CN112668165A - Reactor core design system and application - Google Patents
Reactor core design system and application Download PDFInfo
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- CN112668165A CN112668165A CN202011517947.1A CN202011517947A CN112668165A CN 112668165 A CN112668165 A CN 112668165A CN 202011517947 A CN202011517947 A CN 202011517947A CN 112668165 A CN112668165 A CN 112668165A
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Abstract
The invention discloses a reactor core design system and application thereof, and the system comprises a fuel consumption calculation module, a reactor core state parameter calculation module, a reactivity parameter and loss calculation module, a dynamics parameter calculation module, a xenon evolution calculation module, a samarium reactivity module, a xenon transient structure module, a state transient calculation module, a clamping rod calculation module, a control rod sequential insertion calculation module, a control rod movement calculation module, a control rod calculus value calculation module, a bite amount calculation module, a data extraction and post-processing module, a scale curve calculation module and a three-dimensional pressure two-dimensional module. The design system integrates all the calculation modules required in the reactor core design process of the reactor, so that the reactor core design process is more integrated and automated, the personnel intervention in the design process is reduced, the design efficiency is improved, various human errors are reduced, and the design reliability is improved.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor cores, and particularly relates to a reactor core design system and application thereof.
Background
The core nuclear design is the upstream and core of the reactor design, and any reactor nuclear design is not an accurate, efficient, convenient computing platform and design system.
The existing core design technology needs a large amount of professionals to realize the core design, and has the problems of low calculation efficiency, poor reliability, limited functions and the like; at present, a design and verification system which covers all contents of reactor core design, closely couples each specialty and is automatic in flow is not available in China, and a reactor core design system with all independent intellectual property rights and complete functions is urgently needed to perfect the independent nuclear power intellectual achievement in China.
Disclosure of Invention
The invention provides a reactor core design system, aiming at solving the problems of low calculation efficiency, poor reliability, limited functions and the like of the existing reactor core design technology. The invention uses each independent computing module, and automatically completes the complete physical computing analysis process of the nuclear design reactor core through specific algorithm logic and a series of flexible combinations.
The invention is realized by the following technical scheme:
a reactor core design system comprises a fuel consumption calculation module, a reactor core variable state calculation module, a reactivity parameter and loss calculation module, a kinetic parameter calculation module, a xenon evolution calculation module, a samarium reactivity module, a xenon transient structure module, a state transient calculation module, a rod clamping calculation module, a control rod sequential insertion calculation module, a control rod movement calculation module, a control rod calculus value calculation module, a bite amount calculation module, a data extraction and post-processing module, a scale curve calculation module and a three-dimensional pressure two-dimensional module;
the burnup calculation module is used for calculating the burnup of the reactor and outputting a two-dimensional or three-dimensional burnup result, boron concentration, power, temperature, xenon distribution, nuclear density and other comprehensive burnup of the reactor;
the reactor core variable state calculation module calculates according to the input reactor core state parameters and outputs the calculation result in the reactor core state;
the reactivity parameter and loss calculation module is used for calculating the reactivity coefficient loss after the operating conditions of the reactor change;
the dynamic parameter calculation module is used for extracting dynamic parameters of the reactor core;
the xenon evolution calculation module is used for calculating the iodine and xenon burnup evolution at a preset time step, and simulating the xenon evolution process according to the reactor core relative power and the control rod group position parameters input at each time step;
the samarium reactivity module is used for carrying out samarium evolution calculation by changing the reactor core power before and after disturbance so as to calculate the reactivity of samarium introduction after the reactor core power of the reactor is changed and in a constant period;
the xenon transient construction module is used for calculating xenon evolution under a preset condition, and carrying out xenon evolution calculation by changing reactor core state parameters before and after disturbance so as to simulate xenon distribution in the operation process;
the state transient calculation module performs reactor core calculation by changing the state of the reactor core according to the input calculation sequence to generate a state transient database;
the rod clamping calculation module is used for calculating the state of the reactor by simulating the change of the reactivity of a bundle of control rods for clamping the reactor core;
the control rod sequential insertion calculation module is used for generating a reactor core database under various rod inserting states, providing xenon options, boron concentration options and power options, and inserting each bundle of control rods according to a preset sequence;
