Radiation dose evaluation device, radiation dose evaluation method, and program
The radiation dose evaluation device and method address the challenge of varying reactor operating states by evaluating and managing radiation doses based on past data, ensuring compliance and safety through real-time monitoring and alerting for deviations.
Patent Information
- Authority / Receiving Office
- JP · JP
- Patent Type
- Patents
- Current Assignee / Owner
- MITSUBISHI HEAVY IND LTD
- Filing Date
- 2023-02-09
- Publication Date
- 2026-05-29
Smart Images
Figure 0007867456000001 
Figure 0007867456000002 
Figure 0007867456000003
Abstract
Description
Technical Field
[0001] The present disclosure relates to a radiation dose evaluation apparatus, a radiation dose evaluation method, and a program.
Background Art
[0002] Patent Document 1 discloses a radiation dose rate distribution visualization apparatus that visualizes a three-dimensional distribution of radiation dose rates corresponding to changes in the arrangement of structures caused by work.
Prior Art Documents
Patent Documents
[0003]
Patent Document 1
Summary of the Invention
Problems to be Solved by the Invention
[0004] However, the radiation dose rate distribution visualization apparatus described in Patent Document 1 has a problem that it may not be able to cope with a case where the dose rate changes due to a change in the operating state of a nuclear reactor, for example.
[0005] The present disclosure has been made to solve the above problems, and an object thereof is to provide a radiation dose evaluation apparatus, a radiation dose evaluation method, and a program that can cope with a case where the dose rate changes due to a change in the operating state of a nuclear reactor.
Means for Solving the Problems
[0006] To solve the above problems, the radiation dose evaluation device according to this disclosure is a device for evaluating the radiation dose of a nuclear power plant, and comprises: an acquisition unit that acquires a first set of information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of second information which is a set of first information which is a set of second information which is a set of first information which is a set of second information which is a set of first information which is a set of third information which is a set of fourth information which has been acquired in the past, and whether or not the fourth information included in the first set is within an acceptable range of the fourth information which is within an acceptable range a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set
[0007] The radiation dose determination method relating to this disclosure is a method for evaluating the radiation dose of a nuclear power plant, and includes the steps of: acquiring a first set of information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of second information which is a set of first information which is a set of first information which is a set of second information which is a set of third information which is a set of first information which is a set of first information which is a set of third information which is a set of fourth information which has been acquired in the past.
[0008] The program relating to this disclosure is a program for evaluating radiation levels at a nuclear power plant, and causes a computer to perform the following steps: acquire a first set of information, which is a set of first information representing the operating state of the reactor, second information representing the reactor coolant level, third information representing the measurement location, and fourth information representing the measured value of the radiation level; and determine whether the fourth information included in the first set is within an acceptable range of the fourth information determined based on a second set of information previously acquired, which is a set of first information, second information, third information, and fourth information. [Effects of the Invention]
[0009] The radiation dose evaluation device, radiation dose evaluation method, and program of this disclosure can respond to cases where the dose rate changes due to changes in the operating state of the nuclear reactor. [Brief explanation of the drawing]
[0010] [Figure 1] This is a block diagram showing an example configuration of a radiation dose evaluation device according to the first embodiment of this disclosure. [Figure 2] This is a schematic side cross-sectional view showing an example of the configuration of a nuclear power plant. [Figure 3] This is a schematic partial cross-sectional plan view illustrating an example of the configuration of a nuclear power plant. [Figure 4] This is a schematic diagram illustrating an example of an operating mode for a pressurized water reactor. [Figure 5] This is a schematic diagram illustrating an example of an operating mode for a boiling water reactor. [Figure 6] This is a schematic diagram illustrating an example of a periodic inspection plan for a nuclear power plant. [Figure 7] This is a schematic diagram showing an example of the configuration of a data set according to the first embodiment of this disclosure. [Figure 8] This is a schematic diagram showing an example of radiation dose rate measurement data according to the first embodiment of this disclosure. [Figure 9] This flowchart shows an example of the operation of a radiation dose evaluation device according to the first embodiment of this disclosure. [Figure 10] This block diagram shows an example configuration of a radiation dose evaluation system according to a second embodiment of this disclosure. [Figure 11] This flowchart shows an example of the operation of the radiation dose evaluation system according to the second embodiment of this disclosure. [Figure 12] This is a schematic block diagram showing the configuration of a computer according to at least one embodiment. [Modes for carrying out the invention]
[0011] Hereinafter, the radiation dose evaluation apparatus, radiation dose evaluation method, and program according to the embodiments of this disclosure will be described with reference to the figures. In each figure, the same or corresponding components will be denoted by the same reference numerals, and their descriptions will be omitted as appropriate.
