JPH0711588B2 - Refueling plan creation support device - Google Patents

Description

DETAILED DESCRIPTION OF THE INVENTION [Industrial Application] The present invention relates to a refueling plan creation support device for planning a procedure for taking out fuel, loading, and rearranging a reactor during a periodic inspection of a nuclear reactor. .

(Prior Art) Generally, refueling during periodical reactor inspection is performed for the following basic purposes.

Fuel that has advanced burnup and low reactivity and is not used in the core of the next cycle (may be reloaded after the next cycle) is taken out.

In order to maintain the required reactivity in the core, a new fuel or a fuel (reloading fuel) extracted in the previous cycle and having a surplus of reactivity is loaded.

The fuel is rearranged (shuffling) so that the reactor shutdown margin and core performance of the remaining fuel of the previous cycle and the newly loaded fuel satisfy the limit values.

Here, the target fuel arrangement is evaluated and created using the design code before the refueling work plan. Further, the fuel arrangement and burnup of each cycle are managed using a process computer during the reactor operation period, and the reactivity of each fuel after the end of the cycle can be known by computer processing.

In the refueling plan, in addition to the realization of the core condition of this final goal, it is necessary to realize the core condition necessary for performing core-related work at the time of refueling. The boiling water reactors include the following as the core-related work at the time of refueling, which is involved in the refueling procedure.

Control rod drive system inspection.

Replacement of reactor neutron detectors (local power monitor, intermediate region monitor, neutron source region monitor).

Replacement of control rod.

Temporary fuel withdrawal based on radiation exposure reduction measures during inspection during service.

It is necessary to remove fuel or pull out the control rod for these operations or monitoring. Also, of the fuel that is continuously loaded into the core as fuel for the next cycle,
For fuels with high burnup and two fuel types each, the safety regulation stipulates a visual inspection of the soundness of these fuels. It is necessary to take it out of the furnace.

The main purpose of the refueling work plan is to reduce the amount of work required for refueling as much as possible based on the work processes required during these periodic inspection processes, and to reduce the amount of work required from the previous cycle to the intermediate work required for core-related work. Make a target fuel placement,
Further, it is to complete the fuel arrangement for the next cycle.

The following are the main constraint conditions for creating a refueling work procedure.

Ensuring a margin for furnace shutdown.

Secure support for control rods.

Prohibition of control rod withdrawal adjacent to fuel and transfer of fuel to control rod withdrawal position.

Due to the safety regulations, the reactor shutdown margin means that it is possible to ensure that the reactor becomes subcritical by inserting other control rods regardless of which control rod is inserted. It is required that the core eigenvalue (neutron multiplication factor) is 0.99 or less when one control rod with a certain degree is pulled out from all inserted control rods. This condition is set at the start of refueling work, that is, at the end of the previous operation cycle (End of C
ycle (hereinafter referred to as EOC) and the end of refueling work, that is, the core at the beginning of the next cycle of operation (Beginnig of Cycle,
(Hereinafter referred to as "BOC"), it is ensured by design, but in the process of refueling work, it is not necessarily the case that the fuel arrangement cannot transiently secure the reactor shutdown margin. This is because the reactivity of the fuel in EOC is higher than that of the fuel loaded in BOC, and the core eigenvalue changes depending on the fuel arrangement. In order to ensure this reactor shutdown margin, conventionally, various restrictions have been placed on the fuel combinations that occur in the middle of the reactor, so that the reactivity does not increase locally, and the core eigenvalue is clearly determined from the core state of EOC or BOC as much as possible. Refueling procedures are in place to create core conditions that appear to be low. Therefore, in the process of creating the fuel exchange procedure, many trials and errors regarding fuel combinations are required.

Regarding the control rods, a boiling water reactor uses cross-shaped control rods, and they are inserted and extracted between four fuels.
Only the lower part of the control rod is connected to the drive mechanism, and the control rod is supported so as not to fall down by the surrounding fuel. Therefore, up to two fuels can be taken out diagonally, and the fuels taken out by two adjacent fuels around the control rod are prohibited. In order to take out more fuel, a dummy bundle that has a shape instead of fuel, or a DBG (Bouble Blade Guid) that has two diagonally connected dummy bundles
Use of e) is required. Currently, the number of dummy bundles and DBGs that can be used is limited to a few, and it is necessary to fully consider these movement plans when preparing refueling work.

