核安全法规要求、核电站运行时所采用的核安全大纲以及反应堆压力容器的具体部位等。本专利中提供的具体数值来源于美国核管会导则RG1.99(1988版)对反应堆压力容器堆芯段位置母材的要求。The specific value of the above critical threshold depends on the nuclear safety regulations of the country where the nuclear power plant is monitored, the nuclear safety program used in the operation of the nuclear power plant, and the specific location of the reactor pressure vessel. The specific values provided in this patent are derived from the requirements of the US Nuclear Regulatory Commission guidelines RG 1.99 (1988 edition) for the base material of the reactor pressure vessel core section.
S12、实时监测：核电站正常运行20年后，测得反应堆压力容器钢监测部位辐照损伤后的磁化率χ＝10.15，相比于上一年度，磁化率下降速率为0.56％/年。S12. Real-time monitoring: After 20 years of normal operation of the nuclear power plant, the magnetic susceptibility χ=10.15 after the irradiation damage of the reactor pressure vessel steel monitoring part was measured. Compared with the previous year, the magnetic susceptibility rate decreased by 0.56%/year.
S13、分析计算：根据公式(11)至公式(14)计算反应堆压力容器钢辐照损伤过程中的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2：
S13. Analytical calculation: Calculate real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength in the process of radiation damage of reactor pressure vessel steel according to formula (11) to formula (14) R p0.2 :
RT
NDT＝a
1+b
1·χ (11)
RT NDT = a 1 + b 1 · χ (11)
USE＝a
2+b
2·χ (12)
USE=a 2 +b 2 ·χ (12)
R
m＝a
3+b
3·χ (13)
R m = a 3 + b 3 · χ (13)
R
p0.2＝a
4+b
4·χ (14)
R p0.2 = a 4 + b 4 · χ (14)
其中，a
1的取值范围为450～680，b
1的取值范围为-18～-35；
Wherein, the value of a 1 ranges from 450 to 680, and the value of b 1 ranges from -18 to -35;
a
2的取值范围为270～420，b
2的取值范围为45～75；
a 2 ranges from 270 to 420, and b 2 ranges from 45 to 75;
a
3和a
4的取值范围为1200～2000，b
3和b
4的取值范围为-80～-135。
a 3 and a 4 have a value ranging from 1200 to 2000, and b 3 and b 4 have a value ranging from -80 to -135.
根据反应堆压力容器钢的材料合金元素成分含量、材料的缺陷分布类型及数量浓度、材料制造时的实际热处理工艺，以及核电站运行期间反应堆堆芯中子辐照场能谱大小特征的影响，并结合反应堆压力容器钢初始状态的磁化率(χ)
初始与无延性转变温度(RT
NDT)
初始、上平台能量(USE)
初始、抗拉强度(R
m)
初始和屈服强度(R
p0.2)
初始，以及该反应堆早期的辐照监督试样测试数据加以修正后确定，a
1 取值534，b
1取值-25，a
2取值-342，b
2取值59，a
3取值1756，b
3取值-102，a
4取值1743，b
4取值-110。因此，公式(11)至公式(14)为：
According to the content of the alloying element content of the material of the reactor pressure vessel steel, the type and quantity concentration of the defect distribution of the material, the actual heat treatment process during the manufacture of the material, and the influence of the size characteristics of the neutron irradiation field of the reactor core during the operation of the nuclear power plant, combined with Initialization of the pressure vessel of the reactor pressure vessel steel (χ) Initial and non-ductile transition temperature (RT NDT ) initial , upper platform energy (USE) initial , tensile strength (R m ) initial and yield strength (R p0.2 ) initial And the test data of the irradiation supervision sample in the early stage of the reactor is corrected, and the value of a 1 is 534, the value of b 1 is -25, the value of a 2 is -342, the value of b 2 is 59, and the value of a 3 is 1756. b 3 takes the value -102, a 4 takes the value 1743, and b 4 takes the value -110. Therefore, equations (11) through (14) are:
RT
NDT＝534-25χ (11)
RT NDT =534-25χ (11)
USE＝-342+59χ (12)USE=-342+59χ (12)
R
m＝1756-102χ (13)
R m =1756-102χ (13)
R
p0.2＝1743-110χ (14)
R p0.2 =1743-110χ (14)
在测得的实时磁化率χ＝10.15时，可计算出实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2：
When the measured real-time magnetic susceptibility χ=10.15, the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 can be calculated :
RT
NDT＝534-25×10.15＝280K
RT NDT = 534-25×10.15=280K
USE＝-342+59×10.15＝257JUSE=-342+59×10.15=257J
R
m＝1756-102×10.15＝721MPa
R m =1756-102×10.15=721MPa
R
p0.2＝1743-110×10.15＝627MPa。
R p0.2 = 1743-110 × 10.15 = 627 MPa.
S14、安全评估：S14, safety assessment:
RT
NDT＝280K<(RT
NDT)
上限＝366K，同时，USE＝257J>(USE)
下限＝68J，所以将上述计算出的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2作为分析输入参数，对反应堆压力容器辐照损伤过程中其结构完整性进行安全评估或寿命预测；具体过程与传统的辐照监督分析方法相同。
RT NDT = 280K < (RT NDT ) upper limit = 366K, and USE = 257J > (USE) lower limit = 68J, so the above calculated real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 are used as analytical input parameters to perform safety assessment or life prediction of the structural integrity of the reactor pressure vessel during irradiation damage; the specific process is the same as the traditional irradiation supervision analysis method.
预先设定的磁化率下降速率的预警值为1％/年，本实施例中磁化率χ下降速率为0.56％/年，低于安全预警值1％/年，因此无需对反应堆压力容器开展进一步的安全评估论证。The pre-set warning value of the rate of decrease of the magnetic susceptibility is 1%/year. In this embodiment, the rate of decrease of the magnetic susceptibility is 0.56%/year, which is lower than the safety warning value of 1%/year, so there is no need to further carry out the reactor pressure vessel. Security assessment argument.
对比例1Comparative example 1
为验证本发明利用磁化率的核电站反应堆压力容器辐照损伤的无损评估方法的有效性，取具有相同辐照损伤程度(一般指具有相同的中子辐照累积注量)的传统的反应堆压力容器辐照监督试样进行破坏性力学性能试验，实测并获得 其实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2。
In order to verify the effectiveness of the non-destructive evaluation method of the radiation damage of a nuclear power plant reactor pressure vessel using the magnetic susceptibility of the present invention, a conventional reactor pressure vessel having the same degree of radiation damage (generally referred to as having the same neutron irradiation cumulative fluence) is taken. The irradiated supervised samples were tested for destructive mechanical properties, and the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 were obtained .
表2列出了实施例1与对比例1得出的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2。
Table 2 lists the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 obtained in Example 1 and Comparative Example 1.
表2Table 2
通过表2可以看出，实施例1采用本发明利用磁化率的核电站反应堆压力容器辐照损伤的无损评估方法计算得到的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2的数值与对比例1实测值非常接近；偏差值均在可接受的范围之内，不会对后续反应堆压力容器辐照损伤的安全评价带来影响，而且由于反应堆压力容器钢的磁化率测试是无损的，因此在核电站全寿期以及未来延寿运行期间可无限次测试获取数据。再结合磁化率的下降速率，双重监测，可保证压力容器在运行过程中的安全性。
It can be seen from Table 2 that the first embodiment adopts the non-ductile transition temperature RT NDT calculated by the non-destructive evaluation method for the radiation damage of the nuclear power plant reactor pressure vessel using the magnetic susceptibility, the real-time upper platform energy USE, and the real-time tensile strength R. The values of m and real-time yield strength R p0.2 are very close to those of the comparative example 1; the deviation values are within the acceptable range, and will not affect the safety evaluation of the subsequent reactor pressure vessel radiation damage, and The magnetic susceptibility test of reactor pressure vessel steel is non-destructive, so the data can be tested indefinitely during the full life of the nuclear power plant and during future life extension operations. Combined with the rate of decline of magnetic susceptibility, dual monitoring can ensure the safety of the pressure vessel during operation.
