Search

CN-116256790-B - High-throughput rapid screening method for radioactive substances in waste textile raw materials

CN116256790BCN 116256790 BCN116256790 BCN 116256790BCN-116256790-B

Abstract

The invention relates to the technical field of product quality safety, in particular to a high-throughput rapid screening method for radioactive substances in waste textile raw materials, which comprises the following steps of pre-selecting raw materials; step two, pretreatment of raw materials, step three, detection of radioactive substances, step four, measurement and analysis of radioactive substances, step five, detection of the Sr-90 content of the raw materials, and step six, adding a reagent. The invention provides a research on analysis of common gamma nuclides and Sr-90 content in textile raw materials, ensures the radioactive safety of the textile raw materials, establishes a detection method of radioactive substances Sr-90 in waste textile raw material solid waste by using a low-background alpha beta measuring instrument, has an average recovery rate of 80 percent and an average detection limit, and carries out radioactive detection research on waste textile raw materials, and the research result shows that the content of gamma radionuclides in selected waste textile raw material samples meets the national limit standard requirements and reduces common radionuclide pollution.

Inventors

  • LIU JUN
  • LI HAITAO
  • CHE YINGXIN
  • LONG ZHIXIN
  • WANG BIN

Assignees

  • 中华人民共和国乌鲁木齐海关

Dates

Publication Date
20260512
Application Date
20230213

Claims (8)

