CN118298956A - Method and system for evaluating radiation dose of personnel caused by failure of nuclear power equipment - Google Patents
Method and system for evaluating radiation dose of personnel caused by failure of nuclear power equipment Download PDFInfo
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Abstract
The invention relates to a method and a system for evaluating radiation dose of personnel caused by failure of nuclear power equipment, comprising the following steps: determining a typical device; calculating source item release and migration after typical equipment failure, and obtaining a source item expected value after typical equipment failure; according to the expected value of the source item after the typical equipment fails, calculating the radiation dose of personnel, and obtaining the radiation dose value of the personnel; and performing overrun judgment according to the radiation dose value of the personnel to obtain overrun judgment results. The method can calculate the radiation source item after the nuclear power equipment fails and calculate and evaluate the radiation dose of personnel by the radiation source item. In addition, the safety importance of the equipment can be identified from the angle of the equipment failure in the nuclear power plant to the dosage of workers, so as to determine the safety grouping or management measures of the related equipment.
Description
Technical Field
The invention relates to the field of calculation of nuclear power radiation dose, in particular to a method and a system for evaluating radiation dose of personnel caused by failure of nuclear power equipment.
Background
The purpose of the security classification of the items in the nuclear power plant is to ensure that the design, manufacture, construction, debugging and operation of the items are properly required to ensure that the items have proper quality and can effectively perform security functions. For items that do not participate in the accident handling but only contain a certain radioactive medium, the effect of the failed radioactivity can be considered as the only factor in judging whether the item is a safety level.
The operation of a nuclear power plant requires a large number of staff, and on the one hand, item failure may affect the outside public, and at the same time, the dose to staff in the plant may be significantly increased. The current latest item safety grading standard further proposes that even if no obvious influence is generated on the outside public, certain safety grading and design requirements need to be considered if the obvious dose received by the staff exceeds the specified limit value due to failure, but no set of calculation method for clearly calculating the radiation dose received by the staff due to item failure exists in the industry at present.
The analysis of the consequences of equipment failure in a nuclear power plant is generally based on the analysis of the influence of doses received by the outside public after a conservative assumption, and no analysis of doses received by on-site staff caused by equipment failure is performed.
Disclosure of Invention
The invention aims to provide a method and a system for evaluating radiation dose of personnel caused by failure of nuclear power equipment.
The technical scheme adopted for solving the technical problems is as follows: a method for evaluating radiation dose of personnel caused by failure of nuclear power equipment is constructed, which comprises the following steps:
determining a typical device;
Calculating source item release and migration after the typical equipment is disabled, and obtaining a source item expected value after the typical equipment is disabled;
According to the expected value of the source item after the typical equipment fails, calculating the personnel radiation dose to obtain the personnel radiation dose value;
And performing overrun judgment according to the radiation dose value of the personnel to obtain overrun judgment results.
In the method for evaluating the radiation dose of personnel caused by the failure of nuclear power equipment, the method further comprises the following steps:
And displaying the radiation dose of personnel caused by the failure of different typical equipment in each area according to the overrun judging result.
In the method for evaluating the radiation dose of personnel caused by the failure of the nuclear power equipment, the determining the typical equipment comprises the following steps:
dividing the system according to the functional characteristics and system parameters of the system to obtain different units;
calculating the total radioactivity released after the equipment in each different unit fails to obtain the total radioactivity after the equipment in each unit fails;
typical equipment within each unit is determined based on the total amount of radioactivity after equipment failure in each unit in combination with different radiation partitions of the plant.
In the method for evaluating radiation dose of personnel caused by failure of nuclear power equipment, the calculating the release and migration of the source item after the failure of the typical equipment, and the obtaining the expected value of the source item after the failure of the typical equipment comprises the following steps:
Determining a radiation zone in which the typical device is located;
And according to the radiation partition where the typical equipment is located, carrying out source item release and migration calculation by combining the radiation source type after the typical equipment is disabled, and obtaining the expected value of the source item after the typical equipment is disabled.