结合以上对本发明的详细描述可以看出，相对于现有技术，本发明利用磁化率的核电站反应堆压力容器辐照损伤的无损评估方法至少具有以下有益技术效果：In combination with the above detailed description of the present invention, it can be seen that, relative to the prior art, the non-destructive evaluation method for irradiating damage of a nuclear power plant reactor pressure vessel using magnetic susceptibility has at least the following beneficial technical effects:
(1)根据磁化率对力学性能参数的函数关系，可实现对反应堆压力容器钢损伤程度的实时监测，并结合磁化率的下降速率，双重监测保证压力容器在运行过程中的安全性；(1) According to the magnetic susceptibility as a function of mechanical performance parameters, real-time monitoring of the damage degree of the reactor pressure vessel steel can be realized, combined with the rate of decline of the magnetic susceptibility, and double monitoring ensures the safety of the pressure vessel during operation;
(2)由于反应堆压力容器钢的磁化率测试是无损的，因此在核电站全寿期，包括未来延寿运行期间可无限次测试获取数据，实现实时监测；(2) Since the magnetic susceptibility test of the reactor pressure vessel steel is non-destructive, the data can be acquired indefinitely during the full life of the nuclear power plant, including the future life extension operation, to achieve real-time monitoring;
(3)测试设备及操作不需要特殊的辐射安全防护要求，且对设备外界空间基本无要求，安全性较好，尤其是不产生放射性废物，基本无三废处理需求；(3) Test equipment and operation do not require special radiation safety protection requirements, and there is basically no requirement for the external space of the equipment, and the safety is good, especially no radioactive waste is generated, and there is basically no need for three waste treatment;
(4)可同时监控反应堆压力容器多个位置的辐照损伤程度，尤其适用于监控在役检查时发现的微裂纹或疑似微裂纹的萌生、扩展行为。(4) Simultaneously monitor the degree of radiation damage at multiple locations of the reactor pressure vessel, especially for monitoring the initiation and propagation behavior of microcracks or suspected microcracks found during in-service inspection.
利用剩余磁化强度M
R的核电站反应堆压力容器辐照损伤的无损评估方法
Non-destructive evaluation method for irradiation damage of nuclear power plant reactor pressure vessel using residual magnetization M R
实施例1Example 1
一种利用剩余磁化强度的核电站反应堆压力容器辐照损伤的无损评估方法，其包括以下步骤：A non-destructive evaluation method for irradiated damage of a nuclear power plant reactor pressure vessel using residual magnetization includes the following steps:
从反应堆压力容器钢设备制造厂提供的设备完工报告中查询并记录未辐照初始状态的无延性转变温度(RT
NDT)
初始＝241K、上平台能量(USE)
初始＝335J、抗拉强度(R
m)
初始＝591MPa和屈服强度(R
p0.2)
初始＝483MPa。
Query and record the unexpanded transition temperature (RT NDT ) initial = 241K, upper platform energy (USE) initial = 335J, tensile strength (R) from the equipment completion report provided by the reactor pressure vessel steel equipment manufacturer. m ) initial = 591 MPa and yield strength (R p0.2 ) initial = 483 MPa.
S21、测得反应堆压力容器钢未辐照状态监测部位的初始剩余磁化强度(M
R)
初始＝1.33emu/g；核电站正常运行20年后，实时测得反应堆压力容器钢同一监测部位辐照损伤后的剩余磁化强度M
R＝0.99emu/g；根据公式(21)可得到实时剩余磁化强度M
R相对于未辐照初始状态的剩余磁化强度(M
R)
初始的剩余磁化强度变化率ΔM
R：
S21. The initial residual magnetization (M R ) of the unirradiated state of the reactor pressure vessel steel was measured initially = 1.33 emu / g; after 20 years of normal operation of the nuclear power plant, the radiation damage of the same monitoring part of the reactor pressure vessel steel was measured in real time. the residual magnetization M R = 0.99emu / g; according to equation (21) can be obtained in real time the residual magnetization M R with respect to the initial state of the non-irradiated residual magnetization (M R) of the initial rate of change of residual magnetization ΔM R :
ΔM
R＝[M
R-(M
R)
初始]/(M
R)
初始 (21)
ΔM R =[M R -(M R ) initial ]/(M R ) initial (21)
ΔM
R＝(0.99-1.33)/1.33＝-25.56％
ΔM R = (0.99-1.33) / 1.33 = -25.56%
经研究发现剩余磁化强度变化率ΔM
R与实时无延性转变温度RT
NDT的变化率ΔRT
NDT、实时上平台能量USE的变化率ΔUSE、实时抗拉强度R
m的变化率ΔR
m和实时屈服强度R
p0.2的变化率ΔR
p0.2呈现出规律的函数关系，因此根据剩余磁化强度变化率ΔM
R可得到实时力学性能参数的数据，具体函数关系表现为公式(22)至(25)：
The study found that the residual magnetization change rate ΔM R and the real-time non-ductile transition temperature RT NDT change rate ΔRT NDT , the real-time upper platform energy USE change rate ΔUSE, the real-time tensile strength R m change rate ΔR m and the real-time yield strength R The rate of change ΔR p0.2 of p0.2 exhibits a regular functional relationship. Therefore, the data of real-time mechanical property parameters can be obtained according to the rate of change of residual magnetization ΔM R . The specific functional relationship is expressed by equations (22) to (25):
ΔRT
NDT＝λ
1·ΔM
R (22)
ΔRT NDT = λ 1 · ΔM R (22)
ΔUSE＝λ
2·ΔM
R (23)
ΔUSE=λ 2 ·ΔM R (23)
ΔR
m＝λ
3·ΔM
R (24)
ΔR m =λ 3 ·ΔM R (24)
ΔR
p0.2＝λ
4·ΔM
R (25)
ΔR p0.2 = λ 4 · ΔM R (25)
根据反应堆压力容器钢材料的化学元素成分、材料的加工工艺、材料的缺陷分布类型、辐照温度，以及核电站运行期间反应堆堆芯中子辐照场能谱的大小特征等这些因素，可大概确定出比例系数λ
1、λ
2、λ
3和λ
4的取值，再通过传统的辐照监督试样力学性能试验加以修正，最终得出λ
1＝0.62，λ
2＝0.95，λ
3＝0.87，λ
4＝1.10。所以，ΔRT
NDT、ΔUSE、ΔR
m和ΔR
p0.2的计算过程如下：
According to the chemical element composition of the reactor pressure vessel steel material, the processing technology of the material, the type of defect distribution of the material, the irradiation temperature, and the size characteristics of the neutron irradiation field energy spectrum of the reactor core during the operation of the nuclear power plant, etc. The values of the proportional coefficients λ 1 , λ 2 , λ 3 and λ 4 are corrected by the traditional mechanical test of the irradiation supervision sample, and finally λ 1 = 0.62, λ 2 = 0.95, λ 3 = 0.87 , λ 4 = 1.10. Therefore, the calculation process of ΔRT NDT , ΔUSE, ΔR m and ΔR p0.2 is as follows:
ΔRT
NDT＝0.62ΔM
R＝-15.85％
ΔRT NDT = 0.62 ΔM R = -15.85%
ΔUSE＝0.95ΔM
R＝-24.28％
ΔUSE=0.95ΔM R = -24.28%
ΔR
m＝0.87ΔM
R＝-22.24％
ΔR m =0.87ΔM R =-22.24%
ΔR
p0.2＝1.10ΔM
R＝-28.12％
ΔR p0.2 =1.10ΔM R =-28.12%
在已知(RT
NDT)
初始、(USE)
初始、(R
m)
初始和(R
p0.2)
初始，以及ΔRT
NDT、ΔUSE、ΔR
m和ΔR
p0.2的情况下，根据公式(26)至(29)可计算出本实施例中实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m、实时屈服强度R
p0.2：
In the case of the known (RT NDT ) initial , (USE) initial , (R m ) initial and (R p0.2 ) initial , and ΔRT NDT , ΔUSE, ΔR m and ΔR p0.2 , according to equation (26) To (29), the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, the real-time tensile strength R m , and the real-time yield strength R p0.2 can be calculated in this embodiment:
RT
NDT＝(1-ΔRT
NDT)·(RT
NDT)
初始 (26)
RT NDT = (1-ΔRT NDT )·(RT NDT ) Initial (26)
USE＝(1+ΔUSE)·(USE)
初始 (27)
USE=(1+ΔUSE)·(USE) Initial (27)
R
m＝(1-ΔR
m)·(R
m)
初始 (28)
R m = (1 - ΔR m ) · (R m ) initial (28)
R
p0.2＝(1-ΔR
p0.2)·(R
p0.2)
初始 (29)
R p0.2 =(1-ΔR p0.2 )·(R p0.2 ) initial (29)
因此，RT
NDT、USE、R
m和R
p0.2的具体计算过程如下：
Therefore, the specific calculation process of RT NDT , USE, R m and R p0.2 is as follows:
RT
NDT＝[1-(-15.85％)]×241＝279.19K
RT NDT = [1-(-15.85%)] × 241 = 279.19K
USE＝[1+(-24.28％)]×335＝253.66JUSE=[1+(-24.28%)]×335=253.66J
R
m＝[1-(-22.24％)]×591＝722.42MPa
R m =[1-(-22.24%)]×591=722.42MPa
R
p0.2＝[1-(-28.12％)]×483＝618.8MPa
R p0.2 = [1-(-28.12%)] × 483 = 618.8MPa
S22、将上述计算出的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2作为分析输入参数，对反应堆压力容器辐照损伤过程中的结构完整性进行安全评估或寿命预测；具体过程与传统的辐照监督分析方法相同。
S22. Calculating the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, the real-time tensile strength R m and the real-time yield strength R p0.2 as the analysis input parameters, in the process of irradiating the reactor pressure vessel Structural integrity is performed for safety assessment or life prediction; the specific process is the same as the traditional irradiation supervision analysis method.
