Method for evaluating radiation effect of nuclear power plant effluent

An evaluation method and effluent technology, applied in the fields of electrical digital data processing, special data processing applications, instruments, etc., can solve the problems of superimposed gaseous pathway and liquid pathway radiation effects, etc.

Inactive Publication Date: 2017-03-08
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

When the discharge outlets of liquid effluents and airborne effluents are far apart, there may be large differences in the diet and living h

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  • Method for evaluating radiation effect of nuclear power plant effluent

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Embodiment Construction

[0027] The specific embodiments of the present invention will be further described below in conjunction with the accompanying drawings.

[0028] Taking a nuclear power plant whose liquid effluent discharge port is 25 km away from the site evaluation center (airborne effluent discharge port) as an example, the relevant calculations and assumptions performed according to the steps of the present invention are as follows:

[0029] The first step is to determine the relative position and distance between the liquid effluent discharge port and the evaluation center (airborne effluent discharge port) according to the layout plan of the nuclear power plant: after inspection, the liquid effluent discharge port is located 25km east of the evaluation center.

[0030] The second step is to judge and determine the dilution factors corresponding to different evaluation sub-areas according to the population distribution around the nuclear power plant: the evaluation scope of the nuclear power plant...

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Abstract

The invention belongs to the technical field of nuclear radiation effect evaluation, relates to a method for evaluating a radiation effect of nuclear power plant effluent, and is applicable to a case that a distance between a liquid effluent discharge outlet and an airborne effluent discharge outlet is relatively long. The method comprises the steps of: according to relative positions of a nuclear power plant effluent discharge outlet and an evaluation center (the airborne effluent discharge outlet), a distance between the nuclear power plant effluent discharge outlet and the evaluation center and distribution of people around a plant site, judging and determining dilution factors suitable for different evaluation sub regions; selecting proper resident recipe and life habit data; and calculating the maximum individual effective radiation dosage which the public suffers from in a plant site evaluation range. By utilizing the evaluating method disclosed by the invention, the technical problem of inaccurate evaluation result in the case that the distance between the liquid effluent discharge outlet and the airborne effluent discharge outlet is relatively long, which is caused by no consideration to the case that the distance between the liquid effluent discharge outlet and the airborne effluent discharge outlet is relatively long in relevant evaluation currently, is solved.

Description

Technical field [0001] The invention belongs to the field of nuclear power plant radiation impact assessment, and specifically relates to a method for evaluating the radiation impact of nuclear power plant effluents. Background technique [0002] The radiation impact of the normal operation of nuclear power plants on the public around the site includes two ways, one is the discharge of airborne effluent, and the other is the discharge of liquid effluent. The closer to the airborne effluent discharge port, the worse the atmospheric dispersion, and the greater the impact of gaseous radiation on the public; the closer to the liquid effluent discharge port, the worse the dilution of liquid radionuclides by the receiving water body, the public The greater the influence of radiation from the liquid pathway. When we evaluate the radiation impact of the normal operation of nuclear power plants on the public around the site, we need to superimpose the radiation dose to the public caused ...

Claims

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Application Information

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IPC IPC(8): G06F17/50G06Q50/06G06Q50/26
CPCG06Q50/06G06Q50/265G06F30/20Y02E60/00
Inventor 熊章辉王晓亮周耀权杜红燕李凤菊
Owner CHINA NUCLEAR POWER ENG CO LTD
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