KR102105037B1 - Apparatus and method for analyzing crud in a nuclear reator - Google Patents

Abstract

The reactor crud analysis apparatus of the present invention includes an output measuring unit configured to measure the output of the fuel assembly in the reactor for each operation cycle of the reactor, and based on the output of the fuel assembly in the immediately preceding operation cycle for each operation cycle. It may include a crud analysis unit for analyzing the crud information in the nuclear reactor, and an operation condition setting unit for setting the operating conditions of the nuclear reactor in the next operation cycle for the fuel assembly using the crud information.

Description

Reactor Cradle Analysis Device and Method {APPARATUS AND METHOD FOR ANALYZING CRUD IN A NUCLEAR REATOR}

The present invention relates to a reactor river (Chalk River Unidentified Deposit, CRUD), in particular, modeling and modeling the information in the reactor based on the output of the reactor due to the combustion of the fuel assembly in the immediately preceding operating cycle during operation of the reactor. It relates to an apparatus and method for analyzing the reactor crud so as to increase the operating efficiency of the reactor by setting the operating conditions of the next operating cycle of the reactor based on the obtained information of the crud.

In general, in order to increase the economical efficiency of a pressurized water reactor type (PWR), long cycle, high power, high combustion operation is performed, and the amount of corrosion on the surface of the nuclear fuel cladding and the adhesion of the corrosion product, the crud, are increasing. , There is a problem that the output of the reactor is reduced.

Axial offset anomaly (AOA) is a phenomenon defined when the output distribution difference between the upper and lower parts of the fuel assembly in the reactor, that is, the axial output (Axial offset) deviates by more than 3% from the expected output distribution difference. As a representative phenomenon of the crust attached to the surface of the nuclear fuel assembly is known as the main cause.

Therefore, it is necessary to predict and minimize the generation of the above-mentioned crust, but it is difficult to accurately analyze the nuclear reactor because it is impossible to analyze the amount of crust generated in the reactor and the material distribution of the crust at the current technology level. The problem of output reduction has not been solved.

(Patent literature)

Republic of Korea Patent Publication No. 10-2018-0035725 (published on April 06, 2018)

Accordingly, in one embodiment of the present invention, when the reactor is operated, modeling of the information in the reactor based on the output of the reactor according to the combustion of the nuclear fuel assembly in the immediately preceding operating cycle, and the next operation of the reactor based on the modeled information It is an object of the present invention to provide an apparatus and method for analyzing a reactor crud that can increase a reactor operating efficiency by setting operating conditions of a cycle.

An apparatus for analyzing a nuclear reactor crud according to an embodiment of the present invention as described above, an output measuring unit configured to measure the output of the fuel assembly in the nuclear reactor for each operating cycle of the nuclear reactor, and the nuclear fuel in the immediately preceding operating cycle for each operating cycle Includes a crud analysis unit that analyzes the crud information in the reactor based on the output of the assembly, and a driving condition setting unit that sets the operating conditions of the nuclear reactor in the next operation cycle for the nuclear fuel assembly using the crud information do.

In addition, the output of the fuel assembly is an axial output distribution signal (ASI), and the crud analysis unit analyzes the crud information, based on the axial output distribution signal, based on the axial output distribution signal. It is characterized by predicting the amount and the concentration of boron contained in the crad.

In addition, the crust analysis unit generates a basic axial output distribution signal in the environment without the crust, and the axial output distribution value at each combustion time point for the fuel assembly on the basic axial output distribution signal is the axis. It is characterized by predicting the amount of the crust and the concentration of the boron to converge as much as possible on the axial output distribution value at each combustion point on the direction output distribution signal.

In addition, the operating condition setting unit is characterized in that for setting the operating conditions of the reactor in the next operating cycle based on the predicted amount of the crud in the reactor and the concentration value of the boron.

In addition, as a method for analyzing a nuclear reactor crud according to an embodiment of the present invention, measuring the output of the nuclear fuel assembly in the nuclear reactor for each operation cycle of the nuclear reactor, and the nuclear fuel assembly in the immediately preceding operation cycle for each operation cycle And analyzing crud information in the reactor based on an output, and setting operating conditions of the nuclear reactor in a next operation cycle for the nuclear fuel assembly using the crud information.