对比例1Comparative example 1
为验证本发明利用剩余磁化强度的核电站反应堆压力容器辐照损伤的无损评估方法的有效性，取具有相同辐照损伤程度(一般指具有相同的中子辐照累积注量)的传统的反应堆压力容器辐照监督试样进行破坏性力学性能试验，实测并获得其实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2。
In order to verify the effectiveness of the non-destructive evaluation method of the radiation damage of the nuclear power plant reactor pressure vessel using the residual magnetization of the present invention, the conventional reactor pressure having the same degree of radiation damage (generally referred to as having the same neutron irradiation cumulative fluence) is taken. The container irradiation supervision sample was tested for destructive mechanical properties, and the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 were obtained .
表3列出了实施例1与对比例1得出的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2的数值。
Table 3 lists the values of the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, the real-time tensile strength R m , and the real-time yield strength R p0.2 obtained in Example 1 and Comparative Example 1.
表3table 3
通过表3可以看出，实施例1采用本发明利用剩余磁化强度的核电站反应堆压力容器辐照损伤的无损评估方法计算得到的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2的数值分别为279.19K、253.66J、722.42Mpa和618.8Mpa，而对比例1实测的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2的数值分别为274K、260J、717MPa和623MPa。
It can be seen from Table 3 that the first embodiment adopts the non-ductile transition temperature RT NDT calculated by the non-destructive evaluation method for the radiation damage of the nuclear power plant reactor pressure vessel using the residual magnetization, the real-time upper platform energy USE, and the real-time tensile strength. The values of R m and real-time yield strength R p0.2 are 279.19K, 253.66J, 722.42Mpa and 618.8Mpa, respectively, while the real-time non-ductile transition temperature RT NDT , real-time platform energy USE, real-time tensile strength measured in Comparative Example 1 The values of R m and real-time yield strength R p0.2 are 274K, 260J, 717MPa, and 623MPa , respectively.
由此可见，实施例1计算出的数据与对比例1实测值非常接近，偏差均在6左右，偏差值均在可接受的范围之内，因此本发明利用剩余磁化强度的核电站 反应堆压力容器辐照损伤的无损评估方法可代替传统的辐照监督分析方法，而且可实时监测，可适用于核电站的全寿期，同时对监测所需条件无特殊要求，监测成本低，更具实用性。It can be seen that the data calculated in the first embodiment is very close to the measured value of the comparative example 1, the deviation is about 6, and the deviation values are all within an acceptable range. Therefore, the present invention utilizes the residual magnetization of the nuclear power plant reactor pressure vessel spokes. The non-destructive evaluation method of the damage can replace the traditional irradiation supervision and analysis method, and can be monitored in real time, which can be applied to the full life of the nuclear power plant. At the same time, there are no special requirements for the conditions required for monitoring, and the monitoring cost is low and more practical.
结合以上对本发明的详细描述可以看出，相对于现有技术，本发明利用剩余磁化强度的核电站反应堆压力容器辐照损伤的无损评估方法至少具有以下有益技术效果：In combination with the above detailed description of the present invention, it can be seen that, relative to the prior art, the non-destructive evaluation method for irradiating damage of a nuclear power plant reactor pressure vessel utilizing residual magnetization has at least the following beneficial technical effects:
(1)通过对压力反应堆容器钢进行实时剩余磁化强度的监测，可实现实时监控并评估压力容器的损伤程度，随时掌握反应容器的运行状态，保证整体的安全性。(1) By monitoring the real-time residual magnetization of the pressure reactor vessel steel, real-time monitoring and evaluation of the damage degree of the pressure vessel can be realized, and the operating state of the reaction vessel can be grasped at any time to ensure the overall safety.
(2)实时监控评估的全过程对压力堆反应容器不会产生任何损伤，并可实现多个监测部位的同时监测，即易于操作，出结果速度快，而且得出的数据精确，经济环保，可完全代替传统的辐照监督分析方法。(2) The whole process of real-time monitoring and evaluation will not cause any damage to the pressure reactor reaction vessel, and can realize simultaneous monitoring of multiple monitoring parts, that is, easy to operate, the result is fast, and the obtained data is accurate, economical and environmentally friendly. It can completely replace the traditional irradiation supervision analysis method.
(3)整个监测评估的过程中不会接触和产生放射性物质，因此不需要特殊的辐射安全防护要求，安全性较好，基本无三废处理需求。(3) The entire monitoring and evaluation process will not contact and produce radioactive materials, so no special radiation safety protection requirements are required, and the safety is good. There is basically no need for three waste disposal.
利用矫顽力H
C的核电站反应堆压力容器辐照损伤的无损评估方法
Non-destructive evaluation method for radiation damage of nuclear power plant reactor pressure vessel using coercivity H C
实施例1Example 1
一种利用矫顽力的核电站反应堆压力容器辐照损伤的无损评估方法，其包括以下步骤：A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel using coercivity, comprising the following steps:
从反应堆压力容器钢设备制造厂提供的设备完工报告中查询并记录未辐照初始状态的无延性转变温度(RT
NDT)
初始＝241K、上平台能量(USE)
初始＝335J、抗拉强度(R
m)
初始＝591MPa和屈服强度(R
p0.2)
初始＝483MPa。
Query and record the unexpanded transition temperature (RT NDT ) initial = 241K, upper platform energy (USE) initial = 335J, tensile strength (R) from the equipment completion report provided by the reactor pressure vessel steel equipment manufacturer. m ) initial = 591 MPa and yield strength (R p0.2 ) initial = 483 MPa.
