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Method for testing activity concentrations of strontium-89 and strontium-90 in liquid effluent of nuclear power plant

A test method and effluent technology, applied in the direction of radiation measurement, measuring device, X/γ/cosmic radiation measurement, etc., can solve problems such as not yet available, long analysis time, and inability to separate strontium-90, so as to improve work efficiency , the effect of reducing the impact of radiation

Active Publication Date: 2017-02-15
SUZHOU NUCLEAR POWER RES INST +2
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

These two analysis methods have the characteristics of cumbersome analysis steps and long analysis time.
The American Society for Materials’ standard for measuring strontium-90 (ASTM D5811-08) cannot separate strontium-89 and strontium-90, and cannot be directly applied to the measurement of strontium-89 and strontium-90 in the liquid effluent of nuclear power plants; there is no domestic Relevant standards for the measurement of strontium-89 in liquid effluents from nuclear power plants

Method used

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  • Method for testing activity concentrations of strontium-89 and strontium-90 in liquid effluent of nuclear power plant
  • Method for testing activity concentrations of strontium-89 and strontium-90 in liquid effluent of nuclear power plant
  • Method for testing activity concentrations of strontium-89 and strontium-90 in liquid effluent of nuclear power plant

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Embodiment 1

[0032] This embodiment provides a test method for the activity concentration of strontium-89 and strontium-90 in the liquid effluent of a nuclear power plant, specifically:

[0033] (a) Take 2.0L liquid effluent sample, add 5mg strontium carrier, mix well, add the solution to pass through the cationic resin column, add 50mL 8mol / L HNO 3 Eluting strontium, collecting the first eluate;

[0034] (b) Evaporate the collected first eluent to dryness, add 5mL of 8mol / L nitric acid solution to dissolve it, then pass through the strontium characteristic resin column, and wash the strontium characteristic resin column (Sr -spec chromatographic column), the strontium was eluted twice with 5mL 0.05mol / L nitric acid solution, and the second eluent was collected;

[0035](c) collect the second eluent with the liquid scintillation counting bottle of constant weight (12.0178g), weigh (12.0277g) after drying, calculate the recovery rate Y=(m 1 -m 0 ) / m 锶载 × M Sr / m Sr(NO3)2 (81.98%);

...

Embodiment 2

[0050] This embodiment is to determine the detection lower limit of the test method for the activity concentration of strontium-89 and strontium-90 in the liquid effluent of the nuclear power plant of the present invention, and the detection lower limit is calculated according to the following formula:

[0051]

[0052] Where: MDC is the lower detection limit, Bq / L; N b is the background counting rate, cpm; t is the counting time, min; E is the detection efficiency of the instrument to the Sr-89 standard source, cpm / dpm; Y is the chemical recovery rate of strontium, %; V is the sample volume, L;

[0053] According to the formula for calculating the lower limit of detection, the liquid scintillation spectrometer was used to analyze the activity concentrations of strontium-89 and strontium-90 in the liquid effluent of nuclear power plants, and the results are listed in Table 2. It can be seen from Table 2 that using 2L liquid effluent samples and measuring for 1000 minutes, s...

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Abstract

The present invention relates to a method for testing the activity concentrations of strontium-89 and strontium-90 in a liquid effluent of a nuclear power plant. The method includes the following steps that: (a) a strontium carrier is added into the liquid effluent, the strontium carrier and the liquid effluent are mixed, an obtained mixture is made to pass through a cationic resin column, so that a first eluent can be collected; (b) the first eluent is evaporated until the first eluent is dried, an obtained product is dissolved by a first nitric acid solution, an obtained mixture is made to pass through a strontium specific resin column, the first nitric acid solution is used to elute the strontium specific resin column, so that a second eluent can be collected; (c) the second eluent is arranged in a constant-weight liquid scintillation counting vial, and the second eluent is weighed after being dried, and the recovery rate Y of strontium is calculated; (d) the total radioactivity activity concentration A of the strontium-89 and strontium-90 in the liquid effluent is calculated; and (e) the strontium-89 and strontium-90 are generated based on fission in a nuclear facility and are released for testing time, the proportions of the strontium-89 and strontium-90 in the liquid effluent are calculated according to a formula (2), and the activity concentrations of the strontium-89 and strontium-90 in the liquid effluent are calculated. With the method adopted, work efficiency can be greatly improved, and radiation impact on workers caused by the liquid effluent can be reduced.

Description

technical field [0001] The invention belongs to the detection field of radionuclides, and in particular relates to a method for testing activity concentrations of strontium-89 and strontium-90 in liquid effluents of nuclear power plants. Background technique [0002] Strontium-90 (ie 90 Sr) and strontium-89 (ie 89 Sr) are the fission products of U-235 and Pu-239, mainly from nuclear weapon explosions and nuclear reactors. In a nuclear power plant reactor, it may enter the primary circuit of the reactor due to the defect or damage of the fuel cladding, and discharge to the environment along with the liquid radioactive effluent. Strontium-90 is a pure β radionuclide with a half-life of 28.8 years, which is a highly toxic nuclide; strontium-89 is a pure β radionuclide with a half-life of 50.5 days, which is a toxic nuclide; Among the isotopes, strontium-89 and strontium-90 are the most harmful. After being ingested into the human body, they will be permanently deposited in t...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01T1/204
CPCG01T1/204
Inventor 吴连生陈超峰曾帆黄彦君杨立涛张兵钦红娟
Owner SUZHOU NUCLEAR POWER RES INST
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