In the method for evaluating the radiation dose of personnel caused by the failure of nuclear power equipment, the radiation partition comprises the following steps: a primary partition and a secondary partition; the primary partition includes: red and orange zones; the secondary partition comprises: yellow, green and white;
If the radiation partition where the typical equipment is located is a first-level partition, performing source item release and migration calculation according to the radiation partition where the typical equipment is located and by combining the radiation source type after the typical equipment is disabled, and obtaining the expected value of the source item after the typical equipment is disabled includes:
According to the type of the radiation source after the typical equipment is disabled, performing source item release and migration calculation based on the free volume of a room, and obtaining a source item expected value after the typical equipment is disabled; the expected value of the source item after the typical equipment is failed is the total leakage amount after the typical equipment is failed;
If the radiation partition where the typical device is located is a secondary partition, performing source item release and migration calculation according to the radiation partition where the typical device is located and by combining the radiation source type after the typical device is disabled, where obtaining the expected value of the source item after the typical device is disabled includes:
Performing source item release and migration calculation according to the type of the radiation source after the typical equipment fails and based on the leakage form of the radiation source, and obtaining a source item expected value after the typical equipment fails; the expected value of the source term after the failure of the typical equipment is the total leakage amount after the failure of the typical equipment.
In the method for evaluating the radiation dose of personnel caused by the failure of nuclear power equipment, the radiation source type comprises: a liquid fluid and a gaseous fluid;
the method for obtaining the expected value of the source item after the typical equipment is failed according to the type of the radiation source after the typical equipment is failed and based on the free volume of the room, comprising the following steps:
If the radiation source type is liquid fluid after the typical equipment fails, filling leakage fluid according to the free volume in the room, and calculating by combining the residence time of personnel outside the room after the accident occurs for one hour to obtain the expected value of the source item after the typical equipment fails;
if the radiation source type is gas fluid after the typical equipment fails, filling leakage gas according to the free volume in the room, and calculating by combining the residence time of personnel outside the room after the accident occurs for one hour to obtain the expected value of the source item after the typical equipment fails;
The method for obtaining the expected value of the source item after the typical equipment is failed comprises the following steps of:
If the radiation source type after the typical equipment is failed is liquid fluid, calculating according to the situation that the liquid fluid leaks into the whole room and personnel in the room evacuate for 10 minutes after an accident occurs, and obtaining a source item expected value after the typical equipment is failed;
If the radiation source type after the typical equipment is in failure is gas-liquid, calculating according to the leakage rate of the damage of the typical equipment and calculating the residence time of personnel in a room after the accident is 10 minutes, so as to obtain the expected value of the source item after the typical equipment is in failure.
In the method for evaluating the radiation dose of personnel caused by the failure of the nuclear power equipment, the step of calculating the radiation dose of the personnel according to the expected value of the source item after the failure of the typical equipment, and the step of obtaining the radiation dose value of the personnel comprises the following steps:
if the radiation source after the failure of the typical equipment is liquid fluid, adopting a direct irradiation calculation method, and calculating the radiation dose of personnel according to the expected value of the source item after the failure of the typical equipment to obtain the radiation dose value of the personnel;
If the radiation source after the failure of the typical equipment is gas fluid, a gas radioactivity calculation method is adopted, and according to the expected value of the source item after the failure of the typical equipment, personnel radiation dose calculation is carried out, so that personnel radiation dose values are obtained.
In the method for evaluating the radiation dose of personnel caused by the failure of the nuclear power equipment, the step of calculating the radiation dose of the personnel according to the expected value of the source item after the failure of the typical equipment, and the step of obtaining the radiation dose value of the personnel further comprises:
and after the radiation dose calculation of the personnel is completed by adopting a direct irradiation calculation method or a gas radioactivity calculation method after the typical equipment is out of work, the influence of other equipment on the radiation dose of the personnel is overlapped, and the radiation dose value of the personnel is obtained.
The invention also provides an evaluation system for the radiation dose of personnel caused by the failure of nuclear power equipment, which comprises the following components:
a typical device selection unit for determining a typical device;
the source item release and migration calculation unit is used for calculating source item release and migration after the typical equipment fails to obtain a source item expected value after the typical equipment fails;
The radiation dose calculation unit is used for calculating the radiation dose of personnel according to the expected value of the source item after the typical equipment fails to obtain the radiation dose value of the personnel;
And the overrun judging unit is used for carrying out overrun judgment according to the radiation dose value of the personnel to obtain overrun judgment results.