[0012] <First Embodiment> (Configuration of radiation dose evaluation device) FIG. 1 is a block diagram showing a configuration example of a radiation dose evaluation device according to a first embodiment of the present disclosure. The radiation dose evaluation device 1 shown in FIG. 1 can be configured using, for example, a computer such as a server, a personal computer, a microcomputer, or a peripheral device of the computer, and is configured as a functional configuration including a combination of hardware such as the computer and software such as a program executed by the computer. The radiation dose evaluation device 1 includes an acquisition unit 11, a determination unit 12, and an alarm issuance unit 13.
[0013] In the present embodiment, the radiation dose evaluation device 1 is a device for evaluating the radiation dose of a nuclear power plant. In the present embodiment, the radiation dose may be expressed as a dose rate (dose per unit time) or as a total dose for a predetermined time. Further, the meaning of evaluating the radiation dose is to determine whether the radiation dose is good or bad, whether the radiation dose is a value that requires some action, and the like. Here, some action means, for example, implementing radiation reduction measures, re-implementing measurement, and the like. In the present embodiment, the radiation dose to be evaluated by the radiation dose evaluation device 1 is, for example, the one measured during a periodic inspection of a nuclear power plant. The periodic inspection of a nuclear power plant is an inspection that is periodically carried out by stopping the operation of the nuclear power plant. In the periodic inspection, for example, inspection of equipment, inspection, replacement, repair, etc. of fuel and consumables are carried out. In other embodiments, the radiation dose to be evaluated by the radiation dose evaluation device 1 may be, for example, the one measured outside the periodic inspection stop or after an emergency stop during normal operation, that is, during a period other than the normal operation period.
[0014] In the present embodiment, the measurement of the radiation dose may be manually performed by an operator or the like using a dosimeter or the like, or may be automatically measured using an autonomous mobile body such as a drone equipped with a dosimeter or a ground vehicle robot. Further, when measuring the radiation dose using a mobile body equipped with a dosimeter, all or part of the configuration of the radiation dose evaluation device 1 may be mounted on the mobile body or a relay base where the mobile body stops by.
[0015] First, referring to FIGS. 2 and 3, a configuration example of a nuclear power plant whose radiation dose is to be evaluated by the radiation dose evaluation device 1 will be described. FIG. 2 is a side cross-sectional view schematically showing a configuration example of a nuclear power plant. FIG. 3 is a partial cross-sectional plan view schematically showing a configuration example of a nuclear power plant. The nuclear power plant 100 shown in FIG. 2 is a pressurized water nuclear power plant and includes a reactor building 101, a turbine building 102, and an auxiliary building 103. The reactor building 101 includes a reactor vessel 111, a steam generator 112, and a pressurizer 113. The turbine building 102 includes a steam turbine 121. Note that in FIG. 3, a radiation dose measurement location P in the present embodiment is illustrated. The measurement location P is a predetermined radiation dose measurement location and can be determined, for example, by XY coordinates and elevation (E.L.; altitude; height in the Z direction), corresponding to a region including a certain spatial or planar range.
[0016] Returning to FIG. 1, the acquisition unit 11 acquires a first set that is a set of first information representing the operating state of the reactor, second information representing the reactor coolant level (hereinafter also referred to as the reactor level), third information representing the measurement location, and fourth information representing the measured value of the radiation dose. The first set, which is a set of the first to fourth information, is data including the first to fourth information. The acquisition unit 11 acquires (inputs) the first set, for example, according to an operator's input operation, or acquires it by reading information from a predetermined measuring device, recording device, recording medium, etc. Further, the acquisition unit 11 may acquire, for example, the first information representing the operating state of the reactor and the second information representing the reactor coolant level from information defined in a periodic inspection (hereinafter also referred to as a regular inspection) plan. In this case, the acquisition unit 11 can, for example, refer to the periodic inspection plan and acquire the planned value of the operating state of the reactor at the time of radiation dose measurement as the first information, and acquire the planned value of the reactor coolant level as the second information.
