KR100936927B1 - The spent fuel management and automatic nuclear cross-section input data generation method for nuclear reactor core design - Google Patents

Abstract

The present invention relates to a method of producing spent fuel management and cross-sectional input data for core nuclear design of a nuclear power plant.

Method for producing input data of the present invention comprises the first step of producing the necessary input data from the output data of the ANC code and ALAMO code for the pre-stored past cycles and stores in the GUI database; A second step of producing a current cycle core loading model from the input data and displaying the GUI screen; A third step of modifying and changing the input data of the displayed current cycle core loading model; And a fourth step of outputting the modified input data of the current cycle core loading model into an electronic file format.

The present invention enables the systematic management of fuels discharged from nuclear power plants, makes it easy to view the loading models of existing cycles, and to easily check the detailed information of individual aggregates, and to input the three-dimensional core model of the current design cycle. Can be efficiently and accurately obtained.

Nuclear Power Plant, Core, Nuclear Design, GUI, Nuclear Cross Section

Description

{THE SPENT FUEL MANAGEMENT AND AUTOMATIC NUCLEAR CROSS-SECTION INPUT DATA GENERATION METHOD FOR NUCLEAR REACTOR CORE DESIGN} for Core Fuel Design of Nuclear Power Plants

The present invention relates to a method of producing spent fuel management and cross-sectional input data for core nuclear design of a nuclear power plant.

In particular, it is possible to easily prepare and systematically manage the spent fuel information of nuclear power plants and to reduce the time and effort required to write the input data of the design code for 3D core modeling. A method for producing spent fuel management and nuclear cross-section input data for core nuclear design of nuclear power plants to provide a convenient computing environment.

In order to evaluate the safety of nuclear power plants, core modeling through 3D analysis code is required, and ALPHA / PHOENIX-P as a neutron cross-sectional production code and ANC code (Advanced Nodal Code) as 3D core analysis model code are used in many power plants worldwide. ) Is used commercially.

① After-use fuel management organizes data such as combustion degree, enrichment degree, loading history, and fuel name (ID) of fuel released after burning in power plant for management of future fuel reloading or acquisition of various fuel information. I mean. ② Input data of 3D core modeling is input data for modeling core as 3D analysis code. It means design code input data for verifying various safety factors such as fuel power distribution, reactivity, and combustion distribution of fuel in core.

The management of spent fuel is essential for the selection of reloaded fuel or for obtaining information on the fuel released. The designer checks the fuel information manually from the vast output data of previously executed design codes and organizes the information of the fuel released in each cycle. This requires a lot of time and effort, given that the number of fuels loaded into the core ranges from 121 to 177, depending on the type of power plant. This data is the basis for 3D core modeling and can be used as a fuel for the spent fuel management of nuclear power plants.

Then, the fuels to be reloaded are selected from the information of the used fuels, the specifications of the new fuels to be reloaded are determined, and a two-dimensional neutron cross-sectional production process for these loaded fuels is performed. The designer needs a procedure to reclassify the fuel based on the concentration of the fuel, the degree of combustion, the number of flammable absorbent rods and the combustion history from the information of the fuels to be loaded into the core and to predict the combustion conditions of the core for the current design cycle. The input data for the production of neutron cross-sectional area are prepared by assuming the concentration of boric acid water to control the reactivity of the core contained in the combustion. In order to prepare such input data, the designer needs to manually find and analyze suitable data from the output data of the vast design codes of the existing design cycles, and then arrange and prepare them according to the input of the design code. The designer then executes the ALPHA / PHOENIX-P code to produce a nuclear cross section.

The designer then needs to produce a three-dimensional core model using ANC code. The input data of the ANC code confirms the neutron cross-sectional data mentioned above, the loading history and fuel name (ID) of the fuels that make up the current core, and also determines the core location of each fuel and the nuclear cross-section applied for each fuel. It is necessary to create complex input data that consists of creating linked data. The preparation of these input data needs to be found manually and analyzed from the spent fuel management information or the output data of the ANC code of the last cycles, and then organized according to the input of the design code. Once the input is complete, the designer executes the ANC code to produce a three-dimensional core model.

As such, the input data of the design code for information management of spent fuel and 3D core modeling is based on the specifications of the discharged fuel, the combustion history, the specification of the newly loaded fuel, the name and location of the loaded fuel, and the design cycle. It is required to prepare a large number of input data such as combustion conditions of the designer, and to this end, the designer needs to manually search from the output data of the design code for the existing design cycles and analyze and organize them according to the input of the design code. This requires a lot of manpower and time, and it is not easy to verify the vast design input data.

