CN116415414A - Pressurized water reactor water loss accident data applicability evaluation method, system, equipment and terminal - Google Patents
Pressurized water reactor water loss accident data applicability evaluation method, system, equipment and terminal Download PDFInfo
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Abstract
The invention belongs to the technical field of light water reactor proportion modeling and data applicability evaluation, and discloses a pressurized water reactor water loss accident data applicability evaluation method, system, equipment and terminal, which are used for carrying out important phenomenon analysis of accident process and forming Pi groups by using dimensionless analysis; selecting experimental data, and performing stage division and corresponding point data extraction; selecting applicability evaluation object simulation data, and performing stage division and corresponding point data extraction; and carrying the extracted corresponding point data and the divided stages into Pi groups of each stage to calculate, so as to realize the applicability evaluation of the pressurized water reactor water loss accident data. According to the invention, based on a dimensionless analysis method, by utilizing experimental data of the existing test bench, specific applicability suggestions are given according to whether the dimensionless number meets the condition of a judgment standard, and specific partial phenomena which are not applicable are identified while available data are extracted, so that the economical efficiency of building the whole effect test bench and the separation effect test bench is greatly improved.
Description
Technical Field
The invention belongs to the technical field of light water reactor proportion modeling and data applicability evaluation, and particularly relates to a pressurized water reactor water loss accident data applicability evaluation method, system, equipment and terminal.
Background
At present, in the process of designing and building a nuclear reactor, a great deal of experiments and simulation work are required before a new reactor type is built. Proportional analysis of prototype stacks and targeted establishment of the whole effect test (IET) and the Separation Effect Test (SET) are important links. For example, to build a third generation reactor AP600 from West House corporation, several whole effect benches are built around the world: APEX (the Advanced Plant Experiment, advanced stack experiment) of state university (OSU) of oregon, LSTF (Large Scale Test Facility, large scale test facility, also known as ROSA-AP 600) of japan atomic energy institute (JAERI), SPES-2 (Simulatore per Esperienze di Sicurezza-2, security simulator 2) of italian national electric company (ENEL). While the final AP600 is not built in large numbers for use, experimental data is not fully utilized. In order to fully utilize the existing data and provide data support for building and improving the three-generation-plus-reactor in China as much as possible, and respond to the existing experimental data identified in the computer software development and application guidance for safety analysis of the nuclear power plant, which is proposed in section 3.4.4, a new experiment is developed, and the requirement of a database is completed, a method is required to be provided to evaluate the applicability of each bench experimental data to other primary-size reactors.
Through the above analysis, the problems and defects existing in the prior art are as follows: existing thermodynamic and hydraulic benches are generally based on a particular reactor design, and can only reproduce a particular accident condition or conditions on that particular reactor. However, the gantry is generally expensive to construct, has a small usable range, and cannot be applied to non-prototype stacks. The data of the whole effect test bed of the nuclear reactor at present cannot be fully utilized.
Disclosure of Invention
Aiming at the problems existing in the prior art, the invention provides a pressurized water reactor water loss accident data applicability evaluation method, a system, equipment and a terminal, and particularly relates to a pressurized water reactor small break water loss accident overall effect experimental data applicability evaluation method, a system, a medium, equipment and a terminal based on dimensionless number analysis.
The invention is realized in such a way that the pressurized water reactor water loss accident data applicability evaluation method comprises the following steps: carrying out important phenomenon analysis of accident process, and forming Pi groups by using dimensionless analysis; selecting experimental data, and performing stage division and corresponding point data extraction; selecting applicability evaluation object simulation data, and performing stage division and corresponding point data extraction; and carrying the extracted corresponding point data and the divided stages into each stage Pi group for calculation, so as to realize the applicability evaluation of the accident data.
Further, the pressurized water reactor water loss accident data applicability evaluation method comprises the following steps:
analyzing important phenomena of each stage of the small break accident process, and determining important phenomena corresponding to the phenomenon identification and ordering list;
step two, carrying out dimensionless analysis from top to bottom and from bottom to top to form a dimensionless Pi group comprising single-phase two-phase watershed, and determining important parameters to be selected;
selecting small break experimental data to be subjected to applicability analysis, dividing the accident process into 5 stages of spraying, natural circulation, water seal cleaning, water evaporation and long-term cooling according to an accident sequence, and accurately identifying time points of stage division;
selecting a small-break modeling model corresponding to the model, performing accident simulation, dividing the accident process into 5 identical stages according to an accident sequence, and accurately identifying stage division time points of the model;
step five, data are brought into the Pi groups corresponding to each stage to be calculated, and the obtained two groups of dimensionless parameters are compared; if meeting criterion 0.5 is less than or equal to pi R And if the dimensionless number ratio is less than or equal to 2 and accords with the usable range, the phenomena are considered to be similar, and the selected experimental data are suitable for the target model.
Further, the phenomenon recognition and ranking table in step one corresponds to a selected global effect test bench, a target prototype stack or a target bench, and the selected important phenomenon is guaranteed to be recognized as high H between the two.