S31、初始监测：核电站首次装料运行之前，测得反应堆压力容器钢监测部位的初始矫顽力(H
C)
初始＝10.2Oe；
S31. Initial monitoring: Before the first charge operation of the nuclear power plant, the initial coercive force (H C ) of the reactor pressure vessel steel monitoring part is measured initially = 10.2 Oe;
S32、在线监控：核电站正常运行20年后，测得反应堆压力容器钢同一监测部位辐照损伤后的矫顽力H
C＝9.6Oe；
S32, online monitoring: 20 years after the normal operation of the nuclear power plant, the coercive force H C = 9.6Oe after the irradiation damage of the same monitoring part of the reactor pressure vessel steel is measured;
S33、实时分析：基于初始矫顽力(H
C)
初始和实时测得的矫顽力H
C，根据公式(31)计算反应堆压力容器钢辐照损伤过程中的矫顽力变化率ΔH
C：
S33. Real-time analysis: Based on the initial coercive force (H C ) initial and real-time measured coercive force H C , the coercive force change rate ΔH C during the irradiation damage of the reactor pressure vessel steel is calculated according to formula (31):
ΔH
C＝[H
C-(H
C)
初始]/(H
C)
初始 (31)
ΔH C =[H C -(H C ) initial ]/(H C ) initial (31)
ΔH
C＝(9.6-10.2)/10.2＝-5.88％
ΔH C = (9.6-10.2)/10.2=-5.88%
实时无延性转变温度RT
NDT的变化率Δ(RT
NDT)、实时上平台能量USE的变化率Δ(USE)、实时抗拉强度R
m的变化率Δ(R
m)和实时屈服强度R
p0.2的变化率Δ(R
p0.2)与矫顽力变化率ΔH
C具有函数关系，根据公式(32)至(35)可计算出上述力学性能参数的变化率：
Real-time non-ductile transition temperature RT NDT change rate Δ(RT NDT ), real-time upper platform energy USE change rate Δ(USE), real-time tensile strength R m change rate Δ(R m ) and real-time yield strength R p0. The rate of change Δ(R p0.2 ) of 2 has a function relationship with the rate of change of coercive force ΔH C , and the rate of change of the above mechanical property parameters can be calculated according to formulas (32) to (35):
Δ(RT
NDT)＝λ
1·ΔH
C (32)
Δ(RT NDT )=λ 1 ·ΔH C (32)
Δ(USE)＝λ
2·ΔH
C (33)
Δ(USE)=λ 2 ·ΔH C (33)
Δ(R
m)＝λ
3·ΔH
C (34)
Δ(R m )=λ 3 ·ΔH C (34)
Δ(R
p0.2)＝λ
4·ΔH
C (35)
Δ(R p0.2 )=λ 4 ·ΔH C (35)
其中，λ
1、λ
2、λ
3和λ
4为比例系数，具体取值受反应堆压力容器钢的材料中合金元素成分含量、材料的缺陷分布类型及数量浓度、材料制造时的实际热处理工艺，以及核电站运行期间反应堆堆芯中子辐照场能谱的大小特征等相关因素的影响。在本实施例中，考虑上述影响因素后，再通过传统的辐照监督试样力学性能试验加以修正，得出λ
1＝2.82，λ
2＝4.01，λ
3＝3.39，λ
4＝4.68。
Where λ 1 , λ 2 , λ 3 and λ 4 are proportional coefficients, and the specific values are the alloying element content of the material of the reactor pressure vessel steel, the defect distribution type and quantity concentration of the material, and the actual heat treatment process when the material is manufactured. And the influence of the size characteristics of the neutron irradiation field energy spectrum of the reactor core during the operation of the nuclear power plant. In the present embodiment, after considering the above-mentioned influencing factors, the mechanical properties of the conventional irradiation supervision sample are corrected to obtain λ 1 = 2.82, λ 2 = 4.01, λ 3 = 3.39, and λ 4 = 4.68.
因此，可计算出本实施例中实时无延性转变温度RT
NDT的变化率Δ(RT
NDT)、实时上平台能量USE的变化率Δ(USE)、实时抗拉强度R
m的变化率Δ(R
m)和实时屈服强度R
p0.2的变化率Δ(R
p0.2)：
Therefore, the rate of change Δ(RT NDT ) of the real-time non-ductile transition temperature RT NDT in this embodiment, the rate of change Δ(USE) of the real-time upper platform energy USE, and the rate of change Δ(R) of the real-time tensile strength R m can be calculated. m ) and the rate of change Δ(R p0.2 ) of the real-time yield strength R p0.2 :
Δ(RT
NDT)＝2.82ΔH
C＝-16.58％
Δ(RT NDT )=2.82ΔH C =−16.58%
Δ(USE)＝4.01ΔH
C＝-23.58％
Δ(USE)=4.01ΔH C =-23.58%
Δ(R
m)＝3.39ΔH
C＝-19.93％
Δ(R m )=3.39ΔH C =-19.93%
Δ(R
p0.2)＝4.68ΔH
C＝-27.52％
Δ(R p0.2 )=4.68ΔH C =-27.52%
再根据公式(36)至(39)计算本实施例中实时无延性转变温度RT
NDT、 实时上平台能量USE、实时抗拉强度R
m、实时屈服强度R
p0.2：
Then calculate the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, the real-time tensile strength R m , and the real-time yield strength R p0.2 according to the formulas (36) to (39):
RT
NDT＝(1-ΔRT
NDT)·(RT
NDT)
初始 (36)
RT NDT = (1-ΔRT NDT )·(RT NDT ) Initial (36)
USE＝(1+ΔUSE)·(USE)
初始 (37)
USE=(1+ΔUSE)·(USE) Initial (37)
R
m＝(1-ΔR
m)·(R
m)
初始 (38)
R m = (1 - ΔR m ) · (R m ) initial (38)
R
p0.2＝(1-ΔR
p0.2)·(R
p0.2)
初始 (39)
R p0.2 =(1-ΔR p0.2 )·(R p0.2 ) initial (39)
因此，本实施例中实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m、实时屈服强度R
p0.2的计算过程为：
Therefore, in the present embodiment, the calculation process of the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, the real-time tensile strength R m , and the real-time yield strength R p0.2 is:
RT
NDT＝[1-(-16.58％)]×241＝280.96K
RT NDT = [1-(-16.58%)] × 241 = 280.96K
USE＝[1+(-23.58％)]×335＝256.01JUSE=[1+(-23.58%)]×335=256.01J
R
m＝[1-(-19.93％]×591＝708.81MPa
R m =[1-(-19.93%]×591=708.81MPa
R
p0.2＝[1-(-27.52％]×483＝615.91MPa
R p0.2 =[1-(-27.52%]×483=615.91MPa
S34、损伤评估：将上述计算出的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2作为分析输入参数，对反应堆压力容器辐照损伤过程中的结构完整性进行安全评估或寿命预测；具体过程与传统的辐照监督分析方法相同。
S34. Damage assessment: The above-mentioned calculated real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 are used as analytical input parameters to irradiate the reactor pressure vessel. The structural integrity of the process is assessed for safety or life; the specific process is the same as the traditional irradiance monitoring method.
对比例1Comparative example 1
为验证本发明利用矫顽力的核电站反应堆压力容器辐照损伤的无损评估方法的有效性，取具有相同辐照损伤程度(一般指具有相同的中子辐照累积注量)的传统的反应堆压力容器辐照监督试样进行破坏性力学性能试验，实测并获得其实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2。
In order to verify the effectiveness of the non-destructive evaluation method of the radiation damage of a nuclear power plant reactor pressure vessel using coercivity, the conventional reactor pressure having the same degree of radiation damage (generally referred to as having the same neutron irradiation cumulative fluence) is taken. The container irradiation supervision sample was tested for destructive mechanical properties, and the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 were obtained .
表4列出了实施例1与对比例1得出的实时无延性转变温度RT
NDT、实时上平台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2的数值。
Table 4 lists the values of the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, the real-time tensile strength R m , and the real-time yield strength R p0.2 obtained in Example 1 and Comparative Example 1.