In addition, the output of the fuel assembly is an axial output distribution signal (ASI), and the analyzing step is based on the axial output distribution signal and the amount of crust generated in the reactor and the boron contained in the crust. It is characterized in that it is a step of predicting the concentration.

In addition, the step of predicting, generating a basic axial output distribution signal in the environment without the crust, and the axial output distribution value at each combustion time point for the fuel assembly on the basic axial output distribution signal And estimating the amount of the crust and the concentration of the boron to converge as much as possible on the axial output distribution value at each combustion point on the axial output distribution signal.

In addition, the step of setting the operating condition is characterized in that it is a step of setting the operating condition of the reactor in the next operation cycle based on the predicted amount of the crud in the reactor and the concentration value of the boron.

According to an embodiment of the present invention, in the analysis of the intra-reactor crust, the intra-reactor information is modeled based on the output of the nuclear reactor according to the combustion of the nuclear fuel assembly in the immediately preceding operating cycle during operation of the nuclear reactor, and the modeled crust Based on the information, it is possible to increase the operating efficiency of the reactor by setting the operating conditions of the next operating cycle of the reactor.

1 is a detailed block diagram of a reactor crud analysis apparatus according to an embodiment of the present invention.
2 is an exemplary graph of an axial output distribution signal under various conditions according to an embodiment of the present invention.
Figure 3 is an exemplary view of the appearance of the generation of crust on the nuclear fuel assembly according to an embodiment of the present invention.
Figure 4 is a flow chart of the operation control in the reactor crude analysis apparatus according to an embodiment of the present invention.

Hereinafter, the operating principle of the present invention will be described in detail with reference to the accompanying drawings. In the following description of the present invention, when it is determined that a detailed description of known functions or configurations may unnecessarily obscure the subject matter of the present invention, the detailed description will be omitted. In addition, terms to be described later are terms defined in consideration of functions in the present invention, which may vary according to a user's or operator's intention or practice. Therefore, the definition should be made based on the contents throughout this specification.

1 shows a detailed block configuration of an apparatus for analyzing a reactor crud according to an embodiment of the present invention.

First, the pressurized water reactor 100 may be formed of a cylinder-shaped pressure vessel.

A nuclear reactor core 102 in which nuclear fuel rods are loaded is located inside the reactor 100. At this time, the nuclear fuel assembly 102 is composed of a plurality of nuclear fuel rods (fissilematerial), is located in the lower portion of the nuclear reactor 100 may be implemented in a state generally contained in cooling water such as light water (H2O).

The central vertical tube (cylindricalcentralriser) 104 is disposed, for example, in a concentric circle inside the reactor 100, and allows the cooling water heated by the nuclear fuel assembly 102 to be moved to the upper portion of the pressure vessel 100.

The steam generator 106 is formed to surround the central vertical tube 104 between the lower space 110 and the upper space 112 inside the reactor 100.

The steam generator 106 includes a plurality of tubes 108, and each tube 108 is formed to move coolant from the upper space 112 of the reactor 100 to the lower space 110. Therefore, when the operation of the nuclear fuel assembly 102 is started, the cooling water heated by the nuclear fuel assembly 102 is moved to the upper portion of the reactor 100 through the central vertical tube 104, and to the upper portion of the nuclear reactor 100 The cooled water can be transferred to the bottom of the reactor 100 through the tube 108 of the steam generator 106 again. Accordingly, power is generated by generating heated steam as steam through the tube 108 and applying it to a turbine (not shown) outside the reactor 100.

Next, the nuclear reactor crud analysis apparatus 150 according to an embodiment of the present invention analyzes crud information generated by combustion in the nuclear fuel assembly 102 in the nuclear reactor as described above. As illustrated in FIG. 1, the crud analysis apparatus 150 may include an output measurement unit 152, a crud analysis unit 154, an operation condition setting unit 156, and the like.

The output measuring unit 152 measures the output of the nuclear reactor 100 generated by combustion of the nuclear fuel assembly 102 for each operation cycle.

At this time, for example, if the use period of the nuclear fuel assembly 102 is 3 years and each operation cycle of the nuclear reactor 100 is 1 year, the entire operating cycle of the nuclear fuel assembly 102 may be 3 operating cycles.