In the second step, top-down analysis is carried out, a dimensionless Pi group of a single-phase two-phase basin is obtained, and a pressure drop equation is obtained according to mass, momentum and energy conservation equations; after dimensionless, according to the physical meaning of each term: the pressure change caused by the specific energy and specific volume change caused by mass inflow, mass outflow and heat transfer is obtained to obtain a dimensionless Pi group.
Further, the step three and the step four are divided according to the following steps:
(1) And (3) spraying: the starting point is identified as the opening of the breach. During most of the spraying phase, the RCS remains almost in a single-phase liquid state; when the stage is finished, the upper sealing head, the upper chamber and the hot section start to be separated; in the spraying stage, the opening fluid is single-phase liquid, and the ending point is identified as the opening and two-phase spraying occurs.
(2) Natural circulation and water seal formation stage: typically characterized by a plateau in the pressure of the primary circuit. At the end of the blow-out phase, the RCS pressure reaches quasi-equilibrium for hundreds of seconds, with the liquid in one circuit allowing a significant natural circulation two-phase flow around the circuit. The RCS continues to consume a large amount of cooling liquid, and steam generated in the reactor core is blocked in the upper area of the SG by liquid in the loop to form a water seal; the liquid plug is a U-shaped section in the cold leg between the steam generator outlet plenum and the reactor coolant pump inlet. The coolant with low mass flow still flows out at the break. After the water seal is formed, the flow rate of the transition section of the primary pump of the primary circuit is 0; when the cleaning starts, the flow rises rapidly, and the criterion of the ending time point is that the steam flow of the transition section rises rapidly and the liquid level of the transition section falls rapidly.
(3) And (3) a water seal cleaning stage: the water seal cleaning phenomenon occurs in a transition section U-shaped pipe from an SG outlet pipe of a traditional pressurized water reactor to an inlet of a main pump. The formation of the water seal results in the interruption of natural circulation, when the reactor core liquid level is reduced to a certain extent, and when the pressure difference between the reactor descending section and the reactor core is increased enough to overcome the resistance caused by the water seal, the water seal in the transition section is cleared, obvious steam flow occurs in the transition section, the reactor core liquid level is quickly risen, and the end time point criterion is that = the transition section steam flow reaches a stable value inflection point and the transition section liquid level is reduced to a low value inflection point.
(4) Water evaporation stage: the liquid level of the pressure vessel mixture continues to decrease after the loop seal is cleared due to evaporation of the remaining core water charge. Before the RCS is depressurized to a break flow rate lower than the safe injection flow rate, the primary circuit water content reaches a minimum value, and the reactor core is exposed in some cases, and the criterion of the ending time point is that the safe injection flow rate is equal to the break flow rate.
(5) And (3) a reactor core re-submerging stage: when the safety injection flow is larger than the break flow, the submerged stage starts, the whole water content of the first loop is raised, the continuous cooling of the reactor core is ensured, and the safety is ensured.
Further, the data required in the third and fourth steps include: the reactor comprises 80 groups of data including a reactor core heating section, an upper end enclosure, an upper chamber, a hot pipe section, an SG ascending section, an SG descending section, a transition section, a cold pipe section, a reactor core descending section, water content of a lower chamber, pressure, gas phase temperature, liquid phase temperature, average density, liquid level, vertical height, mass flow rate at a break, pressure, gas phase temperature, liquid phase temperature and density, reactor core decay heat, reactor core inlet nozzle flow rate, reactor core inlet density and reactor core inlet and outlet pressure.
Further, the dimensionless criterion numbers involved in the third and fourth steps include:
Further, the time points involved in the third and fourth steps are selected as the initial time of each stage, namely, 4 time points, and 80 groups of data are required to be extracted from each time point to form a data table.
In the fifth step, 80 groups of data of the 4 time points of the experimental data and the target reactor model operation data are brought into the dimensionless criterion number according to the stage and the requirement, and the dimensionless criterion number calculation results of the experimental data and the target reactor model operation data are compared.
Further, in step five, n R ＝Π Test /Π Object If the dimensionless number ratio accords with the usable range of 0.5 to be equal to or less than pi R If the temperature is less than or equal to 2, the phenomena are considered to be similar, and the data on the selected rack is used for verifying the target reactor; if the dimensionless number ratio exceeds the available range, the phenomenon similarity is deficient, the same type of working condition data on the selected rack cannot be used for verifying the target pile type and the rack, the separation effect experimental phenomenon to be analyzed is identified, and the SET is established for the phenomenon which is not met.
Another object of the present invention is to provide a pressurized water reactor water loss accident data applicability evaluation system applying the pressurized water reactor water loss accident data applicability evaluation method, the pressurized water reactor water loss accident data applicability evaluation system comprising:
the important phenomenon analysis module is used for analyzing important phenomena of each stage of the small break accident process and determining important phenomena corresponding to the phenomenon identification and ranking table;
the dimensionless analysis module is used for carrying out dimensionless analysis from top to bottom and from bottom to top to form a dimensionless Pi group comprising single-phase two-phase watershed, and determining important parameters to be selected;
the stage division module is used for selecting small break experimental data to be subjected to applicability analysis, dividing the accident process into 5 stages according to an accident sequence, and accurately identifying time points of stage division;
the accident simulation module is used for selecting a small break modeling model of a corresponding model to perform accident simulation, dividing the accident process into 5 stages according to an accident sequence, and accurately identifying the stage division time points of the model;
the data applicability evaluation module is used for bringing data into the Pi group calculation of each corresponding stage, comparing the two obtained dimensionless parameters, and obtaining a data applicability conclusion according to a criterion.