  1. 1. A high throughput rapid screening method for radioactive materials in waste textile materials, comprising the steps of; The method comprises the steps of pre-selecting raw materials, namely selecting five representative raw materials of cotton, hemp, silk, wool and nylon, adopting different radioactive substance detection pretreatment methods for treatment, and then measuring the raw materials on a machine; Step two, raw material pretreatment; Detecting radioactive substances, and measuring the contents of gamma radioactive substances Cs-137, cs-134, I-131, K-40 and U-235 in five representative raw materials of cotton, hemp, silk, wool and nylon by using a high-purity germanium gamma energy spectrometer; Measuring and analyzing radioactive substances to determine the activity concentration of nuclide; Detecting the content of Sr-90 in the raw material, enriching the strontium in the raw material by using a calcium carbonate coprecipitation method, adsorbing the Sr-90 in a sample by DtBuH C6 crown ether Sr resin, and measuring the content of the radioactive substance Sr-90 by using a low-background alpha beta measuring instrument; Adding a reagent, detecting and analyzing the Sr-90 content, and determining the Sr-90 content in the sample, wherein the measuring and analyzing step four specifically comprises the following steps: (5.1) sample treatment, namely, adopting a direct preparation method according to the actual detection requirement, and loading the sample into a standard sample box to be put on machine; (5.2) on-machine measurement, namely placing a standard sample box in the central area of a probe of a well-type high-purity germanium gamma spectrometer, maintaining the working condition of the spectrometer, and continuously measuring for a long time; (5.3) nuclide identification, namely searching peaks and determining peak positions, and obtaining corresponding gamma energy according to the determined peak positions so as to determine the type of the measured radionuclide; (5.4) determination of nuclide activity concentration: according to the characteristics of the identified nuclide, selecting a full-energy peak with large gamma-ray emission probability and small interference as a characteristic peak for analyzing the nuclide, calculating the peak area, and calculating the activity concentration of the corresponding nuclide in the sample by a passive efficiency scale, wherein the calculation formula is as follows: ; wherein C is the content Bq/kg of the nuclide in the sample; N-the measured count rate cps of the selected characteristic peak of the nuclide; E, the energy gamma ray total absorption peak detection efficiency; m-the mass kg of the sample contained in the sample box; a-the measured decay branch ratio of the selected characteristic peak of the nuclide.
  2. 2. The method for high throughput rapid screening of radioactive materials in waste textile materials as set forth in claim 1, wherein the principle of said step one is: five representative raw materials of cotton, hemp, silk, wool and nylon are selected, and are measured by a machine after being treated by adopting different radioactive substance detection pretreatment methods, and the detection results are compared to evaluate and optimize the pretreatment methods.
  3. 3. The method for high throughput rapid screening of radioactive materials in waste textile materials as set forth in claim 1, wherein said apparatus comprises an analytical balance, a well-type high purity germanium gamma spectrometer, a standard sample box and an oven.
  4. 4. The method for high throughput rapid screening of radioactive materials in waste textile materials according to claim 1, wherein said step two is specifically: the direct preparation method comprises the steps of cutting up a sample, shearing the cut sample, loading the cut sample into a sample box, compacting the cut sample into a proper sample for gamma spectrum analysis; The dry sample preparation method comprises properly crushing the sample, freeze-drying or placing into a clean enamel tray, drying in an oven, crushing or grinding the dried sample, and then measuring; The ash sample preparation method is characterized in that the temperature is controlled, the temperature is slowly increased in the carbonization stage to prevent ignition, the temperature can be quickly increased to 400 ℃ after the carbonization, and the ash is ashed for ten to tens of hours at the temperature, so that the sample becomes ash with the minimum carbon content, the sample loss or sintering caused by the overhigh temperature in a high-temperature furnace is strictly prevented, the ashed sample is weighed after being cooled in a dryer, and the sample is put into a sample box for machine loading measurement.
  5. 5. The method for high-throughput rapid screening of radioactive substances in waste textile materials as set forth in claim 1, wherein said apparatus comprises analytical balance, low background alpha beta meter, muffle furnace, electric heating plate, centrifuge, and vacuum filtration tank.
  6. 6. The method for high throughput rapid screening of radioactive materials in waste textile materials as set forth in claim 1, wherein said reagents in said step six comprise; extraction chromatography column 2mL pre-packed column 0.65g DtBuH18C6 resin; nitric acid, ρ, is about 1.4g/mL; a strontium carrier solution having a strontium concentration of 5mg/mL; Sodium hydroxide solution, ω (NaOH) =50%; saturated sodium carbonate solution; The pH of the precision test paper is 0.5-5.0; the solvent in the reagent is distilled water or water with the same purity.
  7. 7. The method for high throughput rapid screening of radioactive materials in waste textile materials as set forth in claim 4, wherein said step six is characterized by specifically: (8.1) sample treatment, namely adopting an ash sample preparation method according to the actual detection requirement; (8.2) strontium pre-concentration, namely weighing 1g of ash sample, adding 1mL of strontium carrier, adding 5mL of concentrated nitric acid and 3mL of hydrogen peroxide, collecting supernatant, and discarding insoluble matters; Transferring the sample liquid into a beaker, regulating the pH to be about 2, and adding 0.5mL of 1.25 mol/L calcium nitrate solution; adjusting the pH of the sample solution to 9-10, and adding 30mL of saturated sodium carbonate solution into the beaker; standing, centrifuging, dissolving the precipitate in a 100mL beaker with 5mL concentrated nitric acid, and evaporating to dryness; (8.3) Sr-90 concentration, namely dissolving the evaporated matters in (8.2) by 8mol/L nitric acid, and passing through an extraction chromatographic column; then 5mL8mol/L nitric acid and 5mL 3M nitric acid-oxalic acid are used for washing the chromatographic column respectively, and the washing liquid is discarded; Desorbing strontium with 10mL of 0.05 mol/L nitric acid, collecting the desorption solution in a glass beaker, dripping and evaporating to dryness in the central area of the sample tray; (8.4) on-machine measurement, namely weighing the mass of the dried sample disc, placing the sample disc in a low-background alpha beta measuring instrument with the background and efficiency measured in advance, keeping the argon methane atmosphere, measuring for a long time, and recording the total beta counting rate; (8.5) the Sr-90 content of the sample was calculated.
  8. 8. The method for high throughput rapid screening of radioactive materials in waste textile materials as set forth in claim 7, wherein said calculating the content of Sr-90 in the sample is: ; wherein, C is the content of strontium-90 in the sample, and the unit is Bq/kg; n t -count rate of sample in cps; N b -background count rate in cps; g, ash-to-fresh ratio, the unit is G/kg; J 0 -the net count rate unit of the strontium-90 supervisory source measured when calibrating the detection efficiency of the measuring instrument is cps; J-the net count rate of the strontium-90 supervisory source in cps when measuring the sample; m Ash of ash , the mass of the weighed ash sample is expressed in g; Y—chemical recovery of sample; e-detection efficiency of strontium-90; calculation of the detection lower limit MDA: ; MDA is the detection lower limit, and the unit is Bq/kg; t b -background measurement time in s.