An object of the present invention is to solve such a problem, it is easy to create and systematically manage the information of the spent fuel of the nuclear power plant, and the time and effort required to write the input data of the design code for the three-dimensional core modeling It is to provide a method of producing spent fuel management and nuclear cross-section input data for core nuclear design of nuclear power plants to reduce human error and to create a convenient computing environment.

The present invention for achieving the above object is a first step of producing the necessary input data from the output data of the ANC code and ALAMO code (Automated Linkige of ANC Modeling Operations) for the pre-stored past cycles and storing in the GUI database; A second step of producing a current cycle core loading model from the input data and displaying the GUI screen; A third step of modifying and changing the input data of the displayed current cycle core loading model; And a fourth step of outputting the modified input data of the current cycle core loading model into an electronic file format.

The current cycle core load model inputs the current cycle number in the GUI screen input window, selects the method of constructing the current cycle load model, selects the type of flammable absorbent rod, inputs the predicted cycle burn rate, and names the new fuel region. It is preferable to produce by inputting (ID).

In addition, the current cycle core loading model is preferably displayed as a quarter (4/4) core loading model with respect to the entire core loading model.

In addition, the third step may further include a step of systematically managing the information of the fuel recharged and discharged and the information of the spent fuel previously released in the previous cycles systematically over the entire cycles.

In addition, in the fourth step, it is preferable that the information of the spent fuel is made into a database to be output in an electronic file form along with the input data of the modified and modified current cycle core loading model.

In addition, the display window displaying the current cycle core loading model is a tool that enables the core loading model to be viewed for past cycles, a tool for exchanging positions of fuel with respect to the loading model of the design cycle, and an entire core. Tool for making symmetrical fuels exchangeable, selecting a particular fuel creates a window for that particular fuel and displays details of the individual aggregates such as loading history, output, and concentration of the selected fuel, the current cycle A tool that generates a spent fuel management window when selecting a specific fuel in the core loading model, reloads the desired fuel from the spent fuel information and releases the selected fuel, and the combustion degree, power distribution, and combustion of the fuels in the core loading model. Various aggregate information such as degree, flammable absorption rod, type of neutron absorption cross section used by fuel, and last cycle loading position of fuel Tools to enable selective reading, tools to view the information of fuel released in each cycle, tools to output the input data of the current cycle loading model and used fuel information in the form of electronic files, loading of the core It is desirable to include a tool to make the model easier to distinguish by varying the color of the fuel, which shows the difference in fuel combustion, the flammable absorbent rod, and the position of the control rod.

By the above solution, it is possible to systematically manage the fuels discharged from the nuclear power plant, easily view the loading models of the existing cycles, and easily check the detailed information of the individual aggregates, and input data of the three-dimensional core model of the current design cycle. Can be efficiently and accurately obtained.

Hereinafter, with reference to the accompanying drawings, preferred embodiments of the present invention will be described in detail.

1 is a flow chart of a method of producing spent fuel management and nuclear cross-section input data for the core nuclear design of a nuclear power plant of the present invention, Figure 2 shows an initial execution screen of the present invention, Figure 3 is an output file of the ANC code The figure shows the window for generating input data from them.

4 is a view showing a window for producing a current cycle core loading model, FIG. 5 is a view showing a window for a current cycle core loading model produced by FIG. 4, FIG. Figure shows a window showing the details of the fuel generated when.

7 is a view showing a window for the management of spent fuel, FIG. 8 is a view showing an example of the output information of the spent fuel arranged by the discharge cycle, Figure 9 is a partial output example of the input data of the three-dimensional core model The figure shown.

As shown in the figure, a method for producing spent fuel management and cross-sectional input data for core nuclear design of a nuclear power plant of the present invention uses a graphical user interface (GUI) through an X window system in a Unix computer operating system.

The GUI refers to an environment in which a user can work through graphics when exchanging information with a computer, and allows a user to select a menu on the screen using a mouse to work.

The present invention works by executing a GUI program in a Unix workstation command window, and before the execution of the ANC code, the output files of the ANC code, a three-dimensional core model that has been performed in the past, that is, in past cycles. Output files of ALAMO codes with the ability to extract data from the resulting databank should be prepared and stored in computer memory. These outputs are the results that have already been produced in the design of the last cycles and can be easily prepared by the designer.

