CN110457828B - Environment-promoted fatigue-sensitive position screening method for M310 nuclear power unit - Google Patents
Environment-promoted fatigue-sensitive position screening method for M310 nuclear power unit Download PDFInfo
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Abstract
The invention discloses a screening method of environment-promoted fatigue sensitive positions suitable for an M310 nuclear power unit, which comprises the following steps: counting transient information, combing each system, and dividing hot areas; defining a typical position by considering the severity of the nuclear leakage consequence, the size of a design cumulative use factor value and the influence of a thermal shock transient frequency; for each hot zone, each material, each potential EAF sensitive location, if the location is a typical location then the sensitive location is a sensitive location, if the location is an atypical location and all transient maximum temperatures do not exceed 200 ℃ then the effect of the EAF need not be considered, if the location is an atypical location and all transient maximum temperatures exceed 200 ℃ then F is calculated en (ii) a If calculated F en ≤F en‑int The EAF problem does not need to be considered, otherwise, the fatigue accumulative use factor is calculated according to the accumulative use factor; all potentially sensitive locations per system, per thermal zone, per material are assigned to CUF en Sorting in descending order and preliminary screening; and combining the primarily selected EAF sensitive positions, and determining the sensitive positions needing EAF monitoring.
Description
Technical Field
The invention belongs to the technical field of extended demonstration of the valid period of an operation license of a nuclear power plant, and relates to an Environmental Accelerated Fatigue (EAF) sensitive position screening method suitable for an M310 nuclear power unit.
Background
The extended demonstration of the valid period of the nuclear power plant operation license is to make corresponding improvement through safety demonstration and environmental impact evaluation, so that the nuclear power plant can continue to operate beyond the time specified by the original operation license. In countries such as the United states and Russia, a plurality of nuclear power generating units operate beyond the time specified by the original operation license, the Qinshan nuclear power plant and the Bay nuclear power plant in China are also planned to realize the extension of the valid period of the operation license of the units, and the safety argumentation work is being carried out.
The reactor water environment has obvious weakening effect on the fatigue life of carbon steel, low alloy steel, austenitic stainless steel and nickel-based alloy, the problem of environment-promoted fatigue is not fully considered in the design of an early nuclear power plant, the EAF problem of a typical position listed in a NUREG/CR-6260 report is only evaluated when the nuclear power plant is required to apply for license renewal by the early American nuclear pipe union (NRC), but the NRC calls into question whether the typical position listed in the NUREG/CR-6260 can cover all sensitive positions of the power plant or not in the supplement material applied for the latest limited term of the power plant license and a second-edition GALL report, and requires that the nuclear power plant recalculates all fatigue analysis positions to consider the accumulative use factor after the EAF, and for the fatigue analysis position with the accumulative use factor larger than 1, the accumulative use factor is reduced by optimized calculation by adopting a detailed method and the like so as to meet the specification requirement, or sufficient monitoring means are adopted to ensure the safety in the operation period.
The optimization calculation needs to predict future transient data, the calculation result depends on the reliability of the prediction method, and the optimization calculation method is complex and is not easy to implement. The arrangement monitoring system can monitor the transient of the fatigue analysis position in real time, the data is real and reliable, and the damage of the component caused by EAF can be effectively prevented. However, the fatigue analysis positions of the nuclear power plant are numerous, and the arrangement of monitoring instruments is large in workload and uneconomical, so that all the fatigue analysis positions need to be screened, fatigue sensitive positions capable of enveloping other analysis positions are determined, and finally, only the fatigue sensitive positions need to be monitored.
Disclosure of Invention
In view of this, in order to overcome the defects in the prior art, the present invention aims to provide an EAF sensitive position screening method suitable for an M310 nuclear power plant.