Another object of the present invention is to provide a computer device, including a memory and a processor, where the memory stores a computer program, and the computer program when executed by the processor causes the processor to execute the steps of the method for evaluating the applicability of water loss accident data of a pressurized water reactor.
Another object of the present invention is to provide a computer readable storage medium storing a computer program which, when executed by a processor, causes the processor to execute the steps of the pressurized water reactor water loss accident data applicability evaluation method.
The invention further aims at providing an information data processing terminal which is used for realizing the pressurized water reactor water loss accident data applicability evaluation system.
In combination with the technical scheme and the technical problems to be solved, the technical scheme to be protected has the following advantages and positive effects:
first, aiming at the technical problems in the prior art and the difficulty of solving the problems, the technical problems solved by the technical proposal of the invention are analyzed in detail and deeply by tightly combining the technical proposal to be protected, the results and data in the research and development process, and the like, and some technical effects brought after the problems are solved have creative technical effects. The specific description is as follows:
aiming at the problem that the data of the conventional nuclear reactor integral effect test bed is not fully utilized, the integral effect experimental data applicability evaluation method for the pressurized water reactor small-break water loss accident is based on a dimensionless analysis method, and based on the experimental data of the conventional test bed, specific applicability suggestions are given according to the condition whether dimensionless numbers meet the judgment standard or not, and the construction economy of the integral effect test bed and the separation effect test bed is greatly improved while the available data are extracted.
Useful gains of the invention are: if the dimensionless number ratio accords with the available range, the phenomenon is considered to be similar, experimental data can be used for verifying the target model, a large number of repeated experiments can be avoided to a certain extent, and the expense is saved; if the dimensionless number ratio exceeds the available range, the phenomenon is dissimilar, experimental data cannot be used for verifying the target model, and a corresponding separation effect experiment is required to be carried out on the phenomenon which is not met.
Secondly, the technical scheme is regarded as a whole or from the perspective of products, and the technical scheme to be protected has the following technical effects and advantages:
the invention provides a method for evaluating the applicability of whole effect experimental data of a small water loss accident of a pressurized water reactor, which fully excavates and utilizes the running data of an existing whole effect test bed, performs proportional analysis on the running condition of the small water loss accident, substitutes various data into important dimensionless criterion numbers for comparison after obtaining the important dimensionless criterion numbers, has universality, and can be realized by only re-deriving equations and modifying dimensionless numbers when the selected working condition is other working conditions of other reactors.
Simulation experiment results show that the data applicability evaluation results provided by the invention effectively give the applicability index, and meanwhile, the inapplicable phenomenon or parameter is identified, so that the method is beneficial to guiding the transformation of the rack or the construction of a new rack and improving the economy.
Thirdly, as inventive supplementary evidence of the claims of the present invention, the following important aspects are also presented:
the expected benefits and commercial values after the technical scheme of the invention is converted are as follows:
the construction of a new thermal hydraulic overall effect test bed generally needs billions of funds, the implementation of the method can fully utilize the existing experimental data, the applicability of the data is judged by using a dimensionless array, and if the judgment data is applicable, excessive repeated experiments are avoided to a certain extent, so that a large amount of funds are saved; if the specific position data is judged to be inapplicable, the original test bench can be pertinently modified or the separation effect test bench can be independently built, so that the fund can be saved to a certain extent, and the economical efficiency can be improved.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings that are needed in the embodiments of the present invention will be briefly described below, and it is obvious that the drawings described below are only some embodiments of the present invention, and other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a flow chart of a pressurized water reactor water loss accident data applicability evaluation method provided by an embodiment of the invention;
FIG. 2 is a schematic diagram of a pressurized water reactor water loss accident data applicability evaluation method provided by an embodiment of the invention;
FIG. 3 is a flow chart for judging the applicability of the pressurized water reactor water loss accident data provided by the embodiment of the invention;
FIG. 4 is a schematic diagram of the division of components of an exemplary pressurized water reactor system according to an embodiment of the present invention;
FIG. 5 is a schematic diagram of the process stage division and the marked division of the small water loss accident of the reactor according to the embodiment of the invention;
fig. 6A is a graph of a time point determination for a small breach water loss accident during a blowout phase according to an embodiment of the present invention;
FIG. 6B is a graph of a time point determination for a natural circulation phase of a small-break loss of water accident provided by an embodiment of the present invention;
FIG. 6C is a graph showing a determination of a time point of a water seal clearing stage of a small water loss accident according to an embodiment of the present invention;
fig. 6D is a graph of a time point determination of a small water loss event water evaporation stage according to an embodiment of the present invention.
Detailed Description
The present invention will be described in further detail with reference to the following examples in order to make the objects, technical solutions and advantages of the present invention more apparent. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the invention.
Aiming at the problems existing in the prior art, the invention provides a pressurized water reactor water loss accident data applicability evaluation method, a system, equipment and a terminal, and the invention is described in detail below with reference to the accompanying drawings.