the control rod movement calculation module completes the calculation of a reactor core when any control rod is at various positions, and simulates accident states of rod falling, control rod desynchronizing, rod clamping and rod ejecting;
the control rod calculus value calculation module respectively calculates reactivity coefficients of the reactor core with and without control rods, and the calculus value of the control rods is calculated based on the reactivity coefficients of the control rods and the reactor core;
the bite amount calculation module is used for calculating the minimum insertion amount of the power regulating rod in the reactor core under the normal operation state;
the data extraction and post-processing module searches and extracts a calculation result according to a preset name and format, and performs post-processing calculation;
the scale curve calculation module is used for calculating the scale position of the control rod of the reactor at each power level;
the three-dimensional pressure two-dimensional module is used for performing equivalent integration and compression on the three-dimensional reactor core data to form two-dimensional reactor core data. Based on the reactor core design system, the invention realizes all calculations in the core design and realizes automatic extraction of the calculation data, and the specific calculation flow comprises the following steps:
a moderator temperature coefficient and loss calculation method adopts a reactor core variable state calculation module, a fuel consumption calculation module, a reactivity coefficient and loss calculation module and a data extraction and post-processing module in the reactor core design system to calculate:
1) moderator temperature coefficients and moderator temperature defects at different power levels and different boron concentrations;
2) moderator temperature coefficients at different burning moments, different HFP and different ARO states;
3) moderator temperature coefficients at different rod states and different boron concentrations.
A method for calculating boron differential value adopts a reactor core variable state calculation module, a fuel consumption calculation module, a reactivity coefficient and loss calculation module and a data extraction and post-processing module in the reactor core design system to calculate the boron differential value under different fuel consumption, different boron concentrations and different power levels.
A Doppler coefficient calculation method comprises the following steps of calculating by adopting a three-dimensional pressure two-dimensional module, a core variable state calculation module, a fuel consumption calculation module, a reactivity coefficient and loss calculation module and a data extraction and post-processing module in the reactor core design system:
1) doppler power coefficients at different burnup and different power levels;
2) the reactivity introduced by the doppler effect under EOL varies with power level.
A power coefficient calculation method adopts a three-dimensional pressure two-dimensional module, a reactor core variable state calculation module, a fuel consumption calculation module, a reactivity coefficient and loss calculation module and a data extraction and post-processing module in the reactor core design system to calculate:
1) power coefficients at different burn-up times, different boron concentrations, and different power levels;
2) power deficit at different burn-up times, different boron concentrations, and different power levels;
3) power deficit at different burn-up times, different power levels.
A method for calculating boron concentration adopts a reactor core variable state calculation module, a fuel consumption calculation module and a data extraction and post-processing module in the reactor core design system to calculate:
1) the minimum boron concentration required for shut-down varies with fuel;
2) boron concentrations at different core states;
3) minimum soluble boron concentration for different core states during cold and hot shut-down.
A dynamic parameter calculation method adopts a reactor core variable state calculation module, a burnup calculation module, a dynamic parameter calculation module and a data extraction and post-processing module in the reactor core design system to calculate the reactor core delayed neutron share and the reactor core reactivity along with the change of doubling time and the reactor period under different burnup steps.
A method for calculating the reactivity of xenon comprises the steps of calculating the reactivity introduced by xenon when the reactor core is shut down, power is increased and power is decreased at different burning times by adopting a burnup calculation module, a reactor core variable state calculation module, a three-dimensional pressure two-dimensional module, a xenon evolution calculation module and a data extraction and post-processing module in a reactor core design system.
A rod value calculation method adopts a fuel consumption calculation module, a reactor core variable state calculation module, a control rod differential value calculation module, a control rod sequential insertion reactor core calculation module and a data extraction and post-processing module in the reactor core design system to calculate:
1) the calculus value of the insertion of the power compensation rod groups under different burnup and different power levels according to the overlapping steps and the insertion of the single rod group;
2) the calculus value of the R rod set at different burnup, different power levels.
A power distribution map calculation method adopts a burnup calculation module, a core variable state calculation module, a control rod sequential insertion core calculation module and a data extraction and post-processing module in the reactor core design system to generate the power distribution maps of the cores under different burnups, different rod states and different power levels.