Some core-related work requires control rod withdrawal as a prerequisite, such as inspection of the control rod drive system and replacement of the control rod itself, but due to safety regulations, pulling out the control rod adjacent to the fuel is prohibited. ing. Originally, it is desirable that all control rods be inserted into the core, but since it is impossible for core-related work, the above-mentioned DBG is used to take out all the fuel around the control rods and then pull out the control rods. Fuel is not allowed to be loaded in the position where the control rod is pulled out, and the pulled-out control rod cannot be inserted unless the control rod support is secured by setting DBG or the like. Such constraint conditions related to the control rod must be taken into consideration when creating the fuel exchange procedure.
It is carefully checked using pieces and boards that simulate the fuel arrangement.

In addition to these restrictions, there are various restrictions on the fuel to be taken out so that the detection limit of the neutron source region monitor used for subcritical monitoring is not reached, and how to use the fuel pool. Efficiently creating a refueling procedure under such constraints has a large work load, and since it is important for safety, it also has a large mental load.
Further, as a factor that makes the work environment severe, there is a demand for shortening the work process, and there is a time constraint that the fuel allocation as the work target is not fixed until just before the start of work. In the refueling work plan, it is impossible for a large number of people to work in parallel, so the work load of the planner is extremely large. Under such circumstances, it is desired to develop an environment that efficiently supports the fuel refueling work plan preparation work.

However, in most of the current refueling plan preparation work, various constraints and procedure creation strategies are simply described in documents, and the planner decides the refueling procedure through trial and error. It was the actual situation. The refueling procedure created in this way largely depends on the skill of the person in charge, and the work content includes some useless parts, and it is not possible to sufficiently respond to the request for shortening the work process. It was

(Problems to be Solved by the Invention) As described above, in the conventional refueling plan preparation work, the planner mainly performs trial and error on the basis of various constraint conditions and procedure preparation strategies recorded in the form of documents to carry out refueling. Since the procedure is decided, the workload of the person in charge is extremely large, it is not possible to achieve sufficient efficiency due to the time constraints of work and the size and complexity of work, and the created work procedure is also very efficient. Was not.

The present invention has been made in response to such conventional circumstances,
An object of the present invention is to provide a refueling plan creation support device that reduces the work load on a refueling planner and enables the creation of a safe and efficient refueling procedure.

[Configuration of the Invention] (Means for Solving the Problems) That is, the fuel exchange plan creation support apparatus of the present invention is a fuel database that stores the initial fuel arrangement of the core, the target fuel arrangement, and the nuclear data of the target fuel, and the target. Working environment database containing core structure and fuel pool structure data of a nuclear reactor, data in the fuel database and the working environment database, fuel arrangement information created based on these data, and input core-related Means for creating a refueling work target by work, a refueling work knowledge base that stores data relating to constraint conditions for refueling work and rules for creating procedures, data stored in this refueling work knowledge base, and the fuel In order to perform core-related work based on the replacement work target, create a fuel allocation target that should be realized in the refueling process. Means, a means for creating a fuel exchange work procedure that realizes the fuel placement target based on the fuel placement target and the data stored in the fuel exchange work knowledge base, and a means for outputting the fuel exchange procedure. It is characterized by having.

(Operation) In the refueling plan preparation supporting apparatus of the present invention having the above-described configuration, as shown in FIG. 1, the refueling plan person in charge basically needs the refueling work target indicating mechanism 3 to perform the necessary operation. Various fuel exchange operations are instructed and input, and the output display mechanism 7 receives information on the created fuel exchange procedure. That is, first, the fuel arrangement information 101 is created based on the information in the fuel database 1 and the work environment database 2. The refueling work target instruction mechanism 3 presents the fuel arrangement information 101 to the user mainly regarding the arrangement state of the control rods, in-core neutron detectors and fuel, and receives the input instruction of the core-related work target 102. The fuel replacement work target designating mechanism 3 uses the fuel arrangement information.
101 and the core-related work target 102, and the information of the fuel database 1 and the work environment database 2 necessary for the fuel refueling work plan creation are integrated, and the refueling work target 103
To create. The fuel placement target creation mechanism 5 creates a fuel placement target 104 to be realized in the refueling process in order to perform core-related work, based on the fuel replacement work knowledge base 4 and the fuel replacement work target 103. The refueling procedure creation mechanism 6 creates a refueling operation procedure 105 that realizes the refueling operation knowledge base 4 and the fuel placement target 104 based on the refueling operation knowledge base 4.
The output display mechanism 7 outputs the created fuel exchange procedure 105. In this way, a refueling procedure is established to build the final target core fuel arrangement so that the designated core-related work can be performed on the refueling work process.

