The Calculation Method of Collective Dose in Dispersion Accidents of Transporting Radioactive Materials

A calculation method, a radioactive technology, applied in the field of risk assessment of the transport of radioactive materials

Active Publication Date: 2021-09-24
CHINA INST FOR RADIATION PROTECTION
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] The purpose of the present invention is to provide a method for calculating the collective dose in the dispersion accident in view of the defects of the existing calculation method for the collective dose in the dispersion accident during the transportation of radioactive materials

Method used

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  • The Calculation Method of Collective Dose in Dispersion Accidents of Transporting Radioactive Materials
  • The Calculation Method of Collective Dose in Dispersion Accidents of Transporting Radioactive Materials
  • The Calculation Method of Collective Dose in Dispersion Accidents of Transporting Radioactive Materials

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Embodiment Construction

[0031] The present invention will be described in detail below in conjunction with the examples.

[0032] Assuming that a dispersion accident occurs in the transportation of radioactive materials, it is desired to estimate the collective dose of an arbitrary shape area downwind of the accident point. If the parameters such as shielding factor, dose conversion factor, immersion external exposure time, the number of packages released due to damage, the population density of the area and the area of ​​the area are known, then the calculation of the average nuclide concentration in the area is the key to the problem. Such as figure 2 As shown, it can be solved step by step according to the following steps:

[0033] (S1) fully divide the arbitrary shape area into at least one regular shape sub-area (rectangle, rhombus, equilateral triangle, circle, etc.);

[0034] (S2) Calculate the average nuclide concentration of each regular shape sub-region one by one;

[0035] (S3) Calcula...

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Abstract

The invention belongs to the field of risk assessment of radioactive material transportation, and in particular relates to a calculation method for collective dose in radioactive material transportation dispersion accidents. This method fully divides the area of ​​arbitrary shape concerned in the leeward direction in dispersion accidents into at least one regular-shaped sub-area, calculates the average nuclide concentration of each regular-shaped sub-area, and then further calculates the average nuclide concentration of this area, and then According to the parameters such as shielding factor, dose conversion factor, immersion external exposure time, the number of packages released due to damage, the population density of the area and the area of ​​the area, the collective dose of the area is obtained. The area of ​​collective dose considered in this method is arbitrarily shaped, which is closer to the real situation.

Description

technical field [0001] The invention belongs to the field of risk assessment of radioactive material transportation, and in particular relates to a calculation method for collective dose in radioactive material transportation dispersion accidents. Background technique [0002] For the calculation method of the collective dose in the radioactive material transport dispersion accident, in the original foreign calculation software, the calculation of the collective dose of a certain area downwind of the accident point is considered in the polar coordinate system, that is to say, only the collective dose of the circular area can be considered Dose; in domestic calculation software, under the Cartesian coordinate system, the collective dose in the rectangular area downwind of the accident point is considered, see figure 1 . [0003] In dispersion accidents, the collective dose calculation in any area in the downwind direction can be calculated through the average nuclide concent...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G06F17/10
CPCG16Z99/00
Inventor 王任泽李国强张建岗庄大杰孙树堂冯宗洋孟东原闫峰王学新孙洪超
Owner CHINA INST FOR RADIATION PROTECTION
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