A samarium reactivity calculation method adopts a burnup calculation module, a samarium reactivity burnup calculation module and a data extraction and post-processing module in the reactor core design system to calculate the reactivity introduced by samarium when different burnup lower cores are shut down, power is increased and power is decreased.
A method for calculating a calibration curve of an adjusting rod is characterized in that a burnup calculating module, a reactor core variable state calculating module, a seizure calculating module, a calibration curve calculating module and a data extracting and post-processing module in a reactor core design system are adopted to calculate the calibration rod position of a highway adjusting rod group for compensating power loss at different burning time.
The invention has the following advantages and beneficial effects:
the design system integrates all the calculation modules required in the reactor core design process of the reactor, so that the reactor core design process is more integrated and automated, the personnel intervention in the design process is reduced, the design efficiency is improved, various human errors are reduced, and the design reliability is improved.
The design system of the invention can simultaneously realize the calculation of all parameters in the core design and realize the automatic extraction of the calculation data.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic block diagram of the system architecture of the present invention.
FIG. 2 is a schematic diagram of the moderator temperature coefficient and deficit calculation process of the present invention.
FIG. 3 is a schematic diagram of the boron differential value calculation process of the present invention.
FIG. 4 is a flow chart illustrating the calculation of Doppler coefficient according to the present invention.
FIG. 5 is a schematic diagram of a power coefficient calculation process according to the present invention.
FIG. 6 is a schematic diagram of a boron concentration calculation process according to the present invention.
FIG. 7 is a schematic view of a kinetic parameter calculation process according to the present invention.
FIG. 8 is a schematic diagram of a xenon reactivity calculation flow according to the present invention.
FIG. 9 is a schematic representation of a rod value calculation process of the present invention.
FIG. 10 is a schematic diagram of the calculation of the power distribution diagram according to the present invention.
Fig. 11 is a schematic diagram of a samarium reactivity calculation procedure of the present invention.
FIG. 12 is a schematic diagram of a calibration curve calculation process of the adjusting rod of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1
The present embodiment proposes a reactor core design system, which integrates all the calculation modules involved in the core design and performs automatic extraction on the calculation data, and the parameters calculated by the system of the present embodiment include, but are not limited to: reactivity coefficient and reactivity loss under each state, boron concentration under each state, value of each control rod group under different states, delayed neutron parameters, reactivity change caused by xenon and samarium poisons under different power changes, and other neutron parameters.
Specifically, as shown in fig. 1, the design system of this embodiment includes a fuel consumption calculation module, a reactor core variable state calculation module, a reactivity parameter and loss calculation module (coefficient calculation module for short), a kinetic parameter calculation module, a xenon evolution calculation module, a samarium reactivity module, a xenon transient structure module, a state transient calculation module, a rod clamping calculation module, a control rod sequential insertion calculation module, a control rod movement calculation module, a control rod calculus value calculation module, a bite calculation module, a data extraction and post-processing module, a scale curve calculation module, and a three-dimensional pressure two-dimensional module;
the burnup calculation module of the embodiment is used for performing reactor burnup calculation and outputting comprehensive reactor burnup of two-dimensional or three-dimensional burnup results, boron concentration, power, temperature, xenon distribution, nuclear density and the like.
The core variable state calculation module of the embodiment supports a user to input core state parameters such as control rod positions, critical search options, core power, temperature and the like, calls a three-dimensional core calculation program, calculates according to the input parameters, and outputs a calculation result in the core state.
The reactivity parameters and loss calculation module of this embodiment reflects the ability of the effective multiplication factor to change due to changes in reactor operating conditions such as power levels, moderator average temperature, fuel temperature, pressure, etc. And calculating the loss of the reactivity coefficient after the conditions are changed according to a certain formula.
The dynamic parameter calculation module of the embodiment is used for extracting dynamic parameters of the reactor core, wherein the dynamic parameters include delayed neutron share, prompt neutron lifetime, decay constant and the like.
The xenon evolution calculation module of the embodiment can calculate the iodine and xenon burnup evolution at a given time step, and a user can input parameters such as core relative power, control rod group position and the like at each time step to simulate the xenon evolution process.
The samarium reactivity module of the present embodiment performs samarium evolution calculations by varying the core power before and after the perturbation. To calculate the reactivity introduced by samarium after and during the time that the reactor core power was changed.