In order to fully understand how the invention may be embodied by those skilled in the art, this section is an illustrative embodiment in which the claims are presented for purposes of illustration.
As shown in fig. 1, the method for evaluating the applicability of the pressurized water reactor water loss accident data provided by the embodiment of the invention comprises the following steps:
s101, analyzing important phenomena of accident process, and forming Pi groups by using dimensionless analysis;
s102, selecting experimental data, dividing the stages and extracting corresponding point data;
s103, selecting adaptability evaluation object simulation data, and carrying out stage division and corresponding point data extraction;
s104, carrying the extracted corresponding point data and the divided stages into each stage Pi group to calculate, and realizing the suitability evaluation of the pressurized water reactor water loss accident data.
As a preferred embodiment, as shown in fig. 2, the method for evaluating the applicability of the pressurized water reactor water loss accident data provided by the embodiment of the invention specifically includes the following steps:
s1, analyzing important phenomena of each stage of the small break accident process, and determining important phenomena corresponding to the phenomenon identification and ordering list;
s2, carrying out top-down and bottom-up dimensionless analysis to form a dimensionless Pi group comprising single-phase and two-phase watershed, and determining important parameters to be selected;
s3, small break experimental data to be subjected to applicability analysis are selected, the accident process is divided into 5 stages of spraying, natural circulation, water seal removal, water evaporation and long-term cooling according to an accident sequence, and time points of stage division are accurately identified;
s4, selecting a small break modeling model corresponding to the target reactor, performing accident simulation, dividing the accident process into 5 identical stages according to an accident sequence, and accurately identifying stage division time points of the model;
s5, carrying the data into corresponding Pi groups of each stage to calculate, comparing the obtained two groups of dimensionless parameters, and if the criterion is met, namely, pi is not more than 0.5 R And if the dimensionless number ratio is less than or equal to 2 and accords with the usable range, the phenomena are considered to be similar, and the selected experimental data can be suitable for the target model.
The phenomenon recognition and sorting table in step S1 provided in the embodiment of the present invention needs to correspond to the selected overall effect test stand, the target prototype stack or the target stand. That is, the selected important phenomenon needs to be ensured to be identified as H (high) between the two.
In the step S2 provided by the embodiment of the present invention, top-down proportional analysis is performed, a dimensionless Pi group of a single-phase two-phase basin is derived according to mass, momentum and energy conservation equations to obtain a pressure drop equation, and after dimensionless analysis, according to the physical meaning of each term: the pressure change caused by the specific energy and specific volume change caused by mass inflow, mass outflow and heat transfer is obtained to obtain a dimensionless Pi group.
In steps S3 and S4 provided in the embodiment of the present invention, the basis for stage division and time point selection is respectively:
(1) And (3) spraying: the starting point is identified as "breach open". The RCS remains almost in a single phase liquid state for most of the spraying phase, at the end of which phase separation of the upper head, upper chamber and hot leg begins to occur. In the spraying phase, the breach fluid is a single-phase liquid, so its end point is identified as "two-phase spraying of the breach".
(2) Natural circulation and water seal formation stage: a typical feature of this stage is that the pressure of the primary circuit is plateau. At the end of the blow-off phase, the RCS pressure reaches a quasi-equilibrium state, possibly lasting hundreds of seconds, with enough liquid in one circuit to allow a significant natural circulation two-phase flow around the circuit. The RCS continues to consume a significant amount of coolant, and the steam generated in the core is blocked in the upper region of the SG by a "liquid plug" in the loop (a U-shaped portion in the cold leg between the steam generator outlet plenum and the reactor coolant pump inlet), forming a water seal. The break still has a low mass flow of coolant out. After the water seal is formed, the flow rate of the transition section of the primary pump of the loop is 0, and the flow rate can be quickly increased when the cleaning starts, so that the criterion of the ending time point is that the steam flow rate of the transition section is quickly increased and the liquid level of the transition section is quickly reduced.
(3) And (3) a water seal cleaning stage: the water seal cleaning phenomenon occurs in a transition section U-shaped pipe from an SG outlet pipe of a traditional pressurized water reactor to an inlet of a main pump. The formation of a water seal can cause the natural circulation to break. When the liquid level of the reactor core is reduced to a certain degree, the pressure difference between the reactor descending section and the reactor core is increased enough to overcome the resistance caused by water seal, the water seal in the transition section can be cleared, obvious steam flow occurs in the transition section, and the liquid level of the reactor core can also be quickly raised. The end time point criterion is 'transition section steam flow reaches a stable value inflection point' and 'transition section liquid level falls to a low value inflection point'.
(4) Water evaporation stage: the liquid level of the pressure vessel mixture continues to decrease after the loop seal is cleared due to evaporation of the remaining core water charge. The primary water charge will be at a minimum before the RCS is depressurized to a point where the breach flow becomes lower than the safe injection flow, in some cases resulting in bare core. The end time criterion is therefore "safe injection flow equals break flow".
(5) And (3) a reactor core re-submerging stage: when the safety injection flow is larger than the break flow, the submerged stage starts, namely the whole water content of the primary loop is raised, so that the continuous cooling of the reactor core can be ensured, and the safety is ensured.