(Example) Hereinafter, the Example of this invention is described with reference to drawings.

FIG. 2 shows the basic configuration of the first embodiment of the present invention. First, in the first embodiment of the present invention, a fuel database 1 and a work environment database 2 are prepared corresponding to the reactors and the periodic inspections that are the targets of the refueling plan. The information contained in Fuel Database 1 is:
That is, the fuel arrangement at the end of the previous operation cycle (EOC),
At the end of periodic inspection, that is, at the start of the next operation cycle (BO
There is fuel arrangement of C), fuel arrangement of fuel pool at the start of regular inspection, arrangement of DBG and dummy bundle. Also, E
Nuclear data for all fuels included in the OC and BOC fuel arrangements are provided for each fuel identifier. The information in the fuel database 1 is information that is considered to change at each periodic inspection even for the same nuclear reactor. The information contained in the work environment database 2 relates to the shapes of the core and the fuel pool and defines where the fuel, DBG and dummy bundles can be moved and installed. In addition, the installation location of the core neutron detector and control rod will be defined. The information in the work environment database 2 does not change at each periodic inspection, but it changes depending on the target nuclear reactor. First, EOC and BOC fuel arrangement information 101 is created based on the information in the fuel database 1 and the work environment database 2.

The fuel exchange work target indicating mechanism 3 is composed of an indicating device such as a CRT 8 and a mouse 9, and by using the CRT 8, EOC fuel arrangement information 101, that is, control rods, in-reactor neutron detectors and arrangement of fuels. The situation is graphically displayed and presented to the user, and the core-related work target 102 is input using the indicating device. A specific example of the input of the core-related work target 102 in the refueling work target designating mechanism 3 will be described with reference to FIG. CRT
At 8, fuel allocation information 101 of EOC is displayed. In this display, the control rod 201, in-core neutron detector 202 and fuel
203 is displayed as a symbol. These positional relationships are
It is managed in Cartesian coordinates used in process computers. Since the control rod 201 and the in-core neutron detector 202 are fixed inside the reactor, they can be specified by this coordinate system. Fuel 203
Since it moves within the core or within the fuel pool, an identifier is assigned to each fuel for management purposes.
As for core related work, for control rod 201, there are control rod replacement and control rod drive system inspection, and in-core neutron detector 202
With regard to (2), replacement of fuel is considered, and with regard to fuel 203, there are exposure reduction measures for in-service inspection or fuel removal for visual inspection.

The core-related work may be specified by specifying the individual work target and the work type. The mouse cursor 204 is the mouse 9
Move on the screen according to the movement of. When the button of the mouse 9 is operated while the mouse cursor 204 is over the core-related work target, possible core-related work is displayed as a menu according to the type of the work target. By selecting the work item to be performed from the menu, the designation of one core-related work is completed. By repeating this operation a required number of times, the input instruction of the core-related work target 102 is completed.

As described above, since the core-related work target 102 is designated, the target to be achieved in the refueling work is determined. The fuel exchange work target instruction mechanism 3 prepares a fuel exchange work plan such as fuel arrangement information 101, core-related work targets 102, fuel nuclear data of the fuel database 1, core structure data of the work environment database 2, and fuel pool structure data. The necessary information is integrated to create the refueling work target 103.

Next, the fuel placement target creation mechanism 5 is based on the fuel exchange work knowledge base 4 and the fuel exchange work target 103, and the fuel placement target 10 to be realized in the fuel exchange process in order to perform core-related work.
Create 4. Here, the main knowledge used from the refueling work knowledge base 4 is as follows.