通过表4可以看出，实施例1采用本发明利用矫顽力的核电站反应堆压力容器辐照损伤的无损评估方法计算得到的实时无延性转变温度RT
NDT、实时上平 台能量USE、实时抗拉强度R
m和实时屈服强度R
p0.2的数值与对比例1实测值非常接近；偏差值均在可接受的范围之内，不会对后续反应堆压力容器辐照损伤的安全评价带来影响。
It can be seen from Table 4 that the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, and the real-time tensile strength calculated by the non-destructive evaluation method of the radiation damage of the nuclear power plant reactor pressure vessel using the coercivity of the present invention are obtained. The values of R m and real-time yield strength R p0.2 are very close to those of Comparative Example 1; the deviation values are within acceptable limits and will not affect the safety assessment of subsequent reactor pressure vessel damage.
因此可采用本发明利用矫顽力的核电站反应堆压力容器辐照损伤的无损评估方法代替传统的辐照监督分析方法，不仅方法简单，数据精确，而且可实现实时在线评估，同时反应堆压力容器钢的矫顽力测试是无损的，因此在核电站全寿期以及未来延寿运行期间可无限次测试获取数据。Therefore, the non-destructive evaluation method of the radiation damage of the nuclear power plant reactor pressure vessel using the coercive force can be used instead of the traditional irradiation supervision analysis method, which is not only simple in method, accurate in data, but also real-time online evaluation, and reactor pressure vessel steel The coercivity test is non-destructive, so the data can be tested indefinitely during the full life of the nuclear power plant and during future life extension operations.
表4Table 4
结合以上对本发明的详细描述可以看出，相对于现有技术，本发明利用矫顽力的核电站反应堆压力容器辐照损伤的无损评估方法至少具有以下有益技术效果：In combination with the above detailed description of the present invention, it can be seen that, relative to the prior art, the non-destructive evaluation method of the radiation damage of the nuclear power plant reactor pressure vessel using the coercive force has at least the following beneficial technical effects:
(1)根据矫顽力变化率与力学性能参数的函数关系，可实现对反应堆压力容器钢损伤程度的实时监测，保证压力容器在运行过程中的安全性；(1) According to the relationship between the change rate of coercivity and the mechanical property parameter, real-time monitoring of the damage degree of the reactor pressure vessel steel can be realized to ensure the safety of the pressure vessel during operation;
(2)由于反应堆压力容器钢的矫顽力测试是无损的，因此在核电站全寿期，包括未来延寿运行期间可无限次测试获取数据，实现实时监测；(2) Since the coercivity test of the reactor pressure vessel steel is non-destructive, the data can be acquired indefinitely during the full life of the nuclear power plant, including the future life extension operation, to achieve real-time monitoring;
(3)测试设备及操作不需要特殊的辐射安全防护要求，且对设备外界空间基本无要求，安全性较好，尤其是不产生放射性废物，基本无三废处理需求；(3) Test equipment and operation do not require special radiation safety protection requirements, and there is basically no requirement for the external space of the equipment, and the safety is good, especially no radioactive waste is generated, and there is basically no need for three waste treatment;
(4)可同时监控反应堆压力容器多个位置的辐照损伤程度，尤其适用于监控在役检查时发现的微裂纹或疑似微裂纹的萌生、扩展行为。(4) Simultaneously monitor the degree of radiation damage at multiple locations of the reactor pressure vessel, especially for monitoring the initiation and propagation behavior of microcracks or suspected microcracks found during in-service inspection.
根据上述原理，本发明还可以对上述实施方式进行适当的变更和修改。因此，本发明并不局限于上面揭示和描述的具体实施方式，对本发明的一些修改 和变更也应当落入本发明的权利要求的保护范围内。此外，尽管本说明书中使用了一些特定的术语，但这些术语只是为了方便说明，并不对本发明构成任何限制。According to the above principle, the present invention can also be appropriately modified and modified as described above. Therefore, the invention is not limited to the specific embodiments disclosed and described herein, and the modifications and variations of the invention are intended to fall within the scope of the appended claims. In addition, although specific terms are used in the specification, these terms are merely for convenience of description and do not limit the invention.
Claims (33)
- 一种核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，包括以下步骤：A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel, comprising the following steps:S01、实时监测核电站正常运行期间的反应堆压力容器钢某一监测部位的磁性能参数，所述磁性能参数为磁化率χ、剩余磁化强度M R和矫顽力H C中的任意一种； S01, real-time monitoring magnetic performance parameters of a monitoring portion of the reactor pressure vessel steel during normal operation of the nuclear power plant, wherein the magnetic performance parameter is any one of a magnetic susceptibility χ, a residual magnetization M R and a coercive force H C ;S02、基于实时测得的磁性能参数计算出反应堆压力容器的中子辐照损伤注量Φ或力学性能；以及S02, calculating a neutron irradiation damage Φ or mechanical property of the reactor pressure vessel based on the measured magnetic property parameters in real time;S03、以中子辐照损伤注量Φ或力学性能作为分析输入参数，对反应堆压力容器辐照损伤过程中其结构完整性进行安全评估或寿命预测。S03, using neutron irradiation damage fluence Φ or mechanical properties as the input parameters of the analysis, the safety assessment or life prediction of the structural integrity of the reactor pressure vessel during the radiation damage process.
- 根据权利要求1所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述磁性能参数为磁化率χ时，基于实时测得的磁化率χ计算中子辐照损伤注量Φ，表现为公式(01)：The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 1, wherein when the magnetic property parameter is a magnetic susceptibility χ, the neutron irradiation damage fluence is calculated based on the magnetic susceptibility measured in real time. Φ, expressed as formula (01):Φ＝c 1·㏑(b 1-a 1·χ) (01) Φ=c 1 ·ln(b 1 -a 1 ·χ) (01)其中，a 1的取值范围为0.75-1.38，b 1的取值范围为8.78-16.75，c 1的取值范围为0.042-0.17。 The range of a 1 is 0.75-1.38, the range of b 1 is 8.78-16.75, and the range of c 1 is 0.042-0.17.
- 根据权利要求2所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述a 1、b 1和c 1取值的影响因素包括反应堆压力容器钢初始状态的微观组织特征和核电站运行期间反应堆中子辐照场能谱。 The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 2, wherein the factors affecting the values of a 1 , b 1 and c 1 include microstructure characteristics of the initial state of the reactor pressure vessel steel and Reactor neutron irradiation field energy spectrum during nuclear power plant operation.
- 根据权利要求1所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，包括以下步骤：The method for non-destructive evaluation of radiation damage of a nuclear power plant reactor pressure vessel according to claim 1, comprising the steps of:S11、安全阈值确定：确定并记录反应堆压力容器钢的无延性转变温度的上限临界值(RT NDT) 上限和上平台能量的下限临界值(USE) 下限； S11, safety threshold value determination: determine and record upper threshold no ductile transition temperature of the reactor pressure vessel steel (RT NDT) the upper and lower threshold values of the upper shelf energy (USE) limit;S12、实时监测：核电站正常运行期间，测得任意时间点反应堆压力容器监 测部位辐照损伤后的磁化率χ；S12. Real-time monitoring: During normal operation of the nuclear power plant, the magnetic susceptibility after irradiation damage at the monitoring site of the reactor pressure vessel at any time point is measured;S13、分析计算：根据实时测得的磁化率χ，计算反应堆压力容器钢辐照损伤过程中的实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m和实时屈服强度R p0.2； S13. Analytical calculation: Calculate the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R in the process of irradiation damage of reactor pressure vessel steel according to the measured magnetic susceptibility χ P0.2 ;S14、安全评估：基于磁化率的下降速率和获得的实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m和实时屈服强度R p0.2，对反应堆压力容器钢辐照损伤程度进行安全评估。 S14. Safety assessment: Irradiation of reactor pressure vessel steel based on the rate of decline of magnetic susceptibility and the obtained real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 The degree of damage is assessed for safety.