In steps S3 and S4 provided in the embodiment of the present invention, the required data includes: the reactor comprises 80 groups of data including a reactor core heating section, an upper end enclosure, an upper chamber, a hot pipe section, an SG ascending section, an SG descending section, a transition section, a cold pipe section, a reactor core descending section, water content of a lower chamber, pressure, gas phase temperature, liquid phase temperature, average density, liquid level, vertical height, mass flow rate at a break, pressure, gas phase temperature, liquid phase temperature and density, reactor core decay heat, reactor core inlet nozzle flow rate, reactor core inlet density and reactor core inlet and outlet pressure.
In steps S3 and S4 provided in the embodiment of the present invention, the number of dimensionless criteria involved is shown in table 1.
Table 1 dimensionless criterion number
In the steps S3 and S4 provided in the embodiment of the present invention, the time points involved are selected as the initial time of each stage, that is, 4 time points in total, and 80 sets of data are extracted at each time point to form a data table.
In step S5 provided in the embodiment of the present invention, 80 sets of data at 4 time points of the experimental data and the target reactor model operation data are brought into the dimensionless criterion number according to the stage and the requirement, and the dimensionless criterion number calculation results of the experimental data and the target reactor model operation data are compared.
In step S5 provided by the embodiment of the present invention, pi R ＝Π Test /Π Object If the dimensionless number ratio accords with the usable range (pi is more than or equal to 0.5) R 2), the phenomenon is considered to be similar, the data on the selected rack can be used for verifying the target reactor, a large number of repeated experiments and repeated rack construction can be avoided to a certain extent, and resources are saved; if the dimensionless number ratio exceeds the available range, the phenomenon is lack of similarity, the same type of working condition data on the selected rack cannot be used for verifying the target pile type and the rack, the separation effect experimental phenomenon to be further researched is identified, and the SET is required to be established aiming at the phenomenon which is not consistent with the phenomenon.
The pressurized water reactor water loss accident data applicability evaluation system provided by the embodiment of the invention comprises the following steps:
the important phenomenon analysis module is used for analyzing important phenomena of each stage of the small break accident process and determining important phenomena corresponding to the phenomenon identification and ranking table;
the dimensionless analysis module is used for carrying out dimensionless analysis from top to bottom and from bottom to top to form a dimensionless Pi group comprising single-phase two-phase watershed, and determining important parameters to be selected;
the stage division module is used for selecting small break experimental data to be subjected to applicability analysis, dividing the accident process into 5 stages according to an accident sequence, and accurately identifying time points of stage division;
the accident simulation module is used for selecting a small break modeling model of a corresponding model to perform accident simulation, dividing the accident process into 5 stages according to an accident sequence, and accurately identifying the stage division time points of the model;
the data applicability evaluation module is used for bringing data into the Pi group calculation of each corresponding stage, comparing the two obtained dimensionless parameters, and obtaining a data applicability conclusion according to a criterion.
In order to prove the inventive and technical value of the technical solution of the present invention, this section is an application example on specific products or related technologies of the claim technical solution.
FIG. 4 schematically shows the locations of the components of a typical pressurized water reactor system, which are divided into 5 saturation regions and 5 supercooling regions according to the fluid state in the components after an accident, in the fluid flow direction, in the case of a broken loop, from the core: the reactor comprises a reactor core, an upper cavity, an upper sealing head, a hot pipe section, an SG ascending section, an SG descending section, a transition section, a cold pipe section, a descending section and a lower cavity, wherein the reactor core is composed of 10 parts.
Specifically, the data required by the embodiment of the invention includes: the water content and the mass flow at the break of 10 parts (11 columns of data are stored as M.xls); the pressure of the 10 parts and the pressure at the break (11 columns of data, stored as p.xls); the gas phase temperature and the gas phase temperature at the break of 10 parts (11 columns of data, stored as tg. Xls), the liquid phase temperature and the liquid phase temperature at the break of 10 parts (11 columns of data, stored as tl. Xls), the average density and the density at the break of 10 parts (11 columns of data, stored as rho. Xls), the liquid level of 10 parts (10 columns of data, stored as level. Xls), the vertical height of 10 parts (10 columns of data, stored as l. Xls), and the core decay heat, core inlet take over flow rate, core inlet density, core inlet and outlet pressure (5 columns of data, stored as core. Xls), 80 columns of data are stored in sequence in 8 table files.
As shown in fig. 5, in the embodiment of the present invention, the key point recognition that is performed on the analysis object by time division is respectively: the two-phase jet of break, the liquid level of transition section drop fast, the flow rate of hot pipe section rise fast, the safe injection flow is equal with the break flow.
Specifically, the time points of the phase division provided by the embodiment of the invention need to be judged; the number of rows in each table at a time point is specified after the determination based on the explicit criterion.
Aiming at the analysis object, the embodiment of the invention designs the whole effect experimental data applicability evaluation software of the pressurized water reactor small break loss accident based on dimensionless number analysis, which comprises a data table calling module, a stage characteristic display module and a dimensionless number calculation module.
Specifically, the data table calling module comprises pressure, liquid phase temperature, gas phase temperature, water filling amount/mass flow, characteristic length, average density, reactor core parameters and liquid level parameter calling buttons.