In addition, the output of the reactor measured from the output measurement unit 152 may be, for example, an axial output distribution signal (Axial shape index: ASI) as in FIG. 2, but is not limited thereto.

At this time, the axial output distribution signal as above can be calculated as in [Equation 1] below, and if the value of the axial output distribution signal is "+", the lower side of the fuel assembly 102 is burned a lot. If it is indicated and "-", it may mean that the upper side of the nuclear fuel assembly is burned a lot.

Referring to FIG. 2, the basic axial output distribution signal 200 in a no-clud environment is a fuel assembly 102 on the axial output distribution signal because the upper and lower portions of the fuel assembly 102 in the reactor 100 are burned evenly. It can be seen that the axial output distribution value at each burnup of) is formed near "0".

However, when the reactor 100 is actually operated, referring to the axial output distribution signal 204 actually measured as a crust is generated in the reactor 100 according to the combustion of the nuclear fuel assembly 102, the axial output distribution The axial output distribution value at each burnup of the fuel assembly 102 on the signal 204 is + or ?? It can be seen that a large variation occurs in the direction.

That is, referring to the axial output distribution signal 204 that is actually measured in the nuclear reactor 100, the fuel assembly 102 has a "-" value at the beginning of combustion and then "+" as the combustion of the fuel assembly 102 progresses. It can be seen that after changing to a value, it is changed to a "-" value again. The reason why the axial output distribution value is changed as described above is because the fuel assembly 102 is burned by the crust generated by combustion of the fuel assembly 102, the upper part is burned more and then the lower part is burned. Because it burns more.

The crud analysis unit 154, based on the output of the fuel assembly 102 in the immediately preceding operation cycle among the outputs of each of the reactors 100 provided from the output measurement unit 152, corresponds to the corresponding reactor 100 ) Model the crust information that is expected to exist.

At this time, the crad information may mean information on the amount of the crust generated according to one operating cycle of the nuclear fuel assembly 102 and the material distribution information in the crad, and the material distribution information may be a value of boron concentration in the crad. It may mean, but is not limited to.

In addition, the crud analysis unit 154 in performing the above-described crud modeling, the fuel assembly 102 as shown in Figure 3 shows the shape (Axial shape of crud) occurs on the fuel assembly 102. ), It is assumed that a large amount of crud occurs in the upper axial direction, and the amount of crud in the reactor 100 is predicted from the assumed crud generating shape. In addition, by using the axial output distribution signal, which is the output of the fuel assembly 102, modeling of the crud information is performed by predicting number density of boron in crud, which is one of the material distribution information in the crud, and the like.

)에 대해서는 아래의 수학식 2에서와 같이 예측할 수 있다.At this time, the crad analysis unit 154 is the concentration of boron, which is one of the material distribution information in the crad (

) Can be predicted as in Equation 2 below.

In [Equation 2] above, n denotes a burnup step, and i denotes an XS update index.

)상 핵연료 집합체(102)에 대한 각 연소 시점에서의 축방향 출력 분포 값과 실제 측정된 축방향 출력 분포 신호(

)상 핵연료 집합체(102)에 대한 각 연소 시점에서의 축방향 출력 분포 값을 비교한다.That is, in predicting the concentration of boron in the crad through the above [Equation 2], the crad analysis unit 154 may include, for example, a basic axial output distribution signal in an environment without a crud (

) Axial output distribution value and actual measured axial output distribution signal at each combustion point for the phase fuel assembly 102 (

) Compare the axial power distribution values at each combustion time point for the phase fuel assembly 102.

)상 핵연료 집합체(102)에 대한 각 연소 시점에서의 축방향 출력 분포 값이 실제 측정된 축방향 출력 분포 신호(

)상 핵연료 집합체(102)에 대한 각 연소 시점에서의 축방향 출력 분포 값에 최대한 수렴하도록 하는 크러드의 양과 보론의 농도를 예측한다.Subsequently, the crud analysis unit 154 may include a basic axial output distribution signal (

) Axial output distribution signal in which the axial output distribution value at each combustion time for the phased fuel assembly 102 is actually measured (

) Predict the amount of crust and the concentration of boron to maximize convergence to the axial power distribution value at each combustion time for the phase fuel assembly 102.

