KR-20260065201-A - Method for estimating radioactive dose of specfic point in nuclear power plant and apparatus therefor

Abstract

The present invention relates to a method and apparatus for estimating a dose at a specific location in a nuclear power plant. The dose estimation method according to the present invention comprises the steps of: three-dimensional scanning of a measurement space surrounding the specific location to obtain structural information of the measurement space, the location of a source, and a measured dose; obtaining a source dose of each source from the measured dose; and estimating a dose at the specific location based on the distance between the specific location and each source and the source dose.

Inventors

• 강서곤
• 라현준
• 김정인
• 백윤미
• 박평원
• 유보현
• 염충섭

Assignees

• 한국수력원자력 주식회사
• 고등기술연구원연구조합

Dates

Publication Date

20260508

Application Date

20241101

Claims (10)

1. In a method for estimating dose at a specific location of a nuclear power plant, A step of three-dimensionally scanning a measurement space surrounding the aforementioned specific location to obtain structural information of the measurement space, the location of the source, and the measured dose; A step of obtaining the source dose of each source from the above measured dose; and A method comprising the step of estimating the dose at a specific location based on the distance between the specific location and each source and the source dose.
2. In paragraph 1, A method in which at least some of the above-mentioned sailors are located within a pipe or valve.
3. In paragraph 2, A method for estimating the dose at the above-mentioned specific location by considering at least two sources.
4. In paragraph 3, The above source dose is obtained through the following formula; Here, S ijk is the source dose corresponding to the coordinate ijk D ijk is the measured dose at coordinate ijk L ijk is the distance between the measurement point and the source.
5. In paragraph 4, The method for obtaining the dose at the specific location mentioned above using the following formula: Here, C lmn is the dose at coordinate lmn (specific location). r ijk is the distance from a specific location to the crew.
6. In a device for estimating dose at a specific location of a nuclear power plant, An input unit that receives structural information of the measurement space, the location of the source, and the measured dose obtained by 3D scanning the measurement space surrounding the specific location; An estimation unit that obtains the source dose of each source from the above measured dose, and estimates the dose at the specific location based on the distance between the specific location and each source and the source dose; and A device comprising an output unit that outputs the above-mentioned estimated dose.
7. In paragraph 6, At least some of the above-mentioned crew members are devices located within a pipe or valve.
8. In Paragraph 7, The above-mentioned estimation unit is a device that estimates the dose at the specific location by considering at least two sources.
9. In paragraph 4, The above estimation unit is a device for obtaining the source dose using the following formula; Here, S ijk is the source dose corresponding at coordinates ijk D ijk is the measured dose at coordinate ijk L ijk is the distance between the measurement point and the source.
10. In Paragraph 9, The above-mentioned estimation unit is a device that obtains the dose at the above-mentioned specific location through the following formula: Here, C lmn is the dose at coordinate lmn (specific location). r ijk is the distance from a specific location to the crew.

Description

Method for estimating radioactive dose of specific point in nuclear power plant and apparatus therefor The present invention relates to a method for estimating dose at a specific location in a nuclear power plant with a complex configuration. When a nuclear power plant is operated, radionuclides (radioisotopes) called CRUD are generated and travel along the primary system, attaching to all pipes, valves, and equipment in the primary system and generating radiation. It is a major cause of radiation exposure for nuclear power plant workers and is commonly referred to as a source or source of radiation. The shapes and locations of the equipment, valves, and piping that make up a nuclear power plant are very complexly intertwined, which means that the distribution of sources (terms) is geometrically very complex. This is a very different environment from workplaces handling general radioisotopes outside of nuclear power plants. Such a geometrically complex distribution of radiation sources cannot be accurately represented by the inference method based on interpolation from specific measured points, which is the general method for constructing radiation maps. For example, if a source exists between measurement points, the measurement point measures a lower value than the point where the source exists. Since the estimated value of the point where the source is located is calculated by interpolation using this measured value, there is a problem in that the actual dose at the point where the source is located is estimated to be lower. FIG. 1 is a flowchart of a dose estimation method according to an embodiment of the present invention, and FIG. 2 is a schematic diagram of a 3D scanner used in the present invention, and Figure 3 illustrates dose-related information obtained through a 3D scanner, and Figure 4 shows the change in dose according to the distance from the point source, and Figure 5 illustrates a method for estimating the dose at a specific location for a minute source, and FIG. 6 is a configuration diagram of a dose estimation device according to an embodiment of the present invention. Hereinafter, various embodiments of the present invention will be described in detail with reference to the attached drawings so that those skilled in the art can easily implement the present invention. The present invention may be embodied in various different forms and is not limited to the embodiments described herein. To clearly explain the present invention, parts unrelated to the explanation have been omitted, and the same reference numerals are used for identical or similar components throughout the specification. In addition, the size and thickness of each component shown in the drawings are depicted arbitrarily for convenience of explanation, so the present invention is not necessarily limited to what is illustrated. In the present invention, structural information and corresponding source information regarding a measurement space are acquired using a 3D scanner, and the acquired source information is considered as a micro-source term to evaluate the exposure dose at a location to be estimated using the sum of the micro-source terms. The 3D scanner can acquire structural information and dose information measured during measurement. The present invention provides a specific method for creating a dose map based on dose information acquired using a 3D scanner. The present invention will be described below with reference to the drawings. FIG. 1 is a flowchart of a radiation dose analysis method according to an embodiment of the present invention. First, the measurement space surrounding a specific location is 3D scanned to obtain structural information of the measurement space, the location of the source, and the measured dose (S10). In the present invention, a 'specific location' may be a specific point within a space within a nuclear power plant, particularly but not limited to, a containment building where a number of pipes and valves are arranged. A schematic description of the 3D scanning method is shown in Fig. 2. A 3D scanner used for 3D scanning includes a camera, Lidar, and a spatial dosimeter. A known product may be used for the 3D scanner, for example, a product disclosed in Korean Registered Patent No. 10-2606441 may be used. Structural information may include the shape and location of pipes and valves located in the measurement space. In addition, through 3D scanning, the structure and dose of hot spot points with particularly high radiation doses can also be obtained. In addition to structural information, the dose-related measurements obtained through the 3D scanner are as follows. A line (line) can be in various forms, such as a point, line, and plane. Next, the source dose of each source is obtained from the measured dose (S20), and the dose at a specific location is estimated based on the distance between the specific location and each source and the source dose (S30). Here, at least some of the sour