In the evaluation system for the radiation dose of personnel caused by the failure of the nuclear power equipment, the system further comprises:
And the display unit is used for displaying the radiation dose and whether the overrun of personnel caused by the failure of different typical equipment in each area according to the overrun judging result.
The evaluation method and the system for the radiation dose of personnel caused by the failure of the nuclear power equipment have the following beneficial effects: the method comprises the following steps: determining a typical device; calculating source item release and migration after typical equipment failure, and obtaining a source item expected value after typical equipment failure; according to the expected value of the source item after the typical equipment fails, calculating the radiation dose of personnel, and obtaining the radiation dose value of the personnel; and performing overrun judgment according to the radiation dose value of the personnel to obtain overrun judgment results. The method can calculate the radiation source item after the nuclear power equipment fails and calculate and evaluate the radiation dose of personnel by the radiation source item. In addition, the safety importance of the equipment can be identified from the angle of the equipment failure in the nuclear power plant to the dosage of workers, so as to determine the safety grouping or management measures of the related equipment.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic flow chart of a method for evaluating radiation dose of personnel caused by failure of nuclear power equipment;
FIG. 2 is a schematic illustration of a human radiation dose and overrun display provided by the present invention;
FIG. 3 is a logic block diagram of an evaluation system for the radiation dose of personnel resulting from a failure of a nuclear power plant provided by the present invention.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
According to the invention, by combining the plant and system arrangement characteristics of the nuclear power plant, typical equipment is reasonably selected, factors such as migration characteristics in the plant, the states of workers and the like after the typical equipment fails are considered, reasonable calculation parameters and assumptions are formulated, evaluation and calculation of radiation dose results caused by workers due to the fact that only radioactive medium typical equipment fails are contained in a nuclear island are realized, and judgment of whether the dosage received by the workers exceeds a specified limit value can be realized by further expanding based on typical equipment evaluation results.
Specifically, referring to fig. 1, fig. 1 illustrates a preferred embodiment of a method for evaluating radiation dose to personnel due to failure of a nuclear power plant according to the present invention.
As shown in fig. 1, the method for evaluating the radiation dose of personnel caused by the failure of the nuclear power equipment comprises the following steps:
step S101: a typical device is determined.
In this embodiment, determining a typical device includes: dividing the system according to the functional characteristics and system parameters of the system to obtain different units; calculating the total radioactivity released after the equipment in each different unit fails to obtain the total radioactivity after the equipment in each unit fails; typical equipment within each unit is determined based on the total amount of radioactivity after equipment failure in each unit in combination with different radiation partitions of the plant.
In particular, for a system containing only a small amount of radioactive medium, the system may be further divided into different units according to the functional characteristics of the system and system parameters. The selection of typical events of the equipment in the unit is firstly based on the release of the total radioactivity amount after the equipment is out of order, and then the selection of the typical equipment is carried out by combining different radiation partitions of a nuclear power plant factory building.
Wherein the total amount of radioactivity depends on the amount of radioactive medium held by the device and the amount of upstream available after the device has been disabled until isolation is completed, as well as the radioactivity concentration of the entire medium.
During normal operation of a nuclear power plant, a primary partition and a secondary partition are already divided according to the characteristics of equipment in a plant, wherein the primary partition comprises: red and orange zones; the secondary partition comprises: yellow, green and white. The staff will be restricted to the red and orange zones during normal operation. For equipment failure to be placed in the red and orange zones, it is not necessary to assume that personnel will be in the failed equipment bay during normal operation. For equipment failure arranged in white, yellow and green areas, the personnel need to be in equipment compartments under conservative consideration. The status of the staff may affect the size of the dose that the equipment fails to receive for the staff. Therefore, in addition to the total amount of radioactivity released, the typical device is selected by taking the characteristics of the radiation zone in which the device is located into consideration. The device with the largest total radioactivity is selected from different subareas in the unit, namely the typical device. It should be noted that the radiation partition in the plant is generally divided into a non-limiting area, a supervision area and a control area. The supervision area and the control area are designated areas of professional irradiation. The supervision and control areas may be subdivided into white, green, yellow, orange and red areas, depending on the effective dose rate of the area.