When such output data is prepared, the GUI program is executed. The present invention produces an input file from the output data of ANC code and ALAMO code for previously stored periods and stores the input data in a GUI database. A first step (S11), a second step (S12) of producing a current cycle core loading model from the input data and displaying the GUI screen, and a third step of modifying and changing the input data of the current cycle core loading model displayed. (S13) and through the fourth step (S14) of outputting the input data of the modified and modified current cycle core loading model into an electronic file format for the 3D core model design for the core loading model. Get input data of design code.

In addition, the third step (S13) further includes a step of systematically managing the information of the fuel re-loaded and discharged and the information of the spent fuel previously released in the previous cycles systematically over the entire cycles, Step 4 (S14) may be a database of the information of the spent fuel can be output in the form of an electronic file with the input data of the modified and modified current cycle core loading model.

The input data in the first step S11 is obtained from the windows of FIGS. 2 and 3. FIG. 2 is an initial execution GUI screen. The initial execution GUI screen automatically generates input data required for this GUI program from output data of ANC and ALAMO codes. Clicking the FILE button, the cascade button in the main menu at the top of the screen, has two select buttons that create a separate sub-window that generates the input data required by the program from the output data of the ANC and ALAMO codes. An additional button appears for the case where required input data have been created.

FIG. 3 shows the sub-window of FIG. 2 for generating input data required by the program from the output files of the ANC code. Through this window, the input data for each cycle is processed by processing the output data of 5 cycles of the ANC code at once. Can produce data The input data generated by this cycle are stored in the execution directory so that it does not need to be produced again when the program is executed again. In this way, the output of the ALAMO code is also processed.

The present cycle core loading model of the second step (S12) is produced through the window of FIG. The window of FIG. 4 is a GUI input screen when input files for each cycle are produced. In this window, enter some conditions of the cycle you want to design, such as the current cycle number, select the construction method of the current cycle loading model, select the type of flammable absorbent rod, enter the predicted cycle burn rate, It is a window for inputting a name (ID) and so on, and consists of a simple selection button and a data entry term. When the input is completed and the OK button is clicked, the present cycle core loading model is produced through the input data.

The current cycle core loading model produced through the second step S12 is as shown in FIG. 5. The current cycle core loading model displayed through the GUI window of FIG. 5 is a loading model showing the fuel arrangement form of the quarter (1/4) core. The third step S13 and the fourth step S14 are performed through this window, and this window is composed of various menus, options, and buttons to perform the third step S13 and the fourth step S14. Let's do it. In other words, the menu, options and buttons provided in this window are appropriately selected according to the third step (S13) and the fourth step (S14) to input the design code for designing the three-dimensional core model for the loading model of the core. Get the data.

Looking at this window, you can see the buttons that allow you to view the core's reload model for the last cycle, the buttons that enable the interchange of fuel positions for the reload model in the design cycle, and the entire core. It has a button that makes symmetric fuel exchangeable.

Selecting a particular fuel also creates a new window (see FIG. 7) and has a button (Ass. Info) that shows details of the individual aggregates, such as loading history, output, and concentration of the selected fuel.

In addition, when selecting a specific fuel in the loading model, it generates a used fuel management window, and has a button for reloading the desired fuel discharged from the used fuel information and releasing the selected fuel.

In addition, a button for selectively reading various aggregate information such as combustion degree, power distribution, combustion degree, flammable absorption rod, type of neutron absorption area used for each fuel, and last cycle loading position of fuel of the core loading model ( Multiple toggle buttons at the top of the screen).

In addition, it has a button (View Fuel) to view the information of the fuel released in each cycle, through which the management of spent fuel is automatically performed.

On the other hand, the Xcody punch button built in the window has the function of storing the input data of the 3D core model and the spent fuel information for the present cycle core reloading model and outputting it in the form of an electronic file. At this time, detailed data such as the information of the current cycle core loading model can be output in the form of an electronic file.

The Color View button also makes it easier for designers to change the color of the fuel, which shows the core's loading model based on the difference in fuel burnup, the flammable absorbent rod, and the position of the control rod.

FIG. 6 is a window generated when selecting the "Ass. Info." Button on the screen of FIG. 5 and selecting a fuel of a specific position, and shows detailed information of the selected fuel.

FIG. 7 is a window 7 for the management of spent fuel, which is generated by clicking the View Fuel button in the window of FIG. 5, and selecting a specific cycle burns the data of fuel released in that cycle. Sort by degree. In addition, in the window of FIG. 5, when the Replace button for performing the fuel exchange function is selected and the fuel button of the specific position is clicked, a separate window showing the same information is generated and the previously selected fuel is selected by selecting the discharged fuel to be reloaded. Replacement with fuel is possible. In addition, credit information of all currently available specifications is shown and it is possible to replace the fuel selected previously with fresh fuel.