[0017] Note that in the present embodiment, the reactor means a device that extracts thermal energy generated by causing a nuclear fission reaction in nuclear fuel (hereinafter also referred to as fuel) under control, and is composed of, for example, a reactor vessel 111, nuclear fuel, a moderator, a coolant, control rods, a reflector, biological shielding, etc.
[0018] Furthermore, in the first information representing the operating state of the reactor, the operating state of the reactor is also called the operating mode, and is, for example, the operating state defined in the Safety Regulations for Nuclear Power Reactor Facilities. For example, in a pressurized water reactor, it is defined in correspondence with the reactor output, the average temperature of the primary coolant, the fuel loading state in the reactor vessel, and the closed state of the reactor vessel, and specifically, six types of operating modes, "Mode 1" to "Mode 6," are defined. In a boiling water reactor, it is defined in correspondence with the position of the reactor mode switch, the state of the reactor pressure vessel tightening bolts, the reactor coolant temperature, and specifically, multiple operating modes, from "Operation" to "Fuel Replacement," are defined. Figure 4 is a schematic diagram showing an example of an operating mode for a pressurized water reactor. Figure 5 is a schematic diagram showing an example of an operating mode for a boiling water reactor. In this embodiment, in a pressurized water reactor, the first information is, for example, information representing one of Mode 1, 2, 3, 4, 5, 6, or outside of a mode. In addition, in a boiling water reactor, the first piece of information represents, for example, operation, startup, high-temperature shutdown, cold shutdown, or fuel replacement.
[0019] Furthermore, in the second piece of information representing the reactor coolant level, the reactor coolant level refers to the RCS (Reactor Coolant System; primary cooling system, reactor cooling system) water level. The second piece of information can represent the state of the coolant, such as RCS full, RCS completely blown, or cavity full, or it can represent the elevation of the water level. The cavity refers to the space filled with water in a pool-like manner along the fuel transfer path, including the upper part of the reactor.
[0020] Figure 6 is a schematic diagram illustrating an example of a periodic inspection plan for a nuclear power plant. However, Figure 6 only shows the planned values for the operating modes and the RCS water level in the periodic inspection plan. Furthermore, the horizontal axis represents the time for operating modes 1 to 6 equally and does not correspond to the actual normal time intervals.
[0021] Furthermore, in the third piece of information representing the measurement location, the measurement location is a predetermined radiation dose measurement location, as explained with reference to Figure 3. The third piece of information can, for example, represent information such as XY coordinates and elevation, as described above.
[0022] Furthermore, in the fourth piece of information representing the measured radiation dose, the measured radiation dose is the value of the radiation dose (e.g., dose rate) measured at the measurement location represented by the third piece of information, when the reactor operating state is the first piece of information and the reactor coolant water level is the second piece of information.
[0023] Figure 7 shows an example of a first set acquired by the acquisition unit 11 as data DS1. Figure 7 is a schematic diagram showing an example of the configuration of a data set according to the first embodiment of this disclosure. In this case, data DS1 includes data D1 indicating the operating mode, data D2 indicating the reactor coolant water level, data D3 indicating the measurement location, data D4 indicating the measured value, and data D5 indicating the measurement date and time.
[0024] Furthermore, the determination unit 12 determines whether the fourth information included in the first set acquired by the acquisition unit 11 falls within the permissible range of the fourth information determined based on the second set, which is a set of first, second, third, and fourth information acquired in the past. The first to fourth information included in the second set is, for example, the first to fourth information acquired in past periodic inspections, and the reactor operating state represented by the first information of the second set is the same as the first to third information of the first set, the difference in coolant water level represented by the second information of the second set is within a predetermined first range, and the measurement location represented by the third information is the same. The first range is a range in which the water level is considered to be the same with respect to the impact on the radiation dose, and can be set, for example, based on empirical rules. Figure 8 shows an example of the relationship between the radiation dose represented by the fourth information of the first set, the radiation dose represented by the fourth information of the second set, and the permissible range based on the fourth information of the second set.