The xenon transient construction module of the embodiment is mainly used for calculating the xenon evolution under specified conditions, and the xenon evolution is calculated by changing core state parameters (power and control rods) before and after disturbance so as to simulate possible xenon distribution in the operation process.
The state transient calculation module of the present embodiment performs core calculation by changing the core state according to a calculation sequence input by a user, and generates a state transient database.
The rod clamping calculation module of the embodiment calculates the state of the reactor by simulating the change of the reactivity of the reactor core clamped by a bundle of control rods.
The control rod sequential insertion calculation module of the embodiment is used for generating a reactor core database under various rod inserting states, and simultaneously providing xenon options, boron concentration options and power options, wherein each control rod is inserted according to a set sequence.
The control rod movement calculation module of the embodiment can complete the calculation of the reactor core aiming at any control rod at various positions, and can simulate accident states such as rod falling, control rod desynchronizing, rod clamping, rod ejecting and the like.
The control rod calculus value calculation module of the embodiment is used for calculating reactivity coefficients of a reactor core with a control rod and a reactor core without the control rod respectively, and a difference value calculated by the control rod calculus value calculation module and the reactor core according to a certain formula is the calculus value of the control rod.
The bite amount calculation module of the present embodiment is used to calculate the minimum insertion amount of the power control rod inside the core under normal operation.
The data extraction and post-processing module of the embodiment is used for searching and extracting the calculation result according to a certain name and format, and performing post-processing calculation.
The scale curve calculation module of the embodiment is used for calculating the scale positions of the control rods of the reactor at various power levels;
the three-dimensional pressure two-dimensional module (the three-dimensional core compression is a two-dimensional core calculation module) of the embodiment performs equivalent integration and compression on three-dimensional core data by adopting a certain algorithm to form two-dimensional core data.
Example 2
This example uses the reactor core design system proposed in example 1 above to achieve moderator temperature coefficients and loss calculations.
Specifically, as shown in fig. 2, in this embodiment, multiple processes in the design system, such as core variable state calculation (ChangeStatus), burnup calculation (CoreBurn), coefficient calculation (CoeffCal), result extraction calculation (extraction), and result post-processing calculation (synthesis), are used to implement the following calculations:
1) moderator temperature coefficients and moderator temperature defects at different power levels and different boron concentrations;
2) moderator temperature coefficients in different burning moments, HFP and ARO states;
3) moderator temperature coefficients at different rod states and different boron concentrations.
Example 3
This example uses the reactor core design system set forth in example 1 above to achieve the boron differential value calculation.
Specifically, as shown in fig. 3, in the present embodiment, multiple processes such as core variable state calculation (ChangeStatus), burnup calculation (CoreBurn), coefficient calculation (CoeffCal), result extraction calculation (extraction), and result post-processing calculation (synthesis) in the design system are used to calculate boron differential values at different burnups, different boron concentrations, and different power levels.
In the embodiment, a three-dimensional burnup library established in the loading of the reactor core is read, and boron differential value calculation is established.
Example 4
This example uses the reactor core design system proposed in example 1 above to perform doppler coefficient calculations.
Specifically, as shown in fig. 4, in the present embodiment, a plurality of Procedure calculations such as core variable state calculation (ChangeStatus), burnup calculation (CoreBurn), two-dimensional core calculation (collapse3D — 2D), coefficient calculation (CoeffCal), result extraction calculation (extraction), result post-processing calculation (synthesis) and the like in the design system are adopted:
1) doppler power coefficients at different burnup and different power levels;
2) the reactivity introduced by the doppler effect at EOL varies with power level, i.e., doppler feedback.
In this embodiment, a three-dimensional burnup library established in the core apparatus is read, and doppler power coefficients of different power levels in three burnup steps of BOL (beginning of life), MOL (in life) and EOL (end of life) and doppler feedback calculation in the burnup step of EOL are established.
Example 5
This example uses the reactor core design system set forth in example 1 above to perform the power factor calculation.