- 根据权利要求4所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述无延性转变温度的上限临界值(RT NDT) 上限和上平台能量的下限临界值(USE) 下限根据核电站所在国家的核安全法规要求、核电站运行时所采用的核安全大纲、反应堆压力容器的具体部位确定而得到。 The method of non-destructive evaluation of radiation damage of the reactor pressure vessel of the nuclear power plant as claimed in claim 4, wherein said non-ductile transition temperature of the upper threshold (RT NDT) the upper and lower threshold values of the upper shelf energy (USE) limit According to the nuclear safety regulations of the country where the nuclear power plant is located, the nuclear safety program used in the operation of the nuclear power plant, and the specific location of the reactor pressure vessel.
- 根据权利要求4所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，基于实时测得的所述磁化率χ，根据公式(11)至公式(14)计算反应堆压力容器钢辐照损伤过程中的实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m和实时屈服强度R p0.2： The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 4, wherein the reactor pressure vessel steel spoke is calculated according to formula (11) to formula (14) based on the measured magnetic susceptibility 实时 in real time. The real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 during the damage process:RT NDT＝a 1+b 1·χ (11) RT NDT = a 1 + b 1 · χ (11)USE＝a 2+b 2·χ (12) USE=a 2 +b 2 ·χ (12)R m＝a 3+b 3·χ (13) R m = a 3 + b 3 · χ (13)R p0.2＝a 4+b 4·χ (14) R p0.2 = a 4 + b 4 · χ (14)其中，a 1的取值范围为450～680，b 1的取值范围为-18～-35； Wherein, the value of a 1 ranges from 450 to 680, and the value of b 1 ranges from -18 to -35;a 2的取值范围为270～420，b 2的取值范围为45～75； a 2 ranges from 270 to 420, and b 2 ranges from 45 to 75;a 3和a 4的取值范围为1200～2000，b 3和b 4的取值范围为-80～-135。 a 3 and a 4 have a value ranging from 1200 to 2000, and b 3 and b 4 have a value ranging from -80 to -135.
- 根据权利要求6所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述a 1与b 1、a 2与b 2、a 3与b 3、a 4与b 4的取值可分别通过反应堆压力容器钢未辐照初始状态的磁化率(χ) 初始与无延性转变温度(RT NDT) 初 始、上平台能量(USE) 初始、抗拉强度(R m) 初始和屈服强度(R p0.2) 初始，并结合传统的辐照监督试样力学性能试验结果加以确定或修正。 The method for non-destructive evaluation of radiation damage of a nuclear power plant reactor pressure vessel according to claim 6, wherein the a 1 and b 1 , a 2 and b 2 , a 3 and b 3 , a 4 and b 4 are taken. values may not irradiated by the initial state of the reactor pressure vessel steels of magnetic susceptibility ([chi]) and the initial non-ductile transition temperature (RT NDT) the initial, upper shelf energy (USE) initial tensile strength (R m) and the initial yield The strength (R p0.2 ) is initially determined and corrected in conjunction with the results of the traditional radiation monitoring test specimens.
- 根据权利要求7所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述磁化率(χ) 初始的测试过程为：在所述反应堆压力容器安装到位之后，在核电站首次装料运行之前，测得所述反应堆压力容器钢的初始磁化率(χ) 初始。 The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 7, wherein the initial test procedure of the magnetic susceptibility (χ) is: after the reactor pressure vessel is installed in place, the nuclear power plant is installed for the first time. before feeding operation, the measured initial susceptibility of the reactor pressure vessel steel ([chi]) initial.
- 根据权利要求7所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述(RT NDT) 初始、(USE) 初始、(R m) 初始和(R p0.2) 初始可从反应堆压力容器设备制造厂提供的设备完工报告中查询获得。 A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 7, wherein said (RT NDT ) initial , (USE) initial , (R m ) initial and (R p0.2 ) are initially Queryed from the equipment completion report provided by the reactor pressure vessel equipment manufacturer.
- 根据权利要求6所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述a 1、a 2、a 3和a 4，b 1、b 2、b 3和b 4的取值影响因素包括：反应堆压力容器钢的材料中合金元素成分含量、材料的缺陷分布类型及数量浓度、材料制造时的实际热处理工艺，以及核电站运行期间反应堆堆芯中子辐照场能谱的大小特征。 A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 6, wherein said a 1 , a 2 , a 3 and a 4 , b 1 , b 2 , b 3 and b 4 are taken The influencing factors include: the content of alloying elements in the material of the reactor pressure vessel steel, the type and concentration of the defect distribution of the material, the actual heat treatment process when the material is manufactured, and the energy spectrum of the neutron irradiation field of the reactor core during the operation of the nuclear power plant. feature.
- 根据权利要求6所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，当获得的实时无延性转变温度RT NDT<(RT NDT) 上限，且实时上平台能量USE>(USE) 下限时，将所述实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m和实时屈服强度R p0.2作为分析输入参数，对反应堆压力容器辐照损伤过程中的结构完整性进行安全评估或寿命预测。 The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 6, wherein when the real-time non-ductile transition temperature RT NDT <(RT NDT ) upper limit is obtained , and the platform energy USE> (USE) is real-time. when the lower limit, the non-ductile transition temperature of the real-time RT NDT, the USE real upper shelf energy, real-time tensile strength R m and the yield strength R p0.2 in real time as the analysis input parameters, radiation damage of the reactor pressure vessel during construction Integrity for safety assessment or life prediction.
- 根据权利要求11所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，预先设定磁化率下降速率的预警值，在获得的实时无延性转变温度RT NDT<(RT NDT) 上限，且实时上平台能量USE>(USE) 下限时，当实时测得的磁化率下降速率超过预设的预警值时，对反应堆压力容器开展进一步的安全评估论证。 A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 11, wherein a warning value of a rate of decrease of the magnetic susceptibility is set in advance, and an upper limit of the real-time non-ductile transition temperature RT NDT <(RT NDT ) is obtained. and real-time platform on energy USE> when (USE) limit, when measured in real time susceptibility rate of decrease exceeds a preset warning value, to carry out further safety assessment of argument of the reactor pressure vessel.
- 根据权利要求12所述的核电站反应堆压力容器辐照损伤的无损评估方 法，其特征在于，所述磁化率下降速率的预警值≥1％/年。A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 12, characterized in that the warning value of the rate of decrease of the magnetic susceptibility is ≥ 1% / year.
- 根据权利要求6所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，当获得的实时无延性转变温度RT NDT≥(RT NDT) 上限，或实时上平台能量USE≤(USE) 下限时，对反应堆压力容器开展全面的安全评估论证。 A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 6, wherein when the real-time non-ductile transition temperature RT NDT ≥ (RT NDT ) upper limit is obtained , or the real-time upper platform energy USE ≤ (USE) when the lower limit, carry out a comprehensive safety assessment of argument of the reactor pressure vessel.
- 根据权利要求1所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述磁性能参数为剩余磁化强度M R时，基于实时测得的剩余磁化强度M R计算中子辐照损伤注量Φ，表现为公式(12)： The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 1, wherein when the magnetic property parameter is residual magnetization M R , the neutron radiation is calculated based on the residual magnetization M R measured in real time. According to the damage fluence Φ, it is expressed as formula (12):Φ＝b 2-a 2·M R (12) Φ=b 2 -a 2 ·M R (12)其中，a 2的取值范围为0.087-0.23，b 2的取值范围为0.12-0.31。 Wherein, a 2 has a value ranging from 0.087 to 0.23, and b 2 has a value ranging from 0.12 to 0.31.
- 根据权利要求15所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述a 2和b 2取值的影响因素包括反应堆压力容器钢初始状态的微观组织特征和核电站运行期间反应堆中子辐照场能谱。 The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 15, wherein the factors affecting the values of the a 2 and b 2 include the microstructure characteristics of the initial state of the reactor pressure vessel steel and the operation period of the nuclear power plant. Reactor neutron irradiation field energy spectrum.