How to take out the fuel that should be taken out corresponding to the core-related work (number and layout).

Relationship between fuel extraction and control rod support.

Terms of use for DBG.

Usage conditions for dummy bundles.

Constraints on fuel extraction around the neutron source region monitor.

A rule (meta-rule) that defines the procedure for determining the fuel to be taken out.

The refueling work knowledge base 4 normally applies the determined knowledge as it is, but should be modified in order to improve the efficiency of the processing procedure when there is a change in the constraint condition due to the improvement of the combination of the regular inspection process or the like. Is possible. Fuel placement goals
104 is a fuel arrangement that should be realized between the EOC fuel arrangement and the BOC fuel arrangement. In the current periodic inspection process, core related work is performed collectively between the process of only taking out the fuel and the process of loading / rearranging during the refueling work process. , The fuel allocation target 104. Split some core-related work,
In order to be parallel to the refueling work, multiple states of fuel placement targets 104 are required.

Next, the refueling procedure creation mechanism 6 creates a refueling operation procedure 105 that realizes this, based on the refueling operation knowledge base 4 and the fuel placement target 104. Here, the main knowledge used from the refueling work knowledge base 4 is as follows.

Evaluation model of reactor shutdown margin and constraints on reactor shutdown margin.

Relationship between fuel extraction / loading and control rod support.

A rule that requires a procedure for taking out fuel.

A rule that defines the fuel relocation procedure.

A rule that defines the fuel loading procedure.

DBG Terms and Conditions of Use.

Rules for use conditions and usage of dummy bundles.

Rules for fuel pool usage conditions and usage.

A rule (meta-rule) that defines the procedure for determining the refueling work procedure.

The reactor shutdown margin is a constraint condition that should always be satisfied during the refueling work process, and when the fuel exchange work procedure is sequentially selected, an intermediate fuel arrangement corresponding to this is created, and the reactor shutdown margin evaluation mechanism is used. Evaluate with 10. When the evaluated reactor shutdown margin does not satisfy the limit value shown in the fuel exchange work knowledge base 4, the reactor shutdown margin is secured by selecting another fuel exchange operation procedure. If the reactor shutdown margin cannot be secured even if the work procedure is improved in this way, the process returns to the fuel placement target creation mechanism 5 to create another fuel placement target 104 that satisfies the fuel exchange work target 103, and Redo the selection. Regarding other constraint conditions prepared in Knowledge Base 4,
If not satisfied, another work procedure is selected as well as the reactor shutdown margin. From the EOC fuel allocation, through the fuel allocation target 104, all the steps leading to the BOC fuel allocation can be selected,
Creation of the fuel change procedure 105 is completed.

The output display mechanism 7 outputs the created fuel exchange procedure 105 to the CRT 8 or the printer 11 in a predetermined format.
An example of the procedure format is shown in FIG. In the fuel transfer format example, the step number, fuel identifier, transfer start position and orientation,
The movement end position and direction, and the evaluation value of the reactor shutdown margin, etc. are recorded as remarks. Created refueling procedure 105
Is usually an instruction to move the fuel, DBG, dummy bundle, and insert / pull out the control rod in hundreds to 2000 steps. The output display mechanism 7 creates the fuel arrangement 106 of the core in each step and displays it on the CRT 8 corresponding to the fuel exchange procedure so that the user can easily confirm the produced fuel exchange procedure 105. FIG. 5 shows a display example of the fuel change procedure and the fuel arrangement. Move the mouse cursor 204 to the operation instruction area 205
When you move the button to the mouse 9 and operate the button of the mouse 9, depending on the location, at the start of core related work for EOC, BOC, and intermediate targets, the previous step and the next step of the currently displayed step, or the core arrangement of the specified step number Then, the fuel exchange procedure 105 of several tens of steps before and after the work step is displayed.

That is, according to the fuel exchange plan creation support device of this embodiment, a user who is going to create a fuel exchange plan automatically creates an appropriate fuel exchange procedure simply by making a simple input regarding core-related work. However, since the preparation result can be easily confirmed, the work load of the fuel exchange preparation work can be significantly reduced.