Specifically, as shown in fig. 5, in the present embodiment, a plurality of Procedure calculations such as core variable state calculation (ChangeStatus), burnup calculation (CoreBurn), two-dimensional core calculation (collapse3D — 2D), coefficient calculation (CoeffCal), result extraction calculation (extraction), result post-processing calculation (synthesis) and the like in the design system are adopted:
1) power coefficients at different burn-up times, different boron concentrations, and different power levels;
2) power deficit at different burn-up times, different boron concentrations, different power levels (without taking redistribution effect into account);
3) power deficit at different burn-up times, different power levels (considering redistribution effect).
In the embodiment, a three-dimensional burnup library established in the loading of the reactor core is read, and the power coefficient and the power loss calculation under different states are established.
Example 6
This example uses the reactor core design system set forth in example 1 above to achieve the boron concentration calculations for each state.
Specifically, as shown in fig. 6, in the present embodiment, a plurality of Procedure calculations such as core variable state calculation (ChangeStatus), burnup calculation (CoreBurn), result extraction calculation (extraction), and result post-processing calculation (synthesis) in the design system are adopted:
1) the minimum boron concentration required for shutdown varies with burnup;
2) boron concentrations at different core states;
3) minimum soluble boron concentration for different core states during cold and hot shut-down.
This embodiment uses each three-dimensional burnup calculation library given in the loading template.
Example 7
This example uses the reactor core design system set forth in example 1 above to perform the kinetic parameter calculations.
Specifically, as shown in fig. 7, in the embodiment, a plurality of processes in the design system, such as core variable state calculation (ChangeStatus), burnup calculation (CoreBurn), kinetic parameter calculation (Edit _ kinetic), result extraction calculation (extraction), are used to calculate the core delayed neutron fraction in different burnup steps, and the change of the core reactivity with the doubling time and the reactor cycle.
This example outputs kinetic parameters at different burnup steps.
Example 8
This example uses the reactor core design system set forth in example 1 above to perform the xenon reactivity calculation.
Specifically, as shown in fig. 8, in the present embodiment, a plurality of processes such as burnup calculation (CoreBurn), core variation state calculation (ChangeStatus), two-dimensional core calculation (collapse3D — 2D), xenon evolution calculation (Trans _ xenon), result extraction calculation (extraction), and result post-processing calculation (synthesis) in the design system are adopted.
The reactivity of the reactor core introduced by xenon when the reactor core is shut down from different power levels, is increased from zero power to different power levels, is decreased from full power to different power levels, and is increased from different power levels to full power under different burnups is calculated respectively.
Example 9
This example uses the reactor core design system set forth in example 1 above to achieve the rod value calculation.
Specifically, as shown in fig. 9, in the present embodiment, multiple Procedure calculations such as a fuel consumption calculation (CoreBurn), a core variable state calculation (ChangeStatus), a control rod differential value calculation (ctrl rod diffword), a control rod sequential insertion core calculation (Bank _ sequence), a result extraction calculation (extraction), a result post-processing calculation (synthesis) and the like in the design system are adopted:
1) the calculus value of the insertion of the power compensation rod groups under different burnup and different power levels according to the overlapping steps and the insertion of the single rod group;
2) the calculus value of the R rod set at different burnup, different power levels.
Example 10
This example uses the reactor core design system set forth in example 1 above to perform the power profile calculations.
Specifically, as shown in fig. 10, in the present embodiment, a plurality of processes such as a burnup calculation (CoreBurn), a core change state calculation (ChangeStatus), a control rod sequence insertion core calculation (Bank _ sequence) in the design system are used to generate power distribution maps of cores at different burnups, different rod states, and different power levels.
Example 11
This example uses the reactor core design system presented in example 1 above to achieve samarium reactivity calculations.
Specifically, as shown in fig. 11, in the embodiment, a plurality of processes in the design system, such as a burnup calculation (CoreBurn), a samarium reactive burnup calculation (smract), and the like, are used to calculate reactivities introduced by samarium during shutdown, power up, and power down of the core under different burnups.
This embodiment outputs the reactivity introduced by samarium at the core drop from different power levels to zero power, drop from full power to a certain power level, ramp from zero power to different power levels at the corresponding burnup.
Example 12
This example uses the reactor core design system set forth in example 1 above to achieve the tuning rod calibration curve calculation.
Specifically, as shown in fig. 12, in this embodiment, a plurality of processes in the design system, such as a fuel consumption calculation (CoreBurn), a changed operation parameter calculation (ChangeContext), a Bite calculation (Bite), a calibration curve calculation (calibration), are used to calculate the calibration rod positions of the power loss compensation rod sets at different fuel consumption times.