- 根据权利要求1所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，包括以下步骤：The method for non-destructive evaluation of radiation damage of a nuclear power plant reactor pressure vessel according to claim 1, comprising the steps of:S21、实时监测核电站正常运行期间的反应堆压力容器钢同一监测部位的剩余磁化强度M R，根据实时剩余磁化强度M R相对于未辐照初始状态的剩余磁化强度(M R) 初始的剩余磁化强度变化率ΔM R，计算反应堆压力容器钢辐照损伤过程中的实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m和实时屈服强度R p0.2； S21, the same parts of the monitored reactor pressure vessel steel nuclear power plant during normal operation of the real-time monitoring of the residual magnetization M R, with respect to the residual magnetization (M R) in the initial state according to the non-irradiated real residual magnetization M R of the initial residual magnetization The rate of change ΔM R is calculated for the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 during the irradiation damage of the reactor pressure vessel steel.S22、基于获得的实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m和实时屈服强度R p0.2，对反应堆压力容器钢辐照损伤程度进行分析评估。 S22. Analyze and evaluate the degree of radiation damage of the reactor pressure vessel steel based on the obtained real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 .
- 根据权利要求17所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述剩余磁化强度变化率ΔM R可根据公式(21)计算得出： The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 17, wherein the residual magnetization change rate ΔM R is calculated according to formula (21):ΔM R＝[M R-(M R) 初始]/(M R) 初始 (21)。 ΔM R = [M R - (M R ) initial ] / (M R ) initial (21).
- 根据权利要求18所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述剩余磁化强度变化率ΔM R与实时无延性转变温度RT NDT的变化率ΔRT NDT、实时上平台能量USE的变化率ΔUSE、实时抗拉强度R m的变化率ΔR m和实时屈服强度R p0.2的变化率ΔR p0.2具有函数关系，表现为公式(22)至(25)： The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 18, wherein the residual magnetization change rate ΔM R and the real-time non-ductile transition temperature RT NDT change rate ΔRT NDT , real-time upper platform energy The rate of change USE of USE, the rate of change ΔR m of the real-time tensile strength R m and the rate of change ΔR p0.2 of the real-time yield strength R p0.2 are expressed as equations (22) to (25):ΔRT NDT＝λ 1·ΔM R (22) ΔRT NDT = λ 1 · ΔM R (22)ΔUSE＝λ 2·ΔM R (23) ΔUSE=λ 2 ·ΔM R (23)ΔR m＝λ 3·ΔM R (24) ΔR m =λ 3 ·ΔM R (24)ΔR p0.2＝λ 4·ΔM R (25) ΔR p0.2 = λ 4 · ΔM R (25)其中，λ 1的取值范围为0.42-0.86，λ 2的取值范围为0.65-1.35，λ 3的取值范围为0.51-1.39，λ 4的取值范围为0.51-1.39。 The range of λ 1 is 0.42-0.86, the range of λ 2 is 0.65-1.35, the range of λ 3 is 0.51-1.39, and the range of λ 4 is 0.51-1.39.
- 根据权利要求19所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述λ 1、λ 2、λ 3和λ 4的取值范围受反应堆压力容器钢材料的化学元素成分、材料的加工工艺、材料的缺陷分布类型、辐照温度，以及核电站运行期间反应堆堆芯中子辐照场能谱的大小特征的影响。 A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 19, wherein said λ 1 , λ 2 , λ 3 and λ 4 are subjected to a chemical element composition of a reactor pressure vessel steel material. The processing technology of the material, the type of defect distribution of the material, the irradiation temperature, and the influence of the size characteristics of the neutron irradiation field energy spectrum of the reactor core during the operation of the nuclear power plant.
- 根据权利要求19所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述λ 1、λ 2、λ 3和λ 4可通过传统的辐照监督试样力学性能试验加以确定或修正。 The method for non-destructive evaluation of radiation damage of a nuclear power plant reactor pressure vessel according to claim 19, wherein said λ 1 , λ 2 , λ 3 and λ 4 are determined by a conventional irradiation supervision sample mechanical property test. Or fix it.
- 根据权利要求19所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，基于已知的(RT NDT) 初始、(USE) 初始、(R m) 初始和(R p0.2) 初始，以及计算得到的ΔRT NDT、ΔUSE、ΔR m和ΔR p0.2，可得出实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m、实时屈服强度R p0.2，表现为公式(26)至(9)： A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 19, characterized by based on known (RT NDT ) initial , (USE) initial , (R m ) initial sum (R p0.2 ) Initially , and the calculated ΔRT NDT , ΔUSE, ΔR m and ΔR p0.2 , the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m , real-time yield strength R p0.2 , expressed as formulas (26) to (9):RT NDT＝(1-ΔRT NDT)·(RT NDT) 初始 (26) RT NDT = (1-ΔRT NDT )·(RT NDT ) Initial (26)USE＝(1+ΔUSE)·(USE) 初始 (27) USE=(1+ΔUSE)·(USE) Initial (27)R m＝(1-ΔR m)·(R m) 初始 (28) R m = (1 - ΔR m ) · (R m ) initial (28)R p0.2＝(1-ΔR p0.2)·(R p0.2) 初始 (29) R p0.2 =(1-ΔR p0.2 )·(R p0.2 ) initial (29)其中，(RT NDT) 初始为反应堆压力容器钢未辐照初始状态无延性转变温度； Wherein, (RT NDT) for the initial non-irradiated reactor pressure vessel steel ductility transition temperature of no initial state;(USE) 初始为反应堆压力容器钢未辐照初始状态的上平台能量； (USE) Initially the upper platform energy of the initial state of the reactor pressure vessel steel not irradiated;(R m) 初始为反应堆压力容器钢未辐照初始状态的抗拉强度； (R m ) initially is the tensile strength of the initial state of the reactor pressure vessel steel not irradiated;(R p0.2) 初始为反应堆压力容器钢未辐照初始状态的屈服强度。 (R p0.2 ) is initially the yield strength of the initial state of the reactor pressure vessel steel not irradiated.
- 根据权利要求22所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述(RT NDT) 初始、(USE) 初始、(R m) 初始和(R p0.2) 初始均可从反应堆压力容器设备制造厂提供的设备完工报告中查询获得。 A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 22, wherein said (RT NDT ) initial , (USE) initial , (R m ) initial and (R p0.2 ) initial It can be obtained from the equipment completion report provided by the reactor pressure vessel equipment manufacturer.
- 根据权利要求22所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，将所述实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m、实时屈服强度R p0.2作为分析输入参数，对反应堆压力容器辐照损伤过程中的结构完整性进行安全评估或寿命预测。 The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 22, wherein the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m , real-time yield strength R p0.2 is used as an analytical input parameter to perform a safety assessment or life prediction of the structural integrity of the reactor pressure vessel during irradiation damage.
- 根据权利要求1所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述磁性能参数为矫顽力H C时，基于实时测得的矫顽力H C计算中子辐照损伤注量Φ，表现为公式(3)： The method of non-destructive evaluation of radiation damage of the reactor pressure vessel of the nuclear power plant as claimed in claim 1, wherein said parameter is a magnetic coercive force H C, measured in real time based on the coercive force H C calculated neutron radiation According to the damage fluence Φ, it is expressed as formula (3):Φ＝D-a 3·H C+b 3·(H C) 2-c 3·(H C) 3 (33) Φ=Da 3 ·H C +b 3 ·(H C ) 2 -c 3 ·(H C ) 3 (33)其中，a 3的取值范围为1.79-3.21，b 3的取值范围为0.19-0.41，c 3的取值范围为0.007-0.19，D的取值范围为5.64-9.23。 Wherein, the value of a 3 ranges from 1.79 to 3.21, the range of b 3 ranges from 0.19 to 0.41, the range of c 3 ranges from 0.007 to 0.19, and the range of D ranges from 5.64 to 9.23.
- 根据权利要求25所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述D、a 3、b 3和c 3取值的影响因素包括反应堆压力容器钢初始状态的微观组织特征和核电站运行期间反应堆中子辐照场能谱。 The method of non-destructive evaluation of radiation damage of the reactor pressure vessel of the nuclear power plant as claimed in claim 25, wherein said D, a 3, b 3 and c 3 factors including the value of the initial state of the reactor pressure vessel steel microstructure Characteristics and energy spectrum of the reactor neutron irradiation field during operation of the nuclear power plant.