Further, in this embodiment, the fuel exchange procedure satisfying the limit value is selected while evaluating the reactor shutdown margin during the fuel exchange work, so that the criticality control of the core can be surely performed and the efficiency is ensured while ensuring the safety. You can select a specific work procedure and provide it to the user.

In addition, in the above-mentioned embodiment, the input instruction of the core-related work is configured to be performed by the mouse. It is also possible to specify the work target by inputting, and these instruction devices may be used together. Further, although the structural data of each nuclear power plant can be modified as the work environment database 2, the refueling work target designating mechanism 3, the fuel placement target creating mechanism 5, the refueling procedure creating mechanism 6, and the output display mechanism 7 can be modified. It is also possible to incorporate information into a device dedicated to a specific nuclear power plant. Further, it is possible to provide an online system to which a mechanism for processing the output of the process computer for reactor operation management and automatically creating a database is connected. It is also possible to display a knowledge of the refueling work knowledge base 4 in a form that is easy for the user to understand and add a mechanism that can be modified according to the purpose of the user.

Next, a second embodiment will be described with reference to FIG.

In the second embodiment, in addition to the structure of the first embodiment, a fuel placement target correction mechanism 12 is placed. The fuel placement target modification mechanism 12 displays the fuel placement target 104 created by the fuel exchange work target designating mechanism 3 on the CRT 8 and allows the user to modify the fuel placement target 104 using a pointing device such as the mouse 9. The fuel arrangement status and control rod and reactor neutron detector states are graphically displayed to the user.

That is, as shown in FIG.
The fuel placement target 104 is displayed. In this display, control rod 2
01, in-core neutron detector 202 and fuel 203 are symbolically displayed. The mouse cursor 204 moves on the screen according to the movement of the mouse 9. When the mouse cursor 204 is over the object that is the core-related work, the work content is displayed in the information display area 206. Further, when the button operation of the mouse 9 is performed on the graphic display of the fuel arrangement, possible arrangement target correction items 207 are displayed as a menu according to the type of the cursor position. At the fuel position, the fuel is taken out. At the place where the fuel has already been taken out, it is possible to load the taken-out fuel or set a dummy bundle. It is possible to insert / pull out and set / remove the DBG that supports the control rod. There is no correction operation at the position of the neutron detector in the reactor. In this way, the fuel placement target 104 is modified according to the user's purpose. In the process of this correction, if the work area for core related work cannot be secured or the control rod support cannot be secured, a warning message to that effect is displayed in the information display area, causing a problem. By changing the display state of the target object or area, the user is alerted. When the user gives an instruction to end the correction without sufficiently performing the correction operation corresponding to the warning, the user is prompted to select one from the following processes.

Returning to the fuel exchange work target instruction mechanism 3, the core-related work target is corrected.

Fuel allocation target correction mechanism for correction operation to supplement user's operation
12 automatically.

The user continues the correction work.

And fuel placement goals modified according to user objectives
Based on 104, the fuel exchange procedure creation mechanism 6 creates a fuel exchange work target 105, and the output display mechanism 7 outputs this fuel exchange procedure 105.

That is, according to the second embodiment, the user can confirm the fuel arrangement state for core-related work, and it is possible to appropriately change the fuel arrangement state according to the purpose of the user. It is possible to create a refueling procedure that meets the requirements.
In addition, it is possible to explain in detail to the user the reason for fuel extraction, etc. regarding the fuel arrangement state created for core-related work, so even those who are inexperienced in refueling work plans can understand it. Information can be easily presented, and reasons for fuel refueling work planning can be presented so that even experienced people can easily accept the information.

It should be noted that in the fuel placement target modification mechanism 12, a plurality of fuel placement targets can be modified, and in this case, the other fuel placement targets are automatically modified in association with the modification of one fuel placement target. May be. Further, the fuel allocation target and the reason for selecting the fuel allocation target may be output to the printer 11, or the created fuel exchange procedure may be divided and output for each fuel allocation target. Further, in the second embodiment, the instruction for the fuel arrangement in the fuel pool and the fuel arrangement target are not created, but it is natural that the fuel arrangement target is automatically created and corrected like the fuel arrangement in the core. It is possible. In this case, instead of giving instructions on the details of individual fuel arrangements, the area of the fuel pool is divided into several areas, for unloading fuel, for relocation fuel, for new fuel, for recycle fuel in the previous cycle, or for work. It is also possible to determine the specific fuel arrangement by the fuel arrangement target creation mechanism only by designating the purpose of use such as use.