The embodiment outputs the scale rod positions of the adjusting rod group for compensating the power loss at different burning moments.
As will be appreciated by one skilled in the art, embodiments of the present application may be provided as a method, system, or computer program product. Accordingly, the present application may take the form of an entirely hardware embodiment, an entirely software embodiment or an embodiment combining software and hardware aspects. Furthermore, the present application may take the form of a computer program product embodied on one or more computer-usable storage media (including, but not limited to, disk storage, CD-ROM, optical storage, and the like) having computer-usable program code embodied therein.
The present application is described with reference to flowchart illustrations and/or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of the application. It will be understood that each flow and/or block of the flow diagrams and/or block diagrams, and combinations of flows and/or blocks in the flow diagrams and/or block diagrams, can be implemented by computer program instructions. These computer program instructions may be provided to a processor of a general purpose computer, special purpose computer, embedded processor, or other programmable data processing apparatus to produce a machine, such that the instructions, which execute via the processor of the computer or other programmable data processing apparatus, create means for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.
These computer program instructions may also be stored in a computer-readable memory that can direct a computer or other programmable data processing apparatus to function in a particular manner, such that the instructions stored in the computer-readable memory produce an article of manufacture including instruction means which implement the function specified in the flowchart flow or flows and/or block diagram block or blocks.
These computer program instructions may also be loaded onto a computer or other programmable data processing apparatus to cause a series of operational steps to be performed on the computer or other programmable apparatus to produce a computer implemented process such that the instructions which execute on the computer or other programmable apparatus provide steps for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (12)
1. A reactor core design system is characterized by comprising a burnup calculation module, a reactor core variable state calculation module, a reactivity parameter and loss calculation module, a kinetic parameter calculation module, a xenon evolution calculation module, a samarium reactivity module, a xenon transient structure module, a state transient calculation module, a rod clamping calculation module, a control rod sequential insertion calculation module, a control rod movement calculation module, a control rod calculus value calculation module, a bite calculation module, a data extraction and post-processing module, a scale curve calculation module and a three-dimensional pressure two-dimensional module;
the burnup calculation module is used for calculating the burnup of the reactor and outputting a two-dimensional or three-dimensional burnup result, boron concentration, power, temperature, xenon distribution and nuclear density information;
the reactor core variable state calculation module calculates according to the input reactor core state parameters and outputs the calculation result in the reactor core state;
the reactivity parameter and loss calculation module is used for calculating the reactivity coefficient loss after the operating conditions of the reactor change;
the dynamic parameter calculation module is used for extracting dynamic parameters of the reactor core;
the xenon evolution calculation module is used for calculating the iodine and xenon burnup evolution at a preset time step, and simulating the xenon evolution process according to the reactor core relative power and the control rod group position parameters input at each time step;
the samarium reactivity module is used for carrying out samarium evolution calculation by changing the reactor core power before and after disturbance so as to calculate the reactivity of samarium introduction after the reactor core power of the reactor is changed and in a constant period;
the xenon transient construction module is used for calculating xenon evolution under a preset condition, and carrying out xenon evolution calculation by changing reactor core state parameters before and after disturbance so as to simulate xenon distribution in the operation process;
the state transient calculation module performs reactor core calculation by changing the state of the reactor core according to the input calculation sequence to generate a state transient database;
the rod clamping calculation module is used for calculating the state of the reactor by simulating the change of the reactivity of a bundle of control rods for clamping the reactor core;
the control rod sequential insertion calculation module is used for generating a reactor core database under various rod inserting states, providing xenon options, boron concentration options and power options, and inserting each bundle of control rods according to a preset sequence;
the control rod movement calculation module completes the calculation of a reactor core when any control rod is at various positions, and simulates accident states of rod falling, control rod desynchronizing, rod clamping and rod ejecting;
the control rod calculus value calculation module respectively calculates reactivity coefficients of the reactor core with and without control rods, and the calculus value of the control rods is calculated based on the reactivity coefficients of the control rods and the reactor core;
the bite amount calculation module is used for calculating the minimum insertion amount of the power regulating rod in the reactor core under the normal operation state;
the data extraction and post-processing module searches and extracts a calculation result according to a preset name and format, and performs post-processing calculation;
the scale curve calculation module is used for calculating the scale position of the control rod of the reactor at each power level;
the three-dimensional pressure two-dimensional module is used for performing equivalent integration and compression on the three-dimensional reactor core data to form two-dimensional reactor core data.