Step S102: and (5) calculating the release and migration of the source item after the failure of the typical equipment, and obtaining the expected value of the source item after the failure of the typical equipment.
In this embodiment, calculating the release and migration of the source item after the failure of the typical device, and obtaining the expected value of the source item after the failure of the typical device includes: determining a radiation zone in which a typical device is located; and according to the radiation partition where the typical equipment is located, carrying out source item release and migration calculation by combining the radiation source type after the typical equipment is disabled, and obtaining the expected value of the source item after the typical equipment is disabled.
In this embodiment, the radiation source types include: liquid fluid and gaseous fluid.
If the radiation partition where the typical equipment is located is a first-level partition, performing source item release and migration calculation according to the radiation partition where the typical equipment is located and by combining the type of the radiation source after the typical equipment fails, and obtaining the expected value of the source item after the typical equipment fails includes: and according to the type of the radiation source after the typical equipment is disabled, performing source item release and migration calculation based on the free volume of the room, and obtaining the expected value of the source item after the typical equipment is disabled. The expected source item after the failure of the typical equipment is the total leakage quantity after the failure of the typical equipment. Obtaining expected values for source items after a typical device failure includes: if the radiation source type is liquid fluid after the typical equipment fails, filling leakage fluid according to the free volume in the room, and calculating the residence time of personnel outside the room after the accident happens for one hour to obtain the expected value of the source item after the typical equipment fails; if the radiation source type is gas fluid after the typical equipment fails, the radiation source type is filled with leaked gas according to the free volume in the room, and the calculation is carried out by combining the residence time of personnel outside the room after the accident occurs for one hour, so that the expected source item value after the typical equipment fails is obtained.
If the radiation partition where the typical equipment is located is a secondary partition, performing source item release and migration calculation according to the radiation partition where the typical equipment is located and by combining the radiation source type after the typical equipment fails, wherein obtaining the expected value of the source item after the typical equipment fails comprises: according to the type of the radiation source after the typical equipment is disabled, performing source item release and migration calculation based on the leakage form of the radiation source, and obtaining a source item expected value after the typical equipment is disabled; the expected value of the source term after a typical equipment failure is the total leakage after a typical equipment failure. Obtaining expected values for source items after a typical device failure includes: if the radiation source type after the typical equipment is failed is liquid fluid, calculating according to the situation that the liquid fluid leaks into the whole room and personnel in the room evacuate for 10 minutes after an accident occurs, and obtaining a source item expected value after the typical equipment is failed; if the radiation source type after the failure of the typical equipment is gas-liquid, calculating according to the leakage rate of the damage of the typical equipment and calculating the residence time of personnel in a room after the accident is 10 minutes, so as to obtain the expected value of the source item after the failure of the typical equipment.
Specifically, after the radioactive device is broken, radioactive material leaks into the atmosphere of the device compartment, thereby exposing the staff to both internal and external radiation. The source items mainly considered for the radioactivity result analysis of the staff are as follows:
a) A radioactive source item in the leaking water body (i.e. the radiation source is liquid fluid);
b) The radiation source is a gaseous fluid that is released into the open space within the plant compartment.
Wherein the calculation of the source item requires calculation of the break form and the isolation time for different devices. The isolation time after the equipment failure needs to be determined when the nuclear power plant only contains the total amount of radioactivity released by the equipment failure of the radioactive medium, and the isolation of the equipment failure is completed through automatic signal automatic isolation or manual isolation of operators. The time of manual operation of the operator depends on whether a signal is directly used for reminding the operator of performing the isolation operation or whether the isolation operation is finished in a control room or in situ. In general, the breach isolation time is generally assumed as follows:
When a reliable isolation signal is present, 1min represents that a leak can be found and isolated automatically; 0.5h indicates that a leak can be found but that the master control room has to be isolated manually; 1.0h indicates that the leak can be found only to be isolated on site; the isolation time is typically 8 hours when there is no reliable isolation signal.