[0025] Figure 8 is a schematic diagram showing an example of radiation dose rate measurement data according to the first embodiment of this disclosure. The horizontal axis represents time, with time 0 being the start time of measurement by the dose rate meter. Time t1 corresponds to the start time of measurement setting, and time t2 corresponds to the measurement setting time. The vertical axis represents the dose rate, showing the time change of the current measurement value (first set of fourth information) and past measurement values (second set of fourth information), and the current and past average dose rates from time t1 to t2. The tolerance range used as the judgment criterion by the judgment unit 12 can be, for example, a range in which a predetermined percentage of the past average dose rate is increased or decreased around the past average dose rate. Alternatively, the tolerance range can be a range in which a predetermined percentage of the past dose rate is increased or decreased around the past dose rate at the measurement setting time. The judgment unit 12 determines whether the current dose rate or average dose rate measured up to the measurement setting time is within the respective tolerance range. In the example shown in Figure 8, the current measurement value deviates from both tolerance ranges.
[0026] Furthermore, the alarm issuing unit 13 issues a predetermined alarm if the fourth information included in the first set is outside the acceptable range. The alarm issuing unit 13 issues an alarm, for example, by displaying information indicating the measurement location P that has deviated from the acceptable range, along with information indicating that it is outside the acceptable range, on a predetermined display device, or by registering information indicating the measurement location P that has deviated from the acceptable range in a predetermined list.
[0027] (Example of operation of a radiation dose assessment device) Next, with reference to Figure 9, an example of the operation of the radiation dose evaluation device 1 shown in Figure 1 will be described. Figure 9 is a flowchart showing an example of the operation of the radiation dose evaluation device according to the first embodiment of this disclosure. The process shown in Figure 9 is for the measurement value at one measurement location, and multiple measurement locations can be handled by repeatedly executing the process shown in Figure 9 for multiple locations. The process shown in Figure 9 may be started, for example, according to a predetermined operation by the operator, or it may be started automatically when the automatic measurement of radiation dose is completed.
[0028] When the process shown in Figure 9 is started, first the acquisition unit 11 acquires a first set of information, which consists of a first information representing the operating state of the reactor, a second information representing the reactor coolant level, a third information representing the measurement location, and a fourth information representing the measured value of the radiation dose (step S1). Next, the determination unit 12 determines whether the fourth information included in the first set falls within the acceptable range of the fourth information determined based on the second set of information, which consists of a first information, a second information, a third information, and a fourth information, acquired in the past (step S2). Next, the alarm issuance unit 13 issues a predetermined alarm if the fourth information included in the first set is outside the acceptable range (step S3), and the process shown in Figure 9 is terminated.
[0029] (Effects and Benefits) In the radiation dose evaluation device, radiation dose evaluation method, and program configured as described above, when evaluating the radiation dose at a nuclear power plant, a first set of information is acquired, which consists of a first set of information representing the operating state of the reactor, a second set of information representing the reactor coolant level, a third set of information representing the measurement location, and a fourth set of information representing the measured value of the radiation dose. It is then determined whether the fourth information included in the first set falls within the allowable range of the fourth information determined based on a second set of information previously acquired, which consists of the first, second, third, and fourth sets of information. With this configuration, for example, it is possible to determine whether the measured value of the radiation dose to be evaluated falls within the allowable range based on past measured values of radiation doses for the same reactor operating state, reactor coolant level, and measurement location. Therefore, with the radiation dose evaluation device, radiation dose evaluation method, and program of this embodiment, when the dose rate changes due to changes in the operating state of the reactor or changes in the reactor coolant level, the judgment criteria can be appropriately set and addressed.
[0030] Furthermore, in this embodiment, the first and second pieces of information included in the first set can be information specified in the periodic inspection plan. For example, when making a determination, it may be possible to obtain third pieces of information representing the radiation measurement location and fourth pieces of information representing the measured value, but not first pieces of information representing the reactor operating state and second pieces of information representing the reactor coolant level. In this case, by using the first and second pieces of information specified in the periodic inspection plan, it is possible to appropriately set an acceptable range and determine whether the measured value is within the acceptable range. For example, when measuring radiation dose by mounting a dosimeter on a mobile device and determining whether the radiation dose measured on the mobile device is within the acceptable range, it is necessary to obtain the operating mode and reactor coolant level values via a wired or wireless communication line, for example, when the operating mode or reactor coolant level changes. In such cases, if wired or wireless communication with the mobile device is difficult, or if the mobile device is moving in a place where wireless communication is not permitted, it is difficult to obtain the operating mode and reactor coolant level values in real time via wired or wireless communication. Even in such cases, if the periodic inspection is proceeding as planned, an appropriate judgment can be made without communication acquisition by using the operating mode and reactor coolant water level values from the periodic inspection plan.