2. A moderator temperature coefficient and loss calculation method is characterized in that the method adopts the core variable state calculation module, the fuel consumption calculation module, the reactivity coefficient and loss calculation module and the data extraction and post-processing module of claim 1 to calculate:
1) moderator temperature coefficients and moderator temperature defects at different power levels and different boron concentrations;
2) moderator temperature coefficients at different burning moments, different HFP and different ARO states;
3) moderator temperature coefficients at different rod states and different boron concentrations.
3. A method for calculating the differential value of boron is characterized in that the method adopts the reactor core variable state calculation module, the fuel consumption calculation module, the reactivity coefficient and loss calculation module and the data extraction and post-processing module in claim 1 to calculate the differential value of boron under different fuel consumption, different boron concentrations and different power levels.
4. A doppler coefficient calculation method, which is calculated by using the three-dimensional pressure two-dimensional module, the core variable state calculation module, the fuel consumption calculation module, the reactivity coefficient and loss calculation module, and the data extraction and post-processing module of claim 1:
1) doppler power coefficients at different burnup and different power levels;
2) the reactivity introduced by the doppler effect under EOL varies with power level.
5. A power coefficient calculation method, characterized in that the method adopts the three-dimensional pressure two-dimensional module, the core variable state calculation module, the fuel consumption calculation module, the reactivity coefficient and loss calculation module, and the data extraction and post-processing module of claim 1 to calculate:
1) power coefficients at different burn-up times, different boron concentrations, and different power levels;
2) power deficit at different burn-up times, different boron concentrations, and different power levels;
3) power deficit at different burn-up times, different power levels.
6. A method for calculating boron concentration, which is characterized by using the core change state calculation module, the burnup calculation module and the data extraction and post-processing module as claimed in claim 1 to calculate:
1) the minimum boron concentration required for shut-down varies with fuel;
2) boron concentrations at different core states;
3) minimum soluble boron concentration for different core states during cold and hot shut-down.
7. A dynamic parameter calculation method is characterized in that the core variable state calculation module, the burnup calculation module, the dynamic parameter calculation module and the data extraction and post-processing module in claim 1 are adopted to calculate the reactor core delayed neutron share and the reactor core reactivity along with the change of doubling time and the reactor cycle in different burnup steps.
8. A xenon reactivity calculation method is characterized in that the method adopts the burnup calculation module, the reactor core variable state calculation module, the three-dimensional pressure two-dimensional module, the xenon evolution calculation module and the data extraction and post-processing module which are described in claim 1 to calculate the reactivity introduced by xenon when the reactor core is shut down, power is increased and power is decreased at different burning times.
9. A rod value calculation method, wherein the method employs the burnup calculation module, the core delta state calculation module, the control rod differential value calculation module, the control rod sequential insertion core calculation module, and the data extraction and post-processing module of claim 1 to calculate:
1) the calculus value of the insertion of the power compensation rod groups under different burnup and different power levels according to the overlapping steps and the insertion of the single rod group;
2) the calculus value of the R rod set at different burnup, different power levels.
10. A method for calculating a power distribution map, wherein the method uses the burnup calculation module, the core change state calculation module, the control rod sequential insertion core calculation module, and the data extraction and post-processing module of claim 1 to generate power distribution maps of cores with different burnups, different rod states, and different power levels.
11. A samarium reactivity calculating method is characterized in that the method adopts the burnup calculating module, the samarium reactivity calculating module and the data extracting and post-processing module in claim 1 to calculate the reactivity introduced by samarium when different burnup reactor cores are shut down, power is increased and power is decreased.
12. A calibration curve calculation method for an adjusting rod is characterized in that a burnup calculation module, a reactor core variable state calculation module, a seizure calculation module, a calibration curve calculation module and a data extraction and post-processing module which are described in claim 1 are adopted to calculate the calibration rod position of a road adjusting rod group for compensating power loss at different burnup time.
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