Specifically, when a typical device is in a first zone (for an accident room in which the radiation zone is red or orange, it is assumed that the staff is outside the accident room (taking into account the red zone even when outside the room, it is assumed that the zone is degraded due to maintenance or the like), the total leakage is calculated as follows:
For the radiation source to be liquid fluid, whether the leakage amount is lower or higher than the free volume of the room, the leakage liquid fluid is filled according to the free volume in the room, and the residence time of staff outside the room after the accident is assumed to be 1h;
For a radiation source being a gaseous fluid, the free volume in the room is considered to be filled with the leaked gaseous fluid, and the residence time of the staff outside the room after the accident is assumed to be 1h.
When a typical device is in a secondary zone, for the case that the radiation zone of the room where the accident occurs is a white zone, a yellow zone and a green zone, the total leakage of the staff in the room where the accident occurs is assumed to be calculated as follows:
For the radiation source to be liquid fluid, considering that the liquid fluid in the room leaks into the whole room, and staff in the room evacuate 10 minutes after the accident occurs, the flow rate leaked into the room is the total leakage rate within 10 minutes;
For a radiation source that is a gas fluid, the calculation is performed according to the leakage rate of the broken device, considering the leakage amount of 10 minutes, that is, the total leakage amount of the gas flow amount leaked into the room within 10 minutes, the stay time of the staff in the room after the accident is assumed to be 10 minutes.
In practical application, the calculation of source item release and migration after typical equipment failure (i.e. the expected value of source item after typical equipment failure) can be calculated by adopting a CPFP2.0 program, wherein the calculation is performed by adopting the CPFP2.0 program in combination with the calculation mode under the condition that a certain fuel cladding breakage rate and proper uranium contamination exist.
Step S103: and calculating the personnel radiation dose according to the expected value of the source item after the typical equipment fails, and obtaining the personnel radiation dose value.
In this embodiment, according to the expected value of the source item after the failure of the typical device, performing calculation of the dose of the personnel exposure, and obtaining the dose value of the personnel exposure includes: if the radiation source after the failure of the typical equipment is liquid fluid, adopting a direct irradiation calculation method, and calculating the radiation dose of personnel according to the expected value of the source item after the failure of the typical equipment to obtain the radiation dose value of the personnel; if the radiation source after the failure of the typical equipment is gas fluid, a gas radioactivity calculation method is adopted, and according to the expected value of the source item after the failure of the typical equipment, personnel radiation dose calculation is carried out, so that personnel radiation dose value is obtained.
Further, in this embodiment, according to the expected value of the source item after the failure of the typical device, performing calculation of the radiation dose of the personnel, obtaining the radiation dose value of the personnel further includes: and after the radiation dose calculation of the personnel is finished after the typical equipment is disabled by adopting a direct irradiation calculation method or a gas radioactivity calculation method, the influence of other equipment on the radiation dose of the personnel is overlapped, and the radiation dose value of the personnel is obtained.
1) The direct irradiation calculation method comprises the following steps:
Specifically, in this embodiment, for the radiation source that is liquid fluid, the calculation of the dose caused by the direct external irradiation may be performed by using the MicroShield program version 7.02, which is based on the mask calculation program of the point-kernel integration method. Wherein, the dose rate level is considered 2 times of the safety factor when the shielding calculation is carried out in consideration of the influence of uncertainty of source item calculation and geometric model simplification.
The general principle of dose point selection at the time of calculation is: the side source is located at a position 30cm away from the surface of the shielding wall, and the upper source is located at a position 200cm away from the surface of the floor or the highest possible position; the lower source is 60cm from the floor surface. Some sites may choose the nearest point that a person can reach because of the arrangement of the equipment. And if no special description exists, selecting a position 30cm away from the surface of the wall body on the normal line surface of the wall body and the equipment, and selecting a midpoint position in the vertical direction of the equipment in the height direction for evaluating the radiation shielding design effect.