Next, a third embodiment of the present invention will be described with reference to FIG.

In the third embodiment, in addition to the structure of the second embodiment, a fuel exchange procedure search mechanism 13 is arranged, and it is possible to change the fuel exchange procedure.

In re-creating the refueling work procedure, there is a demand to change the refueling procedure for a specific fuel. Specifically, if the work of taking out, loading, or rearranging a specific fuel is defined in the work procedure, the work order is changed and this fuel transfer work is performed in the front or back depending on the created procedure. It is conceivable that you want to move to another work section in. As mentioned above, the refueling procedure is
In some cases, it takes over 1000 steps, so it is not efficient to search the procedure from the beginning. Therefore, by specifying the fuel identification name, the fuel exchange procedure search mechanism 13 searches for the fuel exchange work for this fuel.

A specific example of the operation in the refueling procedure search mechanism 13 will be described with reference to FIG. The CRT 8, mouse 9 and keyboard 14 are connected to the fuel exchange procedure search mechanism 13 via the output display mechanism 7. A fuel change procedure 105 and a fuel arrangement 106 corresponding to the fuel change procedure 105 are displayed on the CRT 8. In this display, the control rod 201, the in-core neutron detector 202 and the fuel 203 are symbolically displayed. The mouse cursor 204 moves on the screen according to the movement of the mouse 9. When the mouse cursor 204 is over the fuel, the fuel identification name is displayed in the information display area 206. Further, when the button operation of the mouse 9 is performed on the graphic display of the fuel arrangement 106, the work procedure search item 208 is displayed as a menu. The contents of the work procedure search item 208 include, for example, extraction, loading, rearrangement,
There are four unknown items, and if instructed to be unknown,
Steps corresponding to the fuel identification name are sequentially found from the beginning of the work procedure. For other item selections, only the step corresponding to the content is searched. Since the information of the work procedure 105 always includes the fuel identification name and the work content, it is easy to specify the step to be searched. Normally, the fuel that appears in the refueling operation procedure is included in the fuel arrangement of EOC or the fuel arrangement of BOC, so if either of these fuel arrangements is displayed as fuel arrangement 106, Although it is possible to search the step by designating the fuel, when the fuel arrangement 106 is in the state of refueling, it is considered that the fuel to be noticed is not displayed. Also, in large reactors, the number of fuel units is more than 700,
It may be difficult to find even if the fuel of interest is displayed. In such a case, the keyboard 14 can be used to directly input the fuel identification name. By using the fuel identification name input means together, the target fuel exchange procedure can be searched quickly and easily. When the search for the target refueling procedure is completed, the work procedure correction item 209 is displayed on the CRT 8 as a menu. The contents of the work procedure correction item 209 are, for example, move to the previous step and move to the subsequent step, and after each selection, the user selects from the target moving range and the movable range. To specify the movement range,
The step number may be input from the keyboard 14, but if the moving range is represented by a bar graph, it is possible to specify easily and quickly by using the mouse 9 together.

By repeating the operation in the fuel exchange procedure search mechanism 13 described above, the procedure creation constraint condition 107 that limits the execution range of a plurality of sets of fuel exchange work is created.

When the fuel exchange procedure retrieval mechanism 13 corrects the fuel exchange procedure, the fuel exchange procedure creation mechanism 6
The procedure preparation constraint 107 is sent to the fuel allocation target 104, the information on the fuel exchange work knowledge base 4, and the procedure preparation constraint 107.
The refueling procedure 105 is recreated based on The created fuel exchange procedure 105 is confirmed again by the user on the output display device 7, and the modification of the fuel exchange procedure is repeated until the purpose of the user is satisfied.

According to the third embodiment described above, the user can appropriately change the fuel work procedure as necessary, so that it is possible to create a work procedure more suited to the user's purpose. In addition, with regard to refueling work plans, it is possible to carry out planning methods that are in line with the methods that have been used by those skilled in the work of preparing fuel refueling plans up to now, so it is possible to apply it to people with little work experience in an educational manner. Can contribute to training.