In order to achieve the purpose, the invention adopts the following technical scheme:
an environment-promoted fatigue-sensitive position screening method for an M310 nuclear power unit comprises the following steps:
counting transient state information through the actual operation condition of the M310 nuclear power unit, combing each system of the nuclear power plant, and dividing hot areas which experience the same thermal transient state;
secondly, defining a typical position according to the characteristics of the M310 nuclear power generating unit and considering the severity of the nuclear leakage consequence, the size of a design Cumulative Utilization Factor (CUF) value and the influence of thermal shock transient frequency;
and (III) primarily screening, aiming at each hot zone, each material and each potential EAF sensitive position, if the position is a typical position, the position is a sensitive position, if the position is not a typical position and the maximum temperature of all transients does not exceed 200 ℃, the influence of the EAF is not considered, and if the position is not a typical position and the maximum temperature of the transients does not exceed 200 ℃, an environment correction factor F is calculated en ；
(IV) judging the environment correction factor F obtained by calculation en Less than or equal to a critical correction factor F en-int There is no need to consider the EAF problem (F) en-int Taking 3) as a critical correction Factor according to test determination, otherwise, calculating the fatigue Cumulative use Factor CUF (Cumulative use Factor) after considering the environmental effect according to the Cumulative use Factor CUF (Cumulative use Factor) in the stress design report en ＝CUF×F en /F en-int ；
(V) pressing all potentially sensitive positions of each system, each hot zone and each material into CUF en Sorting the sizes in descending order, and performing primary screening;
and (VI) combining the primarily selected EAF sensitive positions, and determining the sensitive positions which need to be subjected to EAF monitoring finally.
Preferably, the step (one) specifically comprises the following steps:
(1.1) determining an accumulated use factor, material characteristics and a design transient according to a stress design report of a nuclear power plant;
(1.2) dividing the pipes and/or vessels that experience the same transient into one hot zone, structures within the same hot zone experience the same transient during the plant operation phase.
Preferably, the typical positions of the M310 nuclear power plant in the step (two) include: the reactor pressure vessel comprises (1) a reactor pressure vessel shell and a lower seal head, (2) a reactor pressure vessel inlet nozzle and an outlet nozzle, (3) a pressurizer surge pipe close to the safety end of the heat pipe nozzle, (4) a 3-foot upper filling nozzle of a chemical and volume control system, (5) a 3-foot nozzle of a safety injection system, (6) a 10-foot liquid storage nozzle of the safety injection system, and (7) a 12-foot nozzle of a waste heat discharge system.
Preferably, the step (iii) specifically includes the steps of:
(3.1) judging whether the potential EAF sensitive position is a typical position, if so, judging that the potential EAF sensitive position is a sensitive position, and if not, entering the step (3.2);
(3.2) judging whether the transient maximum temperature of the position exceeds 200 ℃, if not exceeding 200 ℃, not considering the EAF problem, and if exceeding 200 ℃, entering the step (3.3);
(3.3) calculating an environmental correction factor F according to the material and transient information of the position en 。
Preferably, the environmental correction factor F in step (III) en Is calculated as follows:
for Carbon Steel (CS) and Low Alloy Steel (LAS):
for austenitic Stainless Steels (SS) and nickel-based alloys (Ni-Cr-Fe):
in the above formula, S * For the sulfur content of conversion, T * To the temperature of the conversion, O * In order to obtain the oxygen content of the conversion,
is the strain rate of conversion.
For M310 nuclear power unit, for CS, F can be taken conservatively en Is 1.74; LAS may be conservative to take F en Is 2.46; SS may be conservatively taken from F en Is 10.89; ni-Cr-Fe can be conservative to take F en Was 3.67.
Preferably, the step (v) is specifically as follows: for each system, compute the CUF for each thermal zone, each material, each potential EAF sensitive location en And pressCUF en Sorting all sensitive positions in descending order of size, and sorting the first three CUFs en max 、CUF en max-1 、CUF en max-2 And comparing and primarily screening EAF sensitive positions.
Preferably, the step (vi) specifically includes: combining the initially selected EAF sensitive positions according to the following criteria, and determining the sensitive positions which need to be subjected to EAF monitoring finally:
(6.1) different hotspots in the same system, if there are CUF and F in the sensitive location of hotspot A en Are all larger than the hot area B, and the CUF of the sensitive position of the hot area A en,A >2×CUF en,B Then only the sensitive location of hot zone a may be monitored;
(6.2) same system, same hot zone, if CUF and F of material A en Both larger than material B and CUF of material A en,A >2×CUF en,B Then only the sensitive location of material a may be monitored;
(6.3) not allowing to cull or merge representative locations.
Compared with the prior art, the invention has the advantages that: according to the method for screening the environment-promoted fatigue sensitive position suitable for the M310 nuclear power unit, the fatigue sensitive position can be determined only according to the calculation result of the simplified fatigue use factor in the stress design report of the nuclear power plant, the EAF typical position of the M310 nuclear power unit is determined, meanwhile, the position needing to consider the EAF problem can be greatly reduced by introducing the temperature and the Fen-int judgment condition, and the workload of screening and combining the subsequent fatigue sensitive positions is reduced. In addition, the method can realize the screening of the EAF sensitive positions of the nuclear power plant through the steps from one to six, greatly save the cost of arranging monitoring instruments of the nuclear power plant, ensure the safe operation of the nuclear power plant, fill the blank of the screening of the EAF sensitive positions of the nuclear power plant, and bring great convenience for the nuclear power plant owners and research units to carry out subsequent EAF assessment and long-life operation work of the nuclear power plant.