2) The gas radioactivity calculating method comprises the following steps:
The gas radioactivity is calculated by dose conversion factors and empirical formulas for the immersion external irradiation and the inhalation internal irradiation of the staff. The method comprises the following steps:
the staff stays in the factory building for 1 hour, and the effective dose to be accumulated caused by the inhalation of the radionuclide is as follows:
the effective dose rate of external irradiation of staff in a factory due to limited smoke cloud immersion is as follows:
(1) Formula (la) and (2):
D: stay in the factory building for 1 hour, the effective dose to be accumulated caused by inhaling the radionuclide, mSv;
d': the effective dose rate of external irradiation due to limited smoke cloud immersion is mSv/h;
C i: the radioactive concentration of the ith nuclide in the air in the factory building, bq/m 3;
BR: the breathing rate of the staff is 3.5X10-4 m 3/s;
(DCF) i: inhaling an effective dose conversion factor to be accumulated caused by the ith nuclide, sv/Bq;
(DCF) Ei: the i-th nuclide is immersed in the external radiation with an effective dose rate conversion factor,
GF: the geometric correction factor 352/V 0.338 of the factory building is dimensionless, V is the free space volume of the factory building, and m 3.
After the radiation dose of the personnel is calculated by the direct irradiation calculation method and/or the gas radioactivity calculation method, the radiation influence of other equipment on the personnel can be further considered by conservative superposition.
Among them, specific consideration is as follows:
1) When the radiation partition of the room around the occurrence area is white, when the dose received by the staff is calculated, the local effective dose rate of 0.0025mSv/h is overlapped;
2) When the radiation partition of the room around the occurrence area is green, when the dose received by the staff is calculated, the local effective dose rate of 0.01mSv/h is overlapped;
3) When the radiation partition of the room around the accident occurrence area is a yellow area and above, when the dose received by the staff is calculated, the local effective dose rate of 1mSv/h is overlapped.
Step S104: and performing overrun judgment according to the radiation dose value of the personnel to obtain overrun judgment results.
Specifically, in this embodiment, for the overrun determination of the radiation dose of the person, the calculated radiation dose of the person may be compared with the limit value to determine whether the overrun is exceeded. Wherein the selection of the limit value can be selected for different purposes. For example, for the case of determining whether the device is a safety level, an appropriate limit value may be determined based on regulatory requirements of the nuclear power plant; if the control of this part of the device is to be enhanced (not to the security level), the limit value may be relatively low. If the person is not overdriven by the radiation dose, the typical device may consider none to be overdriven; if the radiation dose of the personnel exceeds the limit value, the typical equipment can be classified or controlled according to the overrun equipment, or the typical equipment is selected in a further refined mode, and finally the judgment of whether the radiation dose of the personnel exceeds the limit or not due to the failure of the whole system equipment is realized.
Further, as shown in fig. 1, the method for evaluating the radiation dose of personnel caused by the failure of the nuclear power equipment further comprises the following steps:
step S105: and displaying the radiation dose of personnel caused by the failure of different typical equipment in each area according to the overrun judgment result.
Specifically, after the radiation dose received by the person is calculated according to the step S103 and whether the radiation dose received by the person exceeds the limit is determined in the step S104, the radiation dose received by the person and whether the radiation dose exceeds the limit can be output and displayed. For example, a nuclear power plant coolant amount storage and processing system (TEP) is illustrated. The TEP system is divided into 6 units of TEP1, TEP2, TEP3, TEP4, TEP5 and TEP6 according to the functions of the TEP system, the TEP system is further divided into three areas A/B/C according to the characteristics of the subsystem, typical equipment of each area is determined according to the areas A/B/C, and after the typical equipment fails, the radiation dose of personnel is calculated according to the radiation dose caused by the typical equipment, and the radiation dose and whether the radiation dose exceeds the limit are displayed. The method is specifically shown in fig. 2, wherein only the division of the three areas A/B/C is shown in fig. 2, and no indication is shown on the radiation dose and whether the radiation dose exceeds the limit of a specific person.
Referring to fig. 3, the invention further provides an evaluation system for radiation dose of personnel caused by failure of nuclear power equipment.
Specifically, as shown in fig. 3, the evaluation system for the radiation dose of personnel caused by the failure of the nuclear power equipment comprises:
the typical device selecting unit 301 is configured to determine a typical device.
The source item release and migration calculation unit 302 is configured to calculate source item release and migration after a typical device fails, and obtain a source item expected value after the typical device fails.
And the radiation dose calculation unit 303 is configured to perform personnel radiation dose calculation according to the expected value of the source item after the typical equipment fails, so as to obtain a personnel radiation dose value.
And the overrun judging unit 304 is configured to perform overrun judgment according to the radiation dose value of the person, and obtain an overrun judgment result.