In the third embodiment, the fuel exchange procedure created in advance may be temporarily recorded in the database, and the fuel exchange procedure may be read and corrected later.
In this case, a plurality of changed and prepared fuel exchange procedures may be held in the database so that they can be simultaneously displayed on the output display mechanism for comparison. It is also possible to display changes in the fuel loading rate, control rod insertion rate, and changes in the reactor shutdown margin evaluation value, which is a constraint condition, in the output display mechanism during the refueling work process. By designating the change graph display of the parameter of interest during the process with a pointing device such as a mouse, it is possible to call up information on a specific step in the fuel operation process and the fuel arrangement corresponding thereto. Further, in the third embodiment, although the constraint condition of the reactor shutdown margin is not changed in the fuel exchange procedure correction mechanism 13, the constraint condition of the reactor shutdown margin is worked in the same manner as the constraint condition for the range of the fuel exchange procedure. It is naturally possible to modify the procedure and include it in the procedure creation constraint condition, and reconfigure the procedure by the fuel exchange procedure creation mechanism.

[Effects of the Invention] As described above, according to the present invention, it is possible to reduce the work load on the person in charge of refueling planning and support the creation of a safe and efficient refueling procedure. Further, by changing the database of fuel and work environment, it can be easily applied to the fuel exchange work of another regular inspection process or the regular inspection process of another nuclear reactor.

The present invention uses the initial fuel arrangement of the core, the target fuel arrangement, and the nuclear data of the target fuel, which have been conventionally used as the fuel exchange plan preparation information, as the input information as in the conventional case, and the remaining necessary information is , Uses the information in the mind of the planner or in a different form of documented information.
Based on this information, most of the work of the planner can be taken over. Therefore, it is easy to apply the present invention to the conventional refueling plan preparation work. Further, the user of the present invention can create a fuel exchange procedure in a required format with a simple operation even if he / she is not particularly proficient in the fuel exchange work planning work. Even the person in charge can assist the work of a skilled person.

[Brief description of drawings]

FIG. 1 is a diagram showing a basic configuration of the present invention, FIG. 2 is a configuration diagram showing a first embodiment of the present invention, and FIG. 3 shows an operation of a fuel exchange work target indicating mechanism of the first embodiment. FIG. 4, FIG. 4 is a view showing an output format of the fuel exchange procedure of the first embodiment, FIG. 5 is a view showing a CRT display by the output display mechanism of the first embodiment, and FIG. 6 is a view of the present invention. FIG. 7 is a diagram showing the basic configuration of the second embodiment, FIG. 7 is a diagram showing the operation of the fuel placement target correction mechanism of the second embodiment, and FIG. 8 is a diagram showing the basic configuration of the third embodiment of the present invention. FIG. 9 and FIG. 9 are diagrams showing the operation of the fuel exchange procedure search mechanism of the third embodiment. 1 ... Fuel database 2 ... Work environment database 3 ... Refueling work target instruction mechanism 4 ... Fuel replacement work knowledge base 5 ... Fuel placement target creation mechanism 6 ... Fuel replacement procedure creation mechanism 7 ... Output display mechanism 101 …… Fuel placement information 102 …… Core-related work target 103 …… Refueling work target 104 …… Fuel placement target 105 …… Fuel replacement work procedure

Claims (1)

[Claims] 1. A fuel database containing initial nuclear fuel allocation, target fuel allocation, and nuclear data of target fuels, a working environment database containing core structure and fuel pool structure data of a target reactor, and the fuel. A means for creating a fuel replacement work target by the data in the database and the work environment database, the fuel arrangement information created based on these data, and the input core-related work, and the constraint condition and the procedure creation of the fuel replacement work. Refueling work knowledge base that contains data related to rules, and fuel allocation target that should be realized in the refueling process in order to perform core-related work based on the data stored in this refueling work knowledge base and the refueling work target And the fuel placement goals and the data contained in the refueling knowledge base. Refueling plan preparation supporting apparatus characterized by comprising means for creating a refueling operation procedure for realizing the fuel placement targets, and means for outputting the refueling procedure based on.