The stage characteristic display module comprises accident types and accident stage options, and four stage characteristics calculated by the small-break water loss accident are displayed after the selection.
The dimensionless number calculation module comprises a line number input, a calculation button and a calculation result display window.
The software also includes unit load, date and time, automatic/manual, historical data and exit buttons.
The embodiment of the invention has a great advantage in the research and development or use process, and has the following description in combination with data, charts and the like of the test process.
The method and the software provided by the invention can realize dimensionless number calculation and evaluate the applicability of experimental data through specific application examples.
Two different integrity test benches A and B for comparing data applicability are taken as small break test conditions, and the time division of each accident stage is as follows: the opening time of the opening A is 0s, the spraying time of the two phases of the opening A is 70s, the spraying stage lasts 70s, the opening time of the opening B is 200s, the spraying time of the two phases of the opening A is 232s, and the spraying stage lasts 32s; the water seal clearing starting time is 475s, the natural circulation stage lasts 405s, the water seal clearing starting time is 575s, and the natural circulation stage lasts 343s; the water seal clearing end time A is 530s, the water seal clearing stage lasts 55s, the water seal clearing end time B is 600s, and the water seal clearing stage is maintainedContinuing for 25s; the time of A safety injection flow is 1865s which is equal to the break flow, the water evaporation stage lasts 1335s, the time of B safety injection flow is 746s which is equal to the break flow, and the water evaporation stage lasts 146s. The dimensionless number calculation method adopts top-down proportional analysis deduction, namely, the mass, energy and momentum conservation equations of the whole system are listed by taking the whole system as a reference, and a loop dimensionless pressure drop equation is deduced to obtain a dimensionless Pi value. The dimensionless Pi value of each stage is calculated by using the method provided by the invention as follows: in the spraying stage, the water loss accident psi of the small crack of the A rack 2 ＝-3.928×10 -1 ，ψ 6 ＝4.624×10 -1 ，ψ 7 ＝-4.345×10 -2 ，ψ 9 ＝1.576×10 -1 Small water loss accident psi of B bench 2 ＝-5.938×10 -1 ，ψ 6 ＝2.444×10 -1 ，ψ 7 ＝-7.194×10 -2 ，ψ 9 ＝2.566×10 -1 ，Π R，2 ＝0.66，Π R，6 ＝1.89，Π R，7 ＝0.60，Π R，9 =0.61; in the natural circulation stage, the small crack of the A rack is dehydrated 5 ＝-1.352，ψ 6 ＝1.576，ψ 8 ＝-7.928×10 -2 ，ψ 9 ＝3.773×10 -1 ，ψ 10 ＝2.002×10 -4 ，ψ 11 =4031.142, b-stage small laceration water loss accident ψ 5 ＝-1.407，ψ 6 ＝8.264×10 -1 ，ψ 8 ＝-9.681×10 -2 ，ψ 9 ＝8.252×10 -1 ，ψ 10 ＝1.9822×10 -3 ，ψ 11 ＝21487.665，Π R，5 ＝0.96，Π R，6 ＝1.91，Π R，8 ＝0.82，Π R，9 ＝0.46，Π R，10 ＝0.10，Π R，11 =0.19; water seal clearing stage, small crack water loss accident psi of A rack 5 ＝-6.792×10 -2 ，ψ 6 ＝1.237×10 -2 ，ψ 8 ＝-3.10810 -3 ，ψ 9 ＝1.717×10 -2 ，ψ 12 ＝1.356，ψ 13 ＝2.618×10 -1 ，ψ 14 ＝4.066×10 -5 ，ψ 15 ＝1.674×10 -2 ，ψ 16 ＝8.964×10 -1 Small water loss accident psi of B bench 5 ＝-9.265×10 -2 ，ψ 6 ＝5.881×10 -3 ，ψ 8 ＝-5.023×10 -3 ，ψ 9 ＝4.235×10 -2 ，ψ 12 ＝1.443，ψ 13 ＝4.381×10 -1 ，ψ 14 ＝7.349×10 -6 ，ψ 15 ＝1.792×10 -2 ，ψ 16 ＝6.878×10 -1 ，Π R，5 ＝0.73，Π R，6 ＝2.10，Π R，8 ＝0.62，Π R，9 ＝0.41，Π R，12 ＝0.94，Π R，13 ＝0.60，Π R，14 ＝5.53，Π R，15 ＝0.93，Π R，16 =1.30; in the water evaporation stage, a small crack of the rack A is dehydrated 5 ＝-4.201，ψ 6 ＝2.415×10 -1 ，ψ 8 ＝-1.797×10 -1 ，ψ 9 =1.186, b-stage small break loss of water accident ψ 5 ＝-6.592×10 -1 ，ψ 6 ＝7.544×10 -2 ，ψ 8 ＝-3.197×10 -2 ，ψ 9 ＝4.638×10 -1 ，Π R，5 ＝6.37，Π R，6 ＝3.20，Π R，8 ＝5.62，Π R，9 =2.56. The conclusion is as follows: the small crack water loss accident working conditions of the A and B benches are in the spraying, natural circulation and water seal cleaning stages, the similarity of data related to crack mass outflow, loop heat transfer and reactor core decay heat is good, and cross verification can be realized. Because the area ratio of the two racks is large, the ratio of the non-dimensional numbers related to the resistance is out of the similarity range; in the water evaporation stage, the data are not completely matched due to the large time progress difference, and further verification is needed.