Further, as shown in fig. 3, the evaluation system for the radiation dose of personnel caused by the failure of the nuclear power plant further comprises:
and the display unit 305 is used for displaying the radiation dose and whether the overrun occurs to personnel caused by different typical equipment failures in each area according to the overrun judging result.
Specifically, the specific matching operation process between each unit in the evaluation system of the personnel radiation dose caused by the failure of the nuclear power equipment can be specifically referred to the above evaluation method of the personnel radiation dose caused by the failure of the nuclear power equipment, and will not be described herein.
According to the evaluation method and the evaluation system for the radiation dose of personnel caused by the failure of nuclear power equipment, provided by the invention, the radiation dose of the personnel caused by the failure of the typical equipment of the radioactive medium only contained in the factory building of the nuclear power plant is reasonably evaluated by considering equipment arrangement, radiation partition, source item generation and migration processes in the factory building after the failure of the equipment and the like according to the design characteristics of normal operation of the nuclear power plant, and the result of the failure of the typical equipment can be further expanded to the whole system to realize envelope analysis of a large number of equipment. In addition, the safety importance of the equipment can be identified from the angle of equipment failure in the nuclear power plant to the dosage received by the staff by the invention, so as to determine the safety classification or the management measures of the related equipment.
In the present specification, each embodiment is described in a progressive manner, and each embodiment is mainly described in a different point from other embodiments, and identical and similar parts between the embodiments are all enough to refer to each other. For the device disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and the relevant points refer to the description of the method section.
Those of skill would further appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware, computer software, or combinations of both, and that the various illustrative elements and steps are described above generally in terms of functionality in order to clearly illustrate the interchangeability of hardware and software. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the solution. Skilled artisans may implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present invention.
The steps of a method or algorithm described in connection with the embodiments disclosed herein may be embodied directly in hardware, in a software module executed by a processor, or in a combination of the two. The software modules may be disposed in Random Access Memory (RAM), memory, read Only Memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.
The above embodiments are provided to illustrate the technical concept and features of the present invention and are intended to enable those skilled in the art to understand the content of the present invention and implement the same according to the content of the present invention, and not to limit the scope of the present invention. All equivalent changes and modifications made with the scope of the claims should be covered by the claims.
Claims (10)
1. A method for evaluating radiation dose to personnel caused by failure of nuclear power equipment, comprising the steps of:
determining a typical device;
Calculating source item release and migration after the typical equipment is disabled, and obtaining a source item expected value after the typical equipment is disabled;
According to the expected value of the source item after the typical equipment fails, calculating the personnel radiation dose to obtain the personnel radiation dose value;
And performing overrun judgment according to the radiation dose value of the personnel to obtain overrun judgment results.
2. The method of assessing the radiation dose of a person resulting from a nuclear power plant failure of claim 1, further comprising:
And displaying the radiation dose of personnel caused by the failure of different typical equipment in each area according to the overrun judging result.
3. The method of assessing the radiation dose of a person resulting from a nuclear power plant failure of claim 1, wherein said determining a representative device comprises:
dividing the system according to the functional characteristics and system parameters of the system to obtain different units;
calculating the total radioactivity released after the equipment in each different unit fails to obtain the total radioactivity after the equipment in each unit fails;
typical equipment within each unit is determined based on the total amount of radioactivity after equipment failure in each unit in combination with different radiation partitions of the plant.
4. The method of claim 1, wherein calculating the source term release and migration after the typical equipment failure to obtain the source term expected value after the typical equipment failure comprises:
Determining a radiation zone in which the typical device is located;
And according to the radiation partition where the typical equipment is located, carrying out source item release and migration calculation by combining the radiation source type after the typical equipment is disabled, and obtaining the expected value of the source item after the typical equipment is disabled.