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In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the description of the embodiments will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without creative efforts.
FIG. 1 is an analysis flow chart of a screening method of an environment-promoted fatigue-sensitive location suitable for an M310 nuclear power unit in an embodiment of the present invention;
fig. 2 is a schematic diagram of hot zone classification in a screening process of an EAF sensitive location according to an embodiment of the present invention.
Detailed Description
In order to make those skilled in the art better understand the technical solutions of the present invention, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
In the method for screening the environment-promoted Fatigue (EAF) sensitive position suitable for the M310 nuclear power unit in the embodiment, the Fatigue sensitive position can be determined only according to the calculation result of the simplified Fatigue use factor in the stress design report of the nuclear power plant, and meanwhile, the temperature and the critical correction factor (F) are introduced en-int According to the test, the method determines that the position needing to consider the EAF problem can be greatly reduced by taking the judgment condition 3), the workload of screening and combining subsequent fatigue sensitive positions is reduced, and the method specifically comprises the following steps:
as shown in fig. 1, the method for screening the EAF sensitive position applicable to the M310 nuclear power plant of the embodiment includes the following steps:
and (I) counting transient state information through the actual operation condition of the M310 nuclear power unit, combing each system of the nuclear power plant, and dividing hot areas experiencing the same thermal transient state. The method comprises the following specific steps:
(1.1) determining an accumulated use factor, material characteristics and a design transient according to a stress design report of a nuclear power plant;
(1.2) dividing the pipes and/or vessels that experience the same transient into one hot zone, structures within the same hot zone experiencing the same transient during the plant's operational phase.
And (II) defining a typical position according to the characteristics of the M310 nuclear power generating unit and considering the severity of the nuclear leakage consequence, the CUF value of the design accumulated use factor and the influence of the thermal shock transient frequency. The typical positions for the M310 nuclear power unit comprise: the reactor pressure vessel comprises (1) a reactor pressure vessel shell and a lower seal head, (2) a reactor pressure vessel inlet nozzle and an outlet nozzle, (3) a pressurizer surge pipe close to the safety end of the heat pipe nozzle, (4) a 3-foot upper filling nozzle of a chemical and volume control system, (5) a 3-foot nozzle of a safety injection system, (6) a 10-foot liquid storage nozzle of the safety injection system, and (7) a 12-foot nozzle of a waste heat discharge system.
And (III) primarily screening, aiming at each hot zone, each material and each potential EAF sensitive position, if the position is a typical position, the position is a sensitive position, if the position is not a typical position and the highest temperature of all transients does not exceed 200 ℃, the influence of the EAF is not considered, and if the position is not a typical position and the highest temperature of the transients does not exceed 200 ℃, an environment correction factor F is calculated en . The method comprises the following specific steps:
(3.1) judging whether the potential EAF sensitive position is a typical position, if so, judging that the potential EAF sensitive position is a sensitive position, and if not, entering the step (3.2);
(3.2) judging whether the transient maximum temperature of the position exceeds 200 ℃, if not, not considering the EAF problem, and if so, entering the step (3.3);
(3.3) calculating an environmental correction factor F according to the material and transient information of the position en 。
(IV) judging the environment correction factor F obtained by calculation en Less than or equal to a critical correction factor F en-int There is no need to consider the EAF problem (F) en-int Taking 3) as a critical correction factor according to test determination, or calculating the fatigue cumulative use factor CUF after considering the environmental effect according to the cumulative use factor CUF in the stress design report en ＝CUF×F en /F en-int 。
For Carbon Steel (CS) and Low Alloy Steel (LAS):
for austenitic Stainless Steels (SS) and nickel-based alloys (Ni-Cr-Fe):
in the above formula, S * For the sulfur content converted, T * To the temperature of the conversion, O * In order to obtain the oxygen content of the conversion,
is the strain rate of the conversion.
F can be taken conservatively for M310 nuclear power unit and CS en Is 1.74; LAS may conservatively take F en Is 2.46; SS may be conservatively taken from F en Is 10.89; ni-Cr-Fe can be conservative to take F en Was 3.67.