FIG. 8 shows an example of the information of the spent fuel, which is arranged according to the discharge cycle, as output data produced when the xcody punch button is clicked in the window of FIG. 5.

FIG. 9 is an output file 9 produced when the xcody punch button is clicked in the window of FIG. 5 and shows some examples of input data of the three-dimensional core model.

As described above, according to the present invention, it is possible to easily prepare and systematically manage the information of spent fuel of a nuclear power plant, and to significantly reduce the time and effort required to prepare input data of design code for 3D core modeling. In addition to preventing errors, it has the effect of creating a convenient computing environment for the designer.

This makes it possible to systematically manage fuels discharged from nuclear power plants, to easily view the loading models of existing cycles and to check the details of individual assemblies, and to efficiently and accurately input the input data of the three-dimensional core model of the current design cycle. You can get it.

1 is a flow chart of a method of producing spent fuel management and nuclear cross-section input data for core nuclear design of a nuclear power plant of the present invention.

2 is a view showing an initial execution screen of the present invention.

3 is a view showing a window for generating input data from output files of an ANC code.

4 is a view showing a window for producing a current cycle core loading model.

5 is a view showing the current cycle core loading model window produced by FIG.

FIG. 6 is a diagram illustrating a window showing detailed information of fuel generated when a fuel of a specific position is selected from the screen of FIG. 5.

7 is a view showing a window for management of spent fuel.

FIG. 8 is a diagram showing an example of outputting used fuel information arranged by emission cycles.

9 is a view showing a part of the output example of the input data of the three-dimensional core model.

Claims (6)

A first step of producing necessary input data from output data of ANC code and ALAMO code for previously stored past cycles and storing them in a GUI database; A second step of producing a current cycle core loading model from the input data and displaying the GUI screen; A third step of modifying and changing the input data of the displayed current cycle core loading model; And And a fourth step of converting the modified and changed input cycle data of the current cycle core loading model into a database and outputting the data in an electronic file form. The current cycle core load model inputs the current cycle number in the GUI screen input window, selects the method of constructing the current cycle load model, selects the type of flammable absorbent rod, inputs the predicted cycle burn rate, and names the new fuel region. A method for producing spent fuel management and cross-sectional input data for core nuclear design of a nuclear power plant, characterized in that it is produced by inputting an ID. delete The spent fuel management and cross-sectional area input for core nuclear design of a nuclear power plant according to claim 1, wherein the current cycle core loading model is displayed as a quarter (4/4) core loading model for the entire core loading model. Method of producing data. The method of claim 1, wherein the third step further comprises the step of systematically managing the information of the reloaded and discharged fuel and the spent fuel previously released in the previous cycles systematically over the entire cycles. A method of producing spent fuel management and nuclear cross-section input data for core nuclear design of a nuclear power plant characterized by 5. The core nuclear design of a nuclear power plant according to claim 4, wherein the fourth step outputs a database of used fuel information and outputs it in an electronic file form with the input data of the modified and modified current cycle core loading model. Method of producing spent fuel management and nuclear cross-section input data. 6. The display of claim 5, wherein the display window for displaying the current cycle core loading model is a tool that enables viewing of the core loading model for past cycles, and a tool for exchanging positions of fuel with respect to the loading model of the design cycle. A tool that allows the exchange of symmetrical fuels for the entire core, selecting a particular fuel creates a window for that particular fuel and displays details of the individual aggregates such as loading history, output and concentration of the selected fuel A tool for generating a spent fuel management window when selecting a specific fuel in the current cycle core loading model, reloading a desired pre-emission fuel from the spent fuel information, and releasing the selected fuel, the combustion degree of the fuels of the core loading model, Various distributions such as output distribution, combustion degree, flammable absorption rod, type of neutron absorption cross section used by fuel, and last cycle loading position of fuel A tool for selectively reading the sieve information, a tool for reading the information of the fuel released in each cycle, a tool for outputting the input data of the current cycle loading model and the used fuel information in the form of an electronic file, For the core nuclear design of nuclear power plants, the loading model of the core includes tools for easy identification by varying the color of the fuel according to the difference in fuel combustion, the flammable absorbing rod, and the position of the control rod. Method of producing spent fuel management and nuclear cross section input data.

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