5. The method of assessing the radiation dose of a person resulting from a nuclear power plant failure of claim 4, wherein said radiation partition comprises: a primary partition and a secondary partition; the primary partition includes: red and orange zones; the secondary partition comprises: yellow, green and white;
If the radiation partition where the typical equipment is located is a first-level partition, performing source item release and migration calculation according to the radiation partition where the typical equipment is located and by combining the radiation source type after the typical equipment is disabled, and obtaining the expected value of the source item after the typical equipment is disabled includes:
According to the type of the radiation source after the typical equipment is disabled, performing source item release and migration calculation based on the free volume of a room, and obtaining a source item expected value after the typical equipment is disabled; the expected value of the source item after the typical equipment is failed is the total leakage amount after the typical equipment is failed;
If the radiation partition where the typical device is located is a secondary partition, performing source item release and migration calculation according to the radiation partition where the typical device is located and by combining the radiation source type after the typical device is disabled, where obtaining the expected value of the source item after the typical device is disabled includes:
Performing source item release and migration calculation according to the type of the radiation source after the typical equipment fails and based on the leakage form of the radiation source, and obtaining a source item expected value after the typical equipment fails; the expected value of the source term after the failure of the typical equipment is the total leakage amount after the failure of the typical equipment.
6. The method of assessing the radiation dose of a person resulting from a nuclear power plant failure of claim 5, wherein the radiation source type comprises: a liquid fluid and a gaseous fluid;
the method for obtaining the expected value of the source item after the typical equipment is failed according to the type of the radiation source after the typical equipment is failed and based on the free volume of the room, comprising the following steps:
If the radiation source type is liquid fluid after the typical equipment fails, filling leakage fluid according to the free volume in the room, and calculating by combining the residence time of personnel outside the room after the accident occurs for one hour to obtain the expected value of the source item after the typical equipment fails;
if the radiation source type is gas fluid after the typical equipment fails, filling leakage gas according to the free volume in the room, and calculating by combining the residence time of personnel outside the room after the accident occurs for one hour to obtain the expected value of the source item after the typical equipment fails;
The method for obtaining the expected value of the source item after the typical equipment is failed comprises the following steps of:
If the radiation source type after the typical equipment is failed is liquid fluid, calculating according to the situation that the liquid fluid leaks into the whole room and personnel in the room evacuate for 10 minutes after an accident occurs, and obtaining a source item expected value after the typical equipment is failed;
If the radiation source type after the typical equipment is in failure is gas-liquid, calculating according to the leakage rate of the damage of the typical equipment and calculating the residence time of personnel in a room after the accident is 10 minutes, so as to obtain the expected value of the source item after the typical equipment is in failure.
7. The method for evaluating the dose of personnel irradiated by a failed nuclear power plant according to claim 1, wherein the calculating the dose of personnel irradiated according to the expected value of the source item after the failure of the typical equipment comprises the following steps:
if the radiation source after the failure of the typical equipment is liquid fluid, adopting a direct irradiation calculation method, and calculating the radiation dose of personnel according to the expected value of the source item after the failure of the typical equipment to obtain the radiation dose value of the personnel;
If the radiation source after the failure of the typical equipment is gas fluid, a gas radioactivity calculation method is adopted, and according to the expected value of the source item after the failure of the typical equipment, personnel radiation dose calculation is carried out, so that personnel radiation dose values are obtained.
8. The method for evaluating the radiation dose of a person caused by a failure of a nuclear power plant according to claim 1, wherein the calculating the radiation dose of the person based on the expected value of the source term after the failure of the typical plant, the obtaining the radiation dose value of the person further comprises:
and after the radiation dose calculation of the personnel is completed by adopting a direct irradiation calculation method or a gas radioactivity calculation method after the typical equipment is out of work, the influence of other equipment on the radiation dose of the personnel is overlapped, and the radiation dose value of the personnel is obtained.
9. An evaluation system for radiation dose to personnel caused by failure of a nuclear power plant, comprising:
a typical device selection unit for determining a typical device;
the source item release and migration calculation unit is used for calculating source item release and migration after the typical equipment fails to obtain a source item expected value after the typical equipment fails;
The radiation dose calculation unit is used for calculating the radiation dose of personnel according to the expected value of the source item after the typical equipment fails to obtain the radiation dose value of the personnel;
And the overrun judging unit is used for carrying out overrun judgment according to the radiation dose value of the personnel to obtain overrun judgment results.
10. The nuclear power plant failure leading to personnel radiation dose evaluation system of claim 9, further comprising:
And the display unit is used for displaying the radiation dose and whether the overrun of personnel caused by the failure of different typical equipment in each area according to the overrun judging result.
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