At this time, when the axial output distribution signal is generated using the predicted amount of the crud and the concentration of boron, modeling is possible similar to the actual measured axial output distribution signal as shown in FIG. 2.

The operating condition setting unit 156 predicts the material distribution information in the nuclear reactor 100 using the crud information modeled through the crud analysis unit 154, and based on the predicted material distribution information, the reactor of the next operating cycle Set the operating conditions of (100).

At this time, the material distribution in the nuclear reactor means the distribution of the material in the nuclear reactor 100 that has changed since the fuel assembly 102 was burned in the nuclear reactor 100 in the immediately preceding operating cycle, and this material distribution is of the nuclear fuel assembly 102. It may mean the amount of crust generated in the reactor 100 after combustion and the concentration value of boron contained in the crust. In addition, the operating conditions may mean conditions for operating the reactor 100 on which the nuclear fuel assembly 102 is mounted, and such operating conditions may be a dose of boron in the reactor 100, a temperature of water, and the like.

That is, the driving condition setting unit 156 is the amount of boron to be administered to the nuclear reactor 100 in the next driving cycle based on the predicted amount of the crud and the concentration value of boron in the crud in the previous operating cycle. It is possible to set the operating conditions such as adjusting the temperature appropriately or adjusting the water temperature.

4 is a flowchart illustrating an operation control flow in an apparatus for analyzing a reactor crud according to an embodiment of the present invention. Hereinafter, an embodiment of the present invention will be described in detail with reference to FIGS. 1 to 4.

The crud analysis apparatus 150 measures the output of the nuclear reactor 100 generated by combustion of the nuclear fuel assembly 102 for each operation cycle (S400). At this time, the output of the reactor may be, for example, an axial output distribution signal (Axial shape index: ASI) as shown in FIG. 2.

Subsequently, the crud analysis apparatus 150 is a reactor corresponding to the corresponding output based on the output of the nuclear fuel assembly 102 in the immediately preceding operating cycle among the output of each operating cycle of the reactor 100 provided from the output measuring unit 152. Models the crud information expected to exist in (100) (S402).

At this time, the crad information may mean information on the amount of the crust generated according to one operating cycle of the nuclear fuel assembly 102 and the material distribution information in the crad, and the material distribution information may be a value of boron concentration in the crad. Can mean

That is, in performing the above-described modeling of the crud information, the crud analysis apparatus 150 shows the shape of a fuel on the nuclear fuel assembly 102 (Axial shape of crud), as shown in FIG. 3. It is assumed that a large amount of crud occurs in the axial upper side of 102), and the amount of crud in the reactor 100 is predicted from the assumed crud-generating shape. In addition, by using the axial output distribution signal, which is the output of the fuel assembly 102, modeling of the crud information is performed by predicting number density of boron in crud, which is one of the material distribution information in the crud, and the like.

Subsequently, the crud analysis apparatus 150 predicts the material distribution information in the nuclear reactor 100 after the previous operation cycle is completed using the modeled crust information based on the output of the nuclear fuel assembly, and based on the predicted material distribution information By setting the operating conditions of the reactor 100 of the next operation cycle (S404).

At this time, the material distribution in the nuclear reactor means the distribution of the material in the nuclear reactor 100 that has changed since the fuel assembly 102 was burned in the nuclear reactor 100 in the immediately preceding operating cycle, and this material distribution is of the nuclear fuel assembly 102. It may mean the amount of crust generated in the reactor 100 after combustion and the concentration value of boron contained in the crust. In addition, the operating conditions may mean conditions for operating the reactor 100 on which the nuclear fuel assembly 102 is mounted, and such operating conditions may be a dose of boron in the reactor 100, a temperature of water, and the like.

As described above, according to an embodiment of the present invention, in the analysis of the intra-reactor crust, the intra-reactor crust information is modeled based on the output of the nuclear reactor according to the combustion of the nuclear fuel assembly in the immediately preceding operating cycle during operation of the nuclear reactor, Based on the modeled crud information, it is possible to increase the operating efficiency of the reactor by setting the operating conditions of the next operating cycle of the reactor.