[0031] Furthermore, in this embodiment, the permissible range is determined based on a second set of data in which the reactor operating state represented by the first information is the same as that of the first set, the difference in coolant water level represented by the second information is within a predetermined first range, and the measurement location represented by the third information is the same as that of the first set. With this configuration, the permissible range can be appropriately set based on past performance values.
[0032] <Second Embodiment> (Configuration of the radiation dose evaluation system) Next, a radiation dose evaluation system according to the second embodiment of this disclosure will be described with reference to Figures 10 and 11. Figure 10 is a block diagram showing an example configuration of the radiation dose evaluation system according to the second embodiment of this disclosure. Figure 11 is a flowchart showing an example of operation of the radiation dose evaluation system according to the second embodiment of this disclosure.
[0033] The radiation dose evaluation system 10 shown in Figure 10 comprises a parent module 2, an autonomous dose rate measurement device 3, and a child module 4. The parent module 2 is installed, for example, in the turbine building 102 shown in Figure 2, and transmits and receives predetermined information with the autonomous dose rate measurement device 3, charges the autonomous dose rate measurement device 3, and evaluates the dose rate value measured by the autonomous dose rate measurement device 3. The autonomous dose rate measurement device 3 is an autonomously mobile device such as a drone or ground-based robot equipped with a dosimeter, which moves autonomously within the turbine building 102 and the reactor building 101 and measures the dose rate at measurement location P. The child module 4 is installed, for example, in the reactor building 101 shown in Figure 2, and transmits and receives predetermined information with the autonomous dose rate measurement device 3, charges the autonomous dose rate measurement device 3, and evaluates the dose rate value measured by the autonomous dose rate measurement device 3.
[0034] The parent module 2 comprises a control device 21, a storage device 22, a radiation dose evaluation device 23, a charging device 24, and a communication device 25. The control device 21 controls each of the devices 22 to 25 within the parent module 2. The storage device 22 stores information representing the periodic inspection plan, information representing the measurement location P, information representing the radiation rate measured during the periodic inspection, etc. The radiation dose evaluation device 23 has a configuration corresponding to the radiation dose evaluation device 1 of the first embodiment described with reference to Figure 1, etc. The charging device 24 is a device that charges the battery of the dose rate autonomous measurement device 3. The communication device 25 is a device that sends and receives predetermined information to and from the dose rate autonomous measurement device 3 via wired communication or predetermined type of wireless communication.
[0035] The autonomous dose rate measurement device 3 comprises a control device 31, an autonomous mobile device 32, a dose rate meter 33, a storage device 34, a battery 35, and a communication device 36. The control device 31 controls each of the devices 32-26 within the autonomous dose rate measurement device 3. The autonomous mobile device 32 moves autonomously between the parent module 2, each measurement location P, and the child module 4. The dose rate meter 33 automatically measures the dose rate. The storage device 34 stores information received from the parent module 1, such as information representing the periodic inspection plan, information representing the measurement location P, information representing the radiation rate measured during the periodic inspection, and information representing the radiation rate measured by the dose rate meter 33. The battery 35 supplies power to each of the devices 31-34 and 36. The communication device 36 is a device that transmits and receives predetermined information between the parent module 1 and the child module 4 via wired communication or a predetermined form of wireless communication.
[0036] The sub-module 4 comprises a control device 41, a storage device 42, a radiation dose evaluation device 43, a charging device 44, and a communication device 45. The control device 41 controls each of the devices 42 to 45 within the sub-module 4. The storage device 42 stores information received from the dose rate autonomous measurement device 3, such as information representing the periodic inspection plan, information representing the measurement location P, information representing the radiation rate measured during the periodic inspection, and information representing the radiation rate measured by the dose rate meter 33. The radiation dose evaluation device 43 has a configuration corresponding to the radiation dose evaluation device 1 of the first embodiment described with reference to Figure 1, etc. The charging device 44 is a device that charges the battery of the dose rate autonomous measurement device 3. The communication device 45 is a device that sends and receives predetermined information to and from the dose rate autonomous measurement device 3 via wired communication or predetermined type of wireless communication.