From the results, the data applicability evaluation result provided by the embodiment of the invention effectively gives the applicability index, and simultaneously identifies the inapplicable phenomenon or parameter, thereby being beneficial to improving the economy.
It should be noted that the embodiments of the present invention can be realized in hardware, software, or a combination of software and hardware. The hardware portion may be implemented using dedicated logic; the software portions may be stored in a memory and executed by a suitable instruction execution system, such as a microprocessor or special purpose design hardware. Those of ordinary skill in the art will appreciate that the apparatus and methods described above may be implemented using computer executable instructions and/or embodied in processor control code, such as provided on a carrier medium such as a magnetic disk, CD or DVD-ROM, a programmable memory such as read only memory (firmware), or a data carrier such as an optical or electronic signal carrier. The device of the present invention and its modules may be implemented by hardware circuitry, such as very large scale integrated circuits or gate arrays, semiconductors such as logic chips, transistors, etc., or programmable hardware devices such as field programmable gate arrays, programmable logic devices, etc., as well as software executed by various types of processors, or by a combination of the above hardware circuitry and software, such as firmware.
The foregoing is merely illustrative of specific embodiments of the present invention, and the scope of the invention is not limited thereto, but any modifications, equivalents, improvements and alternatives falling within the spirit and principles of the present invention will be apparent to those skilled in the art within the scope of the present invention.
Claims (10)
1. The method for evaluating the applicability of the pressurized water reactor water loss accident data is characterized by comprising the following steps of: carrying out important phenomenon analysis of accident process, and forming Pi groups by using dimensionless analysis; selecting experimental data, and performing stage division and corresponding point data extraction; selecting applicability evaluation object simulation data, and performing stage division and corresponding point data extraction; and carrying the extracted corresponding point data and the divided stages into Pi groups of each stage to calculate, so as to realize the applicability evaluation of the pressurized water reactor water loss accident data.
2. The pressurized water reactor water loss accident data applicability evaluation method according to claim 1, characterized in that the pressurized water reactor water loss accident data applicability evaluation method comprises the steps of:
analyzing important phenomena of each stage of the small break accident process, and determining important phenomena corresponding to the phenomenon identification and ordering list;
step two, carrying out dimensionless analysis from top to bottom and from bottom to top to form a dimensionless Pi group comprising single-phase two-phase watershed, and determining important parameters to be selected;
selecting small break experimental data to be subjected to applicability analysis, dividing the accident process into 5 stages of spraying, natural circulation, water seal cleaning, water evaporation and long-term cooling according to an accident sequence, and accurately identifying time points of stage division;
selecting a small-break modeling model corresponding to the model, performing accident simulation, dividing the accident process into 5 identical stages according to an accident sequence, and accurately identifying stage division time points of the model;
step five, data are brought into the Pi groups corresponding to each stage to be calculated, and the obtained two groups of dimensionless parameters are compared; if meeting criterion 0.5 is less than or equal to pi R And if the dimensionless number ratio is less than or equal to 2 and accords with the usable range, the phenomena are considered to be similar, and the selected experimental data are suitable for the target model.
3. The method for evaluating the applicability of pressurized water reactor water loss accident data according to claim 2, wherein the phenomenon recognition and ranking table in the first step corresponds to a selected overall effect test bench, a target prototype stack or a target bench, and the selected important phenomenon is guaranteed to be recognized as high H therebetween;
in the second step, top-down analysis is carried out, a dimensionless Pi group of a single-phase two-phase basin is obtained, and a pressure drop equation is obtained according to mass, momentum and energy conservation equations; after dimensionless, according to the physical meaning of each term: the pressure change caused by the specific energy and specific volume change caused by mass inflow, mass outflow and heat transfer is obtained to obtain a dimensionless Pi group.