(V) calculating the CUF of each hot zone, each material and each potential EAF sensitive position aiming at each system en And press against CUF en Sorting all sensitive positions in descending order of size, and sorting the first three CUFs en max 、CUF en max-1 、CUF en max-2 For comparison, EAF sensitive sites were screened initially as shown in fig. 1.
And (VI) merging the initially selected EAF sensitive positions according to the following criteria to determine the sensitive positions which are finally required to be subjected to EAF monitoring:
(6.1) in the same system, different hot zones, if CUF and F in the sensitive position of hot zone A en Are all larger than the hot area B, and the CUF of the sensitive position of the hot area A en,A >2×CUF en,B Then only the sensitive location of hot zone a may be monitored;
(6.2) same system, same hot zone, if CUF and F of material A en Both larger than material B and CUF of material A en,A >2×CUF en,B Then only the sensitive location of material a may be monitored;
(6.3) not allowing to cull or merge representative locations.
The method for screening EAF sensitive positions of M310 nuclear power units by taking a Reactor Pressure Vessel (RPV) system of a certain nuclear power plant as an example comprises the following steps:
the method comprises the following steps of (I) combing an RPV system through the statistics of transient state information of actual operation conditions of a nuclear power plant, and dividing the system into an RPV inlet nozzle, an RPV outlet nozzle, an RPV upper end enclosure and an RPV lower end enclosure, as shown in figure 2. In FIG. 2, the flanges and stubs of the reactor head closure are flanges and bolts of the reactor head, the closure head web pipe is a head exhaust pipe, the control rod mechanism housing is a control rod mechanism housing, the lifting lug is a lifting lug, the upper flange is an upper flange, the inlet nozzle is an inlet nozzle, the outlet nozzle is an inlet nozzle, the core shell core is a reactor core barrel, the core support pad is a reactor core support, the lower head is a lower head, the insulation tubes are instrumentation tubes, and the analyzed areas in the pressure report are analysis areas.
(II) defining typical positions, including: (1) A reactor pressure vessel shell and a lower seal head, and (2) a reactor pressure vessel inlet nozzle and a reactor pressure vessel outlet nozzle.
And (III) primarily screening, listing potential sensitive positions, judging whether the positions are typical positions, if not, judging whether the highest temperature of the transient state exceeds 200 ℃, and if so, calculating an environment correction factor F en . The maximum temperature of the transient state in this case exceeds 200 ℃.
If F en ≤F en-int The EAF problem does not need to be considered, otherwise, the fatigue cumulative use factor CUF after the environmental effect is considered is calculated en ＝CUF×F en /F en-int . F of this case en The results of the calculations are shown in Table 1.
(V) pressing each potentially sensitive position of each system, each hot zone and each material into CUF en The sizes are arranged in descending order and the preliminary screening is carried out.
And (VI) combining the primarily selected EAF sensitive positions, and determining the sensitive positions which need to be subjected to EAF monitoring finally. The results of the RPV system EAF sensitive location screening are shown in table 1.
TABLE 1 screening Process parameters and results for EAF sensitive locations of RPV System
According to the method for screening the environment-promoted fatigue sensitive position suitable for the M310 nuclear power unit, the fatigue sensitive position can be determined only according to the calculation result of the simplified fatigue use factor in the stress design report of the nuclear power plant, seven EAF typical positions of the M310 nuclear power unit are determined, meanwhile, the positions needing to consider EAF problems can be greatly reduced by introducing temperature and Fen-int judgment conditions, and the workload of screening and combining subsequent fatigue sensitive positions is reduced. In addition, the method can realize the screening of the EAF sensitive positions of the nuclear power plant through the steps from one to six, greatly save the cost of arranging monitoring instruments of the nuclear power plant, ensure the safe operation of the nuclear power plant, fill the blank of the screening of the EAF sensitive positions of the nuclear power plant, and bring great convenience for the nuclear power plant owners and research units to carry out subsequent EAF assessment and long-life operation work of the nuclear power plant.
The above-mentioned embodiments are provided only for illustrating the technical idea and features of the present invention, and the purpose thereof is to enable those skilled in the art to understand the content of the present invention and to implement the present invention, and not to limit the protection scope of the present invention by this, and all equivalent changes or modifications made according to the spirit of the present invention should be covered in the protection scope of the present invention.