[0037] (Example of operation of a radiation dose assessment system) Next, with reference to Figure 11, an example of the operation of the radiation dose evaluation system 10 shown in Figure 10 will be described. In the example of operation shown in Figure 11, first, the periodic inspection plan (operating mode, reactor water level on calendar days) is input to the parent module 1, and the input information is stored in the storage device 22 and transferred to the dose rate autonomous measurement device 3 (step S11). Next, the measurement location (floor, EL) is specified in the parent module 1, and the specified information is stored in the storage device 22 and transferred to the dose rate autonomous measurement device 3 (step S12). Next, the parent module 1 acquires dose rate measurement data for each measurement location at the same operating mode and reactor water level during the previous periodic inspection, and the acquired information is stored in the storage device 22 and transferred to the dose rate autonomous measurement device 3 (step S13).
[0038] Next, dose rate measurements are performed at pre-set points by the dose rate autonomous measurement device 3 (step S14). Note that each step in block B1 is performed inside the reactor building 101. Next, the dose rate autonomous measurement device 3 is parked in the sub-module 4, and in the sub-module 4, the periodic inspection plan is created, dose rate measurement data is acquired at the same operating mode and reactor water level as during the previous periodic inspection for each measurement location, and the measurement data is stored, a fume hood is stored in the sub-module 4, and power is supplied to the battery 35 (step S15). Next, the sub-module 4 determines whether the current measurement data deviates from a predetermined tolerance range by comparing it with the dose rate measurement data from the previous periodic inspection at the same operating mode and reactor water level from the parent module 2 (step S16). Next, under the direction of the sub-module 4, the dose rate autonomous measurement device 3 remeasures the current measurement data that has deviated, and the sub-module 4 performs a re-determination, and the result of the re-determination is recorded in the storage device 34 (step S17).
[0039] Next, after the measurement of the entire measurement area is completed, the dose rate autonomous measurement device 3 returns to the parent module 2 and transfers all measurement data to the parent module 2 (step S18). Next, the parent module 2 issues an alert for any deviations in the measurement data (step S19).
[0040] (Effects and Benefits) According to the second embodiment, by utilizing first information representing the reactor operating status and second information representing the reactor coolant water level as defined in the periodic inspection plan, the permissible range of radiation dose can be appropriately set offline. Furthermore, radiation doses that deviate from the set permissible range can be remeasured without returning to the parent module 2.
[0041] While embodiments of this invention have been described above with reference to the drawings, the specific configuration is not limited to the embodiments described above, and design changes and the like that do not depart from the spirit of this invention are also included.
[0042] <Computer Configuration> Figure 12 is a schematic block diagram showing the configuration of a computer according to at least one embodiment. The computer 90 includes a processor 91, main memory 92, storage 93, and an interface 94. The radiation dose evaluation devices 1, 23, and 43 described above are implemented in the computer 90. The operation of each of the above-described processing units is stored in storage 93 in the form of a program. The processor 91 reads the program from storage 93, loads it into main memory 92, and executes the above-described processing according to the program. The processor 91 also allocates memory areas in main memory 92 corresponding to each of the above-described storage units according to the program.
[0043] The program may be for implementing some of the functions that the computer 90 is to perform. For example, the program may perform functions in combination with other programs already stored in storage, or in combination with other programs implemented in other devices. In other embodiments, the computer may include a custom LSI (Large Scale Integrated Circuit) such as a PLD (Programmable Logic Device) in addition to, or instead of, the above configuration. Examples of PLDs include PAL (Programmable Array Logic), GAL (Generic Array Logic), CPLD (Complex Programmable Logic Device), FPGA (Field Programmable Gate Array), etc. In this case, some or all of the functions implemented by the processor may be implemented by the integrated circuit.
[0044] Examples of storage 93 include HDDs (Hard Disk Drives), SSDs (Solid State Drives), magnetic disks, magneto-optical disks, CD-ROMs (Compact Disc Read Only Memory), DVD-ROMs (Digital Versatile Disc Read Only Memory), and semiconductor memory. Storage 93 may be an internal medium directly connected to the bus of the computer 90, or an external medium connected to the computer 90 via an interface 94 or a communication line. Furthermore, if this program is distributed to the computer 90 via a communication line, the computer 90 that receives the program may expand it into main memory 92 and execute the above processing. In at least one embodiment, storage 93 is a tangible storage medium that is not temporary.
