Method for rapidly analyzing strontium-90 in liquid state efflux of nuclear power plant

A rapid analysis and effluent technology, applied in the field of radionuclide detection and analysis, can solve the problems of strontium isotope separation and difficulty in adoption, and achieve the effect of improving work efficiency and reducing the impact of radiation

Active Publication Date: 2014-07-02
FUJIAN NINGDE NUCLEAR POWER +2
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Problems solved by technology

However, in mainstream nuclear power plants with pressurized water reactors as the reactor type, the content of strontium-89 in the liquid effluent discharge is much higher than that of strontium-90, and the above two technologies cannot separate the isotopes of strontium. It is difficult to use the above two techniques for the rapid monitoring of strontium-90 in the liquid effluent of nuclear power plants

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  • Method for rapidly analyzing strontium-90 in liquid state efflux of nuclear power plant
  • Method for rapidly analyzing strontium-90 in liquid state efflux of nuclear power plant
  • Method for rapidly analyzing strontium-90 in liquid state efflux of nuclear power plant

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Embodiment Construction

[0021] The preferred embodiment of the present invention will be described in detail below in conjunction with accompanying drawing:

[0022] Such as figure 1 The rapid analysis method for strontium-90 in the nuclear power plant liquid effluent includes the following steps: (a) take a certain amount of nuclear power plant liquid effluent, and add strontium carrier and yttrium carrier to it, under acidic conditions It flows through the cation exchange chromatography column, and then rinses the cation exchange chromatography column with nitric acid solution, collects the eluent to obtain the first eluent; (b) flows the first eluent through P204 Separation and purification of the extraction resin chromatography column, rinse the P204 extraction resin chromatography column with nitric acid solution, collect the eluent to obtain the second eluent; (c) evaporate the second eluent to dryness, and use hydrochloric acid Dissolved and transferred to a low-potassium glass vial, adding s...

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Abstract

The invention relates to a method for rapidly analyzing strontium-90 in liquid state efflux of a nuclear power plant. The method includes the following steps that (a) the liquid state efflux of the nuclear power plant is made to flow through a cation exchange color layer pillar under the acidic condition, a salpeter solution is used for leaching, and first eluant is obtained through collection; (b) the first eluant is made to flow through a P204 levextrel resin color layer pillar to be separated and purified, the salpeter solution is used for leaching, and second eluant is obtained through collection; (c) a scintillation solution is added and mixed and then is placed on a liquid scintillation spectrometer so that the counting rate of yttrium-90 can be measured; (d) an average value is acquired through repeated measurement, and the specific activity of yttrium-90 is calculated; (e) the specific activity of strontium-90 is calculated. On one hand, the liquid state efflux of the nuclear power plant is made to flow through the cation exchange color layer pillar under the acidic condition, so that radioactive substances in the liquid state efflux of the nuclear power plant are gathered; on the other hand, the first eluant is made to flow through the P204 levextrel resin color layer pillar to be separated and purified, hence, yttrium-90 can be separated from the first eluant, and strontium-89 and strontium-90 can be separated indirectly.

Description

technical field [0001] The invention belongs to detection and analysis methods of radionuclides, and relates to a rapid analysis method for strontium-90, in particular to a rapid analysis method for strontium-90 in the liquid effluent of a nuclear power plant. Background technique [0002] Strontium-90 (ie 90 Sr) is the fission product of U-235 and Pu-239, mainly from nuclear weapon explosions and nuclear reactors. In nuclear power plant reactors, it may enter the primary circuit of the reactor due to fuel cladding defects or damage, and discharge to the environment with liquid radioactive effluents . Among the isotopes of radioactive strontium, strontium-90 is the most harmful, because its physical half-life (28.6 years) and biological half-life (49.3 years) are long and will be permanently deposited in the hematopoietic skeletal system, replacing calcium and causing radiation sickness (such as leukemia); while its daughter yttrium-90 (ie 90 Y) The high-energy beta ray...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01T1/167
Inventor 吴连生陈超峰黄彦君曾帆杨立涛张兵钦红娟郭杰
Owner FUJIAN NINGDE NUCLEAR POWER
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