Claims (4)
1. A screening method of an environment-promoted fatigue sensitive position suitable for an M310 nuclear power unit is characterized by comprising the following steps: the method comprises the following steps:
counting transient state information through the actual operation condition of the M310 nuclear power unit, combing each system of the nuclear power plant, and dividing hot areas experiencing the same thermal transient state;
secondly, defining a typical position according to the characteristics of the M310 nuclear power unit and considering the severity of the nuclear leakage consequence, the CUF value of the design accumulated use factor and the influence of the thermal shock transient frequency;
and (III) primarily screening, aiming at each hot area, each material and each potential environment fatigue promotion EAF sensitive position, if the position is a typical position, the position is a sensitive position, if the position is an atypical position, the influence of the environment fatigue promotion EAF is not considered if the highest temperature of all transients does not exceed 200 ℃, and if the position is an atypical position, the highest temperature of the transients exceeds 200 ℃, an environment correction factor F is calculated en ；
(IV) if the calculated environment correction factor F is obtained en Less than or equal to the critical correction factor F en-int The problem of environment-promoted fatigue (EAF) is not required to be considered, otherwise, the CUF is calculated according to the CUF in the stress design report, and the CUF is calculated after the environmental effect is considered en ＝CUF×F en /F en-int ；
(V) pressing each potentially sensitive position of each system, each hot zone and each material into CUF en Sorting in descending order and carrying out preliminary screening;
sixthly, combining the primarily selected environment fatigue-promoting EAF sensitive positions, and determining the sensitive positions which need to be subjected to environment fatigue-promoting EAF monitoring finally;
the step (III) specifically comprises the following steps:
(3.1) judging whether the EAF sensitive position is a typical position or not, if so, judging the EAF sensitive position is a sensitive position, and if not, entering the step (3.2);
(3.2) judging whether the transient maximum temperature of the position exceeds 200 ℃, if not exceeding 200 ℃, not considering the problem of environmental promotion fatigue (EAF), and if exceeding 200 ℃, entering the step (3.3);
(3.3) calculating an environmental correction factor F according to the material and transient information of the position en ；
The environmental correction factor F in the step (III) en Is calculated as follows:
for carbon steel and low alloy steel:
for austenitic stainless steels and nickel-based alloys:
in the above formula, S * For the sulfur content of conversion, T * Temperature of conversion, O * In order to obtain the oxygen content of the conversion,
strain rate for conversion;
the step (V) is as follows: for each system, compute the CUF for each thermal zone, each material, each potential environment promotes fatigue EAF sensitive location en And press against CUF en Sorting all the sensitive positions in descending order of size, and sorting the first three CUFs enmax 、CUF enmax-1 、CUF enmax-2 And comparing, and primarily screening the EAF sensitive positions where the environment promotes fatigue.
2. The method for screening the environment-promoted fatigue-sensitive position suitable for the M310 nuclear power generating unit according to claim 1, characterized in that: the step (I) comprises the following steps:
(1.1) determining an accumulated use factor, material characteristics and a design transient state according to a stress design report of a nuclear power plant;
(1.2) dividing the pipes and/or vessels that experience the same transient into one hot zone, structures within the same hot zone experiencing the same transient during the plant's operational phase.
3. The method for screening the environment-promoted fatigue-sensitive position suitable for the M310 nuclear power unit as claimed in claim 1, wherein: the typical positions of the M310 nuclear power unit in the step (II) comprise: reactor pressure vessel shell and low head, reactor pressure vessel inlet nozzle and outlet nozzle, manostat surge tube near the heat pipe nozzle safety end, chemical and volume control system 3 feet upper fill nozzle, safety injection system 3 feet nozzle, safety injection system 10 feet accumulator nozzle, residual heat removal system 12 feet nozzle.
4. The method for screening the environment-promoted fatigue-sensitive position suitable for the M310 nuclear power generating unit according to claim 1, characterized in that: the step (VI) specifically comprises the following steps: combining the initially selected environment-promoted fatigue EAF sensitive positions according to the following criteria, and determining the sensitive positions which need environment-promoted fatigue EAF monitoring finally:
(6.1) different hotspots in the same system, if there are CUF and F in the sensitive location of hotspot A en Are all larger than the hot area B, and the CUF of the sensitive position of the hot area A en,A >2×CUF en,B Then only the sensitive location of hot zone a is monitored;
(6.2) same system, same hot zone, if CUF and F of material A en Both larger than material B and CUF of material A en,A >2×CUF en,B Only the sensitive location of material a is monitored.
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