4. The method for evaluating the applicability of the pressurized water reactor water loss accident data according to claim 2, wherein the step three and the step four are based on the steps of:
(1) And (3) spraying: the starting point is identified as the opening of the break; during most of the spraying phase, the RCS remains almost in a single-phase liquid state; when the stage is finished, the upper sealing head, the upper chamber and the hot section start to be separated; in the spraying stage, the fluid at the break is single-phase liquid, and the end point is identified as the two-phase spraying of the break;
(2) Natural circulation and water seal formation stage: typically characterized by a plateau of circuit pressure; at the end of the spraying phase, the RCS pressure reaches a quasi-equilibrium state for hundreds of seconds, and the liquid in one loop allows a significant natural circulation two-phase flow around the loop; the RCS continues to consume a large amount of cooling liquid, and steam generated in the reactor core is blocked in the upper area of the SG by liquid in the loop to form a water seal; the liquid plug is a U-shaped portion in the cold leg between the steam generator outlet plenum and the reactor coolant pump inlet; the coolant with low mass flow still flows out of the crack; after the water seal is formed, the flow rate of the transition section of the primary pump of the primary circuit is 0; when the cleaning starts, the flow rises rapidly, and the criterion of the ending time point is that the steam flow of the transition section rises rapidly and the liquid level of the transition section falls rapidly;
(3) And (3) a water seal cleaning stage: the water seal cleaning phenomenon occurs in a transition section U-shaped pipe from an SG outlet pipe of a traditional pressurized water reactor to an inlet of a main pump; the formation of the water seal causes the interruption of natural circulation, when the liquid level of the reactor core is reduced to a certain extent, and when the pressure difference between the reactor descending section and the reactor core is increased enough to overcome the resistance caused by the water seal, the water seal in the transition section is cleared, obvious steam flow occurs in the transition section, the liquid level of the reactor core is quickly risen, and the criterion of the ending time point is that = the transition section steam flow reaches a stable value inflection point and the transition section liquid level is reduced to a low value inflection point;
(4) Water evaporation stage: the liquid level of the pressure vessel mixture continues to decrease after the loop water seal is cleared due to the evaporation of the remaining core water content; before the RCS is depressurized to the point that the break flow becomes lower than the safe injection flow, the primary circuit water content reaches a minimum value, the reactor core is exposed in some cases, and the criterion of the ending time point is that the safe injection flow is equal to the break flow;
(5) And (3) a reactor core re-submerging stage: when the safety injection flow is larger than the break flow, the submerged stage starts, the whole water content of the first loop is raised, the continuous cooling of the reactor core is ensured, and the safety is ensured.
5. The pressurized water reactor water loss accident data applicability evaluation method according to claim 2, wherein the data required in the third and fourth steps comprises: the method comprises the steps of a reactor core heating section, an upper end enclosure, an upper chamber, a hot pipe section, an SG ascending section, an SG descending section, a transition section, a cold pipe section, a reactor core descending section, water loading capacity of a lower chamber, pressure, gas phase temperature, liquid phase temperature, average density, liquid level, vertical height, mass flow rate at a break, pressure, gas phase temperature, liquid phase temperature and density, reactor core decay heat, reactor core inlet nozzle flow rate, reactor core inlet density and reactor core inlet and outlet pressure, wherein the total number of the data is 80;
the dimensionless criterion numbers involved in the third and fourth steps include:
the time points involved in the third and fourth steps are selected as the initial time of each stage, namely 4 time points, and 80 groups of data are required to be extracted at each time point to form a data table.
6. The method for evaluating the applicability of the pressurized water reactor water loss accident data according to claim 2, wherein in the fifth step, 80 groups of data of 4 time points of the experimental data and the target reactor model operation data are brought into the dimensionless criterion number according to the stage and the requirement, and the dimensionless criterion number calculation results of the experimental data and the target reactor model operation data are compared;
Π R ＝Π Test /Π Object if the dimensionless number ratio accords with the usable range of 0.5 to be equal to or less than pi R If the temperature is less than or equal to 2, the phenomena are considered to be similar, and the data on the selected rack is used for verifying the target reactor; if the dimensionless number ratio exceeds the available range, the phenomenon similarity is deficient, the same type of working condition data on the selected rack cannot be used for verifying the target pile type and the rack, the separation effect experimental phenomenon to be analyzed is identified, and the SET is established for the phenomenon which is not met.
7. A pressurized water reactor water loss accident data applicability evaluation system applying the pressurized water reactor water loss accident data applicability evaluation method according to any one of claims 1 to 6, characterized in that the pressurized water reactor water loss accident data applicability evaluation system comprises:
the important phenomenon analysis module is used for analyzing important phenomena of each stage of the small break accident process and determining important phenomena corresponding to the phenomenon identification and ranking table;
the dimensionless analysis module is used for carrying out dimensionless analysis from top to bottom and from bottom to top to form a dimensionless Pi group comprising single-phase two-phase watershed, and determining important parameters to be selected;
the stage division module is used for selecting small break experimental data to be subjected to applicability analysis, dividing the accident process into 5 stages according to an accident sequence, and accurately identifying time points of stage division;
the accident simulation module is used for selecting a small break modeling model of a corresponding model to perform accident simulation, dividing the accident process into 5 stages according to an accident sequence, and accurately identifying the stage division time points of the model;
the data applicability evaluation module is used for bringing data into the Pi group calculation of each corresponding stage, comparing the two obtained dimensionless parameters, and obtaining a data applicability conclusion according to a criterion.
8. A computer device comprising a memory and a processor, the memory storing a computer program which, when executed by the processor, causes the processor to perform the steps of the pressurized water reactor loss of water accident data suitability assessment method according to any one of claims 1 to 6.
9. A computer-readable storage medium storing a computer program which, when executed by a processor, causes the processor to execute the steps of the pressurized water reactor water loss event data applicability evaluation method according to any one of claims 1 to 6.
10. An information data processing terminal, characterized in that the information data processing terminal is used for realizing the pressurized water reactor water loss accident data applicability evaluation system according to claim 7.
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Non-Patent Citations (2)
| Title |
|---|
| 张雪艳等: "基于无量纲准则数的整体效应试验数据适用性验证方法探究", 核动力工程, vol. 43, no. 1, pages 1 - 4 * |
| 邓程程等: "小破口失水事故最佳估算的不确定性和敏感性分析", 原子能科学技术, vol. 50, no. 07, pages 1224 - 1231 * |
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