- 根据权利要求1所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，包括以下步骤：The method for non-destructive evaluation of radiation damage of a nuclear power plant reactor pressure vessel according to claim 1, comprising the steps of:S31、初始监测：核电站首次装料运行之前，测得反应堆压力容器钢监测部 位的初始矫顽力(H C) 初始； S31, IDP: Before loading the first nuclear power plant operation, monitoring of the measured portion of the reactor pressure vessel steel initial coercivity (H C) Initial;S32、在线监控：核电站正常运行期间，测得任意时间点反应堆压力容器钢同一监测部位辐照损伤后的矫顽力H C； S32. On-line monitoring: During normal operation of the nuclear power plant, the coercive force H C after irradiation damage of the same monitoring part of the reactor pressure vessel steel at any time point is measured;S33、实时分析：基于所述初始矫顽力(H C) 初始和任意时间点测得的矫顽力H C，根据公式(1)计算反应堆压力容器钢辐照损伤过程中的矫顽力变化率ΔH C： S33. Real-time analysis: based on the initial coercive force (H C ) initial and any time point measured coercive force H C , according to formula (1), the coercive force change during the irradiation damage of the reactor pressure vessel steel is calculated. Rate ΔH C :ΔH C＝[H C-(H C) 初始]/(H C) 初始 (31) ΔH C =[H C -(H C ) initial ]/(H C ) initial (31)根据得出的矫顽力变化率ΔH C计算反应堆压力容器钢辐照损伤过程中的实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m和实时屈服强度R p0.2； Calculate the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 in the process of irradiation damage of reactor pressure vessel steel according to the obtained coercivity change rate ΔH C ;S34、损伤评估：基于获得的实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m和实时屈服强度R p0.2，对反应堆压力容器钢辐照损伤程度进行安全评估。 S34. Damage assessment: Based on the obtained real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m and real-time yield strength R p0.2 , the degree of radiation damage of reactor pressure vessel steel is evaluated safely.
- 根据权利要求27所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，基于所述矫顽力变化率ΔH C，根据公式(32)至(35)计算反应堆压力容器钢辐照损伤过程中的实时无延性转变温度RT NDT的变化率ΔRT NDT、实时上平台能量USE的变化率ΔUSE、实时抗拉强度R m的变化率ΔR m和实时屈服强度R p0.2的变化率ΔR p0.2： The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 27, wherein the reactor pressure vessel steel irradiation is calculated according to the formula (32) to (35) based on the coercive force change rate ΔH C Real-time non-ductile transition temperature during damage RT NDT change rate ΔRT NDT , real-time upper platform energy USE change rate ΔUSE, real-time tensile strength R m change rate ΔR m and real-time yield strength R p0.2 change rate ΔR P0.2 :ΔRT NDT＝λ 1·ΔH C (32) ΔRT NDT = λ 1 · ΔH C (32)ΔUSE＝λ 2·ΔH C (33) ΔUSE=λ 2 ·ΔH C (33)ΔR m＝λ 3·ΔH C (34) ΔR m =λ 3 ·ΔH C (34)ΔR p0.2＝λ 4·ΔH C (35) ΔR p0.2 = λ 4 · ΔH C (35)其中，λ 1的取值范围为2.11-3.48，λ 2的取值范围为3.37-4.84，λ 3的取值范围为2.91-5.62，λ 4的取值范围为2.91-5.62。 The range of λ 1 is 2.11-3.48, the range of λ 2 is 3.37-4.84, the range of λ 3 is 2.91-5.62, and the range of λ 4 is 2.91-5.62.
- 根据权利要求28所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述λ 1、λ 2、λ 3和λ 4取值的影响因素包括：反应堆压力容器 钢的材料中合金元素成分含量、材料的缺陷分布类型及数量浓度、材料制造时的实际热处理工艺，以及核电站运行期间反应堆堆芯中子辐照场能谱的大小特征。 The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 28, wherein the factors affecting the values of λ 1 , λ 2 , λ 3 and λ 4 include: materials of reactor pressure vessel steel The content of alloying elements, the type and concentration of defects in the material, the actual heat treatment process when the material is manufactured, and the size characteristics of the neutron irradiation field energy spectrum of the reactor core during operation of the nuclear power plant.
- 根据权利要求28所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述λ 1、λ 2、λ 3和λ 4可通过传统的辐照监督试样力学性能试验加以确定或修正。 The method for non-destructive evaluation of radiation damage of a nuclear power plant reactor pressure vessel according to claim 28, wherein said λ 1 , λ 2 , λ 3 and λ 4 are determined by a conventional irradiation supervision sample mechanical property test. Or fix it.
- 根据权利要求28所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，基于所述实时无延性转变温度RT NDT的变化率ΔRT NDT、实时上平台能量USE的变化率ΔUSE、实时抗拉强度R m的变化率ΔR m和实时屈服强度R p0.2的变化率ΔR p0.2，根据公式(36)至(39)计算实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m、实时屈服强度R p0.2： The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 28, characterized by: based on the real-time non-ductile transition temperature RT NDT change rate ΔRT NDT , real-time upper platform energy USE change rate ΔUSE, real-time The rate of change ΔR m of the tensile strength R m and the rate of change ΔR p0.2 of the real-time yield strength R p0.2 are calculated according to the formulas (36) to (39), and the real-time non-ductile transition temperature RT NDT , the real-time upper platform energy USE, Real-time tensile strength R m , real-time yield strength R p0.2 :RT NDT＝(1-ΔRT NDT)·(RT NDT) 初始 (36) RT NDT = (1-ΔRT NDT )·(RT NDT ) Initial (36)USE＝(1+ΔUSE)·(USE) 初始 (37) USE=(1+ΔUSE)·(USE) Initial (37)R m＝(1-ΔR m)·(R m) 初始 (38) R m = (1 - ΔR m ) · (R m ) initial (38)R p0.2＝(1-ΔR p0.2)·(R p0.2) 初始 (39) R p0.2 =(1-ΔR p0.2 )·(R p0.2 ) initial (39)其中，(RT NDT) 初始为反应堆压力容器钢未辐照初始状态无延性转变温度； Wherein, (RT NDT ) is initially a non-ductile transition temperature in the initial state of the reactor pressure vessel steel not irradiated;(USE) 初始为反应堆压力容器钢未辐照初始状态的上平台能量； (USE) Initially the upper platform energy of the initial state of the reactor pressure vessel steel not irradiated;(R m) 初始为反应堆压力容器钢未辐照初始状态的抗拉强度； (R m ) initially is the tensile strength of the initial state of the reactor pressure vessel steel not irradiated;(R p0.2) 初始为反应堆压力容器钢未辐照初始状态的屈服强度。 (R p0.2 ) is initially the yield strength of the initial state of the reactor pressure vessel steel not irradiated.
- 根据权利要求31所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，所述(RT NDT) 初始、(USE) 初始、(R m) 初始和(R p0.2) 初始均可从反应堆压力容器设备制造厂提供的设备完工报告中查询获得。 A non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 31, wherein said (RT NDT ) initial , (USE) initial , (R m ) initial and (R p0.2 ) initial It can be obtained from the equipment completion report provided by the reactor pressure vessel equipment manufacturer.
- 根据权利要求31所述的核电站反应堆压力容器辐照损伤的无损评估方法，其特征在于，将所述实时无延性转变温度RT NDT、实时上平台能量USE、实时抗拉强度R m、实时屈服强度R p0.2作为分析输入参数，对反应堆压力容器辐照 损伤过程中的结构完整性进行安全评估或寿命预测。 The non-destructive evaluation method for radiation damage of a nuclear power plant reactor pressure vessel according to claim 31, wherein the real-time non-ductile transition temperature RT NDT , real-time upper platform energy USE, real-time tensile strength R m , real-time yield strength R p0.2 is used as an analytical input parameter to perform a safety assessment or life prediction of the structural integrity of the reactor pressure vessel during irradiation damage.
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