Description

High-throughput rapid screening method for radioactive substances in waste textile raw materials Technical Field The invention relates to a screening method, in particular to a high-throughput rapid screening method for radioactive substances in waste textile raw materials, and belongs to the technical field of product quality safety. Background The traditional energy source is increasingly exhausted, the energy crisis and energy pollution is gradually approaching, nuclear energy is used as a clean and efficient energy source to gradually replace the traditional energy source, although the safety requirement of the nuclear power station is very severe at present, nuclear leakage accidents still possibly occur under extreme conditions such as strong earthquake, the monitoring of the activity level of artificial radioactive isotopes is widely focused along with the construction of a large number of nuclear power units in China and the occurrence of a Fudawn nuclear accident in 2011, a large amount of fission products are released into the environment after the accident of the nuclear power station or other nuclear facilities occurs, mainly I-131, cs-134, cs-137, sr-90 and the like are greatly released, the uranium ore scale is gradually enlarged along with the strong development of the nuclear industry, the natural radionuclide levels such as U-235, K-40 are likely to be remarkably higher than those in other places in natural radioactive mining areas, textile raw materials such as cotton, hemp and animal hair are extremely likely to be polluted in polluted environments along with the construction of the large number of the nuclear power units in China, and even if the radioactive nuclides are greatly polluted by the radionuclides in such environments, and the textile raw materials such as cotton, hemp and animal hair are likely to be remarkably harmful to the textile raw materials are greatly polluted along with the high activity level of the natural radionuclide levels such as natural radionuclide in the natural radionuclide mining areas, and the textile materials are likely to have high harm effect on the human body, clothing and clothing is likely to be produced, and have serious health and have the health effects. With the development of economy, people have higher standard requirements on clothing and food, and detection of harmful substances in textiles is also in global attention, however, in the field of textile safety, people focus attention on harmful substances such as formaldehyde, harmful coloring agents, heavy metals and the like, detection and analysis of radioactive substances possibly existing in the harmful substances are never reported, and the risk of textile raw material pollution possibly caused by the radioactive substances is gradually increased, so that the research is of great significance. Accordingly, there is a need for an improved screening method for radioactive materials to solve the above-mentioned problems. Disclosure of Invention The invention aims to provide a high-throughput rapid screening method for radioactive substances in waste textile raw materials, provides research on analysis of common gamma nuclides and Sr-90 content in textile raw materials, aims to establish a high-throughput rapid screening technology for radioactive substances in waste textile raw materials, ensures the radioactive safety of the textile raw materials, establishes a detection method for the radioactive substances Sr-90 in waste textile raw material solid wastes by using a low-background alpha beta measuring instrument, has an average recovery rate of 80 percent and an average detection limit, and carries out radioactive detection research on the waste textile raw materials, and the research result shows that the content of gamma radionuclide Cs-137, cs-134, I-131, K-40, U-235 and Sr-90 in selected waste textile raw material samples meets the national limit standard requirement, and the measured samples do not have common radionuclide pollution. In order to achieve the above purpose, the main technical scheme adopted by the invention comprises the following steps: a high throughput rapid screening method for radioactive substances in waste textile materials comprises the following steps; The method comprises the steps of pre-selecting raw materials, namely selecting five representative raw materials of cotton, hemp, silk, wool and nylon, adopting different radioactive substance detection pretreatment methods for treatment, and then measuring the raw materials on a machine; Step two, raw material pretreatment; Detecting radioactive substances, and measuring the contents of gamma radioactive substances Cs-137, cs-134, I-131, K-40, U-235 and the like in five representative raw materials of cotton, hemp, silk, wool and nylon by using a high-purity germanium gamma energy spectrometer; Measuring and analyzing radioactive substances to determine the activity concentration of nuclide; Detecting the con