[0045] <Note> The radiation dose evaluation devices 1, 23, and 43 described in each embodiment are understood, for example, as follows.
[0046] (1) The radiation dose evaluation devices 1, 23 and 43 according to the first embodiment are devices for evaluating the radiation dose of a nuclear power plant and include an acquisition unit 11 that acquires a first set of information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of first information which is a set of second information which is a set of first information which is a set of first information which is a set of second information which is a set of first information which is a set of third information which is a set of first information which is a set of first information which is a set of first information which is a set of second information which is a set of first information which is a set of third information which is a set of fourth information which has been acquired in the past.
[0047] (2) The radiation dose evaluation devices 1, 23 and 43 according to the second embodiment are the radiation dose evaluation devices 1, 23 and 43 of (1), wherein the first information and the second information included in the first set are information specified in the periodic inspection plan of the nuclear power plant. According to this embodiment, the first information and the second information can be set based on the periodic inspection plan.
[0048] (3) The radiation dose evaluation devices 1, 23 and 43 according to the third embodiment are the radiation dose evaluation devices 1, 23 and 43 of (1) or (2), wherein the permissible range is determined based on the second set, in which the operating state of the reactor represented by the first information is the same as that of the first set, the difference in the coolant water level represented by the second information is within a predetermined first range, and the measurement location represented by the third information is the same as that of the first set.
[0049] (4) The radiation dose evaluation devices 1, 23 and 43 according to the fourth embodiment are the radiation dose evaluation devices 1, 23 and 43 of (1) to (3), further comprising an alarm issuing unit 13 that issues a predetermined alarm when the fourth information included in the first set is outside the permissible range. According to this embodiment, a predetermined alarm can be issued when the measured radiation dose is outside the permissible range. [Explanation of Symbols]
[0050] 1, 23, 43... Radiation dose evaluation device 2...Parent module 3… Autonomous dose rate measurement device 4...Child module 10…Radiation dose evaluation system 11…Acquisition part 12...Judgment section 13… Alarm issuing unit
Claims
1. A device for evaluating radiation levels at a nuclear power plant, An acquisition unit acquires a first set of information, which is a set of first information representing the operating status of the reactor, second information representing the reactor coolant water level, third information representing the measurement location, and fourth information representing the measured value of the radiation dose. A determination unit that determines whether the fourth information included in the first set falls within the acceptable range of the fourth information, which is determined based on the second set, which is a set of the first information, the second information, the third information, and the fourth information acquired in the past. A radiation dose evaluation device equipped with the following features.
2. The first set of information, the first and second pieces of information, is information specified in the periodic inspection plan for the nuclear power plant. The radiation dose evaluation device according to claim 1.
3. The aforementioned tolerance range is determined based on the second set, in which the operating state of the reactor represented by the first information is the same as that of the first set, the difference in the coolant water level represented by the second information is within a predetermined first range, and the measurement location represented by the third information is the same as that of the first set. A radiation dose evaluation device according to claim 1 or 2.
4. An alarm issuing unit that issues a predetermined alarm when the fourth information included in the first set is outside the acceptable range, The radiation dose evaluation device according to claim 3, further comprising:
5. A method for evaluating radiation levels at a nuclear power plant, Steps include obtaining a first set of information, which is a set of first information representing the operating status of the reactor, second information representing the reactor coolant water level, third information representing the measurement location, and fourth information representing the measured value of the radiation dose, A step of determining whether the fourth information included in the first set falls within the acceptable range of the fourth information, which is determined based on the second set, which is a set of the first information, the second information, the third information, and the fourth information acquired in the past. A method for determining radiation dose, including the method described above.
6. A program for evaluating radiation levels at nuclear power plants, Steps include obtaining a first set of information, which is a set of first information representing the operating status of the reactor, second information representing the reactor coolant water level, third information representing the measurement location, and fourth information representing the measured value of the radiation dose, A step of determining whether the fourth information included in the first set falls within the acceptable range of the fourth information, which is determined based on the second set, which is a set of the first information, the second information, the third information, and the fourth information acquired in the past. A program that causes a computer to execute something.