Combinations of each step of each flowchart attached to the present invention may be performed by computer program instructions. These computer program instructions can be mounted on a processor of a general purpose computer, special purpose computer, or other programmable data processing equipment, so that the instructions executed through the processor of a computer or other programmable data processing equipment are described in each step of the flowchart. It creates a means to do them. These computer program instructions can also be stored in computer readable or computer readable memory that can be oriented to a computer or other programmable data processing equipment to implement a function in a particular manner, so that computer readable or computer readable memory It is also possible for the instructions stored in to produce an article of manufacture containing instructions means for performing the functions described in each step of the flowchart. Since computer program instructions may be mounted on a computer or other programmable data processing equipment, a series of operational steps are performed on the computer or other programmable data processing equipment to create a process that is executed by the computer to generate a computer or other programmable data. It is also possible for instructions to perform processing equipment to provide steps for executing the functions described in each step of the flowchart.

In addition, each step may represent a module, segment, or portion of code that includes one or more executable instructions for executing the specified logical function (s). It should also be noted that in some alternative embodiments it is also possible that the functions mentioned in the steps occur out of order. For example, the two steps shown in succession may in fact be performed substantially simultaneously, or it is also possible that the steps are sometimes performed in reverse order depending on the corresponding function.

Meanwhile, in the above description of the present invention, specific embodiments have been described, but various modifications may be made without departing from the scope of the present invention. Therefore, the scope of the invention should not be determined by the described embodiments, but should be determined by the claims.

150: crud analysis device 152: output measurement unit
154: Cradle analysis unit 156: operating condition setting unit

Claims (8)

An output measuring unit for measuring the output of the nuclear fuel assembly in the reactor for each operation cycle of the reactor,
A crad analysis unit for analyzing crust information in the nuclear reactor based on the output of the nuclear fuel assembly in the previous operation cycle for each operation cycle;
And an operation condition setting unit configured to set an operation condition of the nuclear reactor in a next operation cycle for the nuclear fuel assembly using the crud information,
The crad information,
Containing the amount of crust generated in the reactor and the concentration of boron contained in the crust
Nuclear reactor crud analysis device. According to claim 1,
The output of the nuclear fuel assembly,
Axial output deviation signal (ASI),
The crust analysis unit,
In analyzing the crad information, based on the axial output deviation signal, it predicts the amount of crust generated in the reactor and the concentration of boron contained in the crud.
Nuclear reactor crud analysis device. According to claim 2,
The crust analysis unit,
A basic axial output deviation signal is generated in the environment without the crust, and the axial output distribution value at each combustion time point for the fuel assembly on the basic axial output deviation signal is the respective combustion time point on the axial output deviation signal. Predict the amount of the crust and the concentration of the boron to converge to the axial output distribution value at
Nuclear reactor crud analysis device. The method of claim 3,
The driving condition setting unit,
Based on the predicted amount of the crud in the reactor and the concentration value of the boron, operating conditions of the reactor in the next operation cycle are set.
Nuclear reactor crud analysis device. Measuring the output of the nuclear fuel assembly in the reactor for each operating cycle of the reactor,
Analyzing the crud information in the nuclear reactor based on the output of the nuclear fuel assembly in the previous operation cycle for each operation cycle;
And setting operating conditions of the nuclear reactor in a next operation cycle for the nuclear fuel assembly using the crud information,
The crad information,
Containing the amount of crust generated in the reactor and the concentration of boron contained in the crust
Reactor Cradle Analysis Method. The method of claim 5,
The output of the nuclear fuel assembly,
Axial output deviation signal (ASI),
The analyzing step,
Predicting the amount of crust generated in the reactor and the concentration of boron contained in the crust based on the axial output deviation signal.
Reactor Cradle Analysis Method. The method of claim 6,
The predicting step,
Generating a basic axial output deviation signal in the environment without the clutch,
The amount of the crud so that the axial output distribution value at each combustion point for the fuel assembly on the basic axial output deviation signal converges to the axial output distribution value at each combustion point on the axial output deviation signal and Comprising the step of predicting the concentration of the boron
Reactor Cradle Analysis Method. The method of claim 7,
The step of setting the driving conditions,
Setting operation conditions of the reactor in the next operation cycle based on the predicted amount of the crud in the reactor and the concentration value of the boron
Reactor Cradle Analysis Method.

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