Table of Content

20 February 2022 Volume 42 Issue 1

  

Ariticles

Rapid Determination of Uranium Radionuclides in Environmental Samples by Solid Phase Extraction Alphaspectrometry Method

Fang Chunming, Jiang Dong, Lu Di, Du Yaofang, Zhao Yuling, Wang Haitao, Shang Di

RADIATION PROTECTION BULLETIN. 2022, 42(1):  1-5. 

Abstract ( 66 )   PDF (1108KB) ( 120 )  

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Uranium radionuclides in environmental samples should be analyzed to survey radioactive pollution. In this paper, the uranium in the samples was extracted by heating with concentrated nitric acid solution, adsorbed by UTEVA resin and desorbed by dilute hydrochloric acid solution. The measurement source was extracted by TTA and chemical recovery of uranium (U-234,U-235 and U-238) was corrected by tracer U-232.The method realized the rapid analysis of uranium radionuclides in environmental samples, and the condition experiments were carried out to determine the optimal measurement conditions: the extracting solution was 8.0 mol/L nitric acid solution, the desorption solution was 0.01 mol/L hydrochloric acid solution, and the dosage of tracer was 180 mBq.When the amount of sample is 0.5 g and the measurement time is 10 000 s, the minimum detectable activity concentration of the method is 0.13 Bq/kg, which meet the requirement of radionuclides analysis in environmental samples.

Investigation of Radiation Environment Status of Typical Oil and Gas Fields

Zhu Jidong

RADIATION PROTECTION BULLETIN. 2022, 42(1):  6-10. 

Abstract ( 64 )   PDF (7921KB) ( 4 )  

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To understand the development process of oil the effects of radiation on the surrounding environment, this paper investigates the gobi and desert of two kinds of oil and gas fields and gamma radiation levels around gathering facilities, survey results show that the joint of oil and gas treatment station point gamma radiation level is higher, suggested further oilfield enterprise in the field of natural radioactive pollution survey and tracking survey practitioners illuminated dose.

Design and Application of Radiation Monitoring Data Management Software of Radioactive Materials Transportation

Ma Guoxue, Zhao Guangcui, Huang Wei, Li Jianjie, Dong Haiyang

RADIATION PROTECTION BULLETIN. 2022, 42(1):  11-14. 

Abstract ( 58 )   PDF (1949KB) ( 48 )  

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In order to assist the consignor to finish radioactive materials transportation radiation monitoring data management, we design radiation monitoring report data management terminal software for the consignor to handle radioactive materials transportation, using the software which can realize to deal with the documents for centralized management, radiation monitoring organizations can also be convenient to collect information on radioactive materials, realize information sharing,improved work efficiency.After the relevant information is provided to the radiation management department, it can also facilitate the radiation management department to master the transportation situation of radioactive materials, provide support for the evaluation of potential risks and accidents caused by the environment and people during radioactive materials transportation, and explore the realization of dynamic management of radioactive materials transportation.

Experiences

Discussion and Research on Radiation Protection Detection Methods and Evaluation Methods of Industrial Pulsed X-Ray Generators

Liu Chao, Liu Meimei, Zhao Xiao, Xing Yafei, Chen Yu, Song Zhiwei, Yu Rusiqi

RADIATION PROTECTION BULLETIN. 2022, 42(1):  15-20. 

Abstract ( 62 )   PDF (1773KB) ( 45 )  

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Objective The feasibility of using thermoluminescence dosimeter for radiation protection detection and evaluation of industrial pulsed X-ray generator is discussed. Methods Arrange thermoluminescence dosimeters and AT1123 X/γ radiation dose rate meters at key points in the workplace of the pulsed X-ray generator.Trigger the exposure of the pulsed X-ray generator, and read the test results of the AT1123 X/γ radiation dose rate meters on site.The thermoluminescence dosimeters are taken back to the laboratory for reading. Result By thermoluminescence method, the cumulative doses of the no.1 pulsed X-ray generator are 620.9 μSv, 71.3 μSv and 22.5 μSv at 1 m, 3 m and 5.6 m from the center of the radiation beam axis, respectively. The highest cumulative dose is 199.5 μSv at 1.0 m on the left and right sides of the pulsed X-ray tube (near the target) and 14.6 μSv at 1 m behind the tube.The cumulative dose of 4 exposures outside the shielding wall is between 8.2 μSv and 1.0 μSv. The radiation dose distribution around the X-ray tube of no. 2 pulsed X-ray generator is basically consistent with that of No.1 generator. AT1123 X/γ radiation dose rate meter shows that the dose equivalent rate is 18.8 mSv/h around the center 1 m of the beam axis at the instant of exposure. Conclusion The detection results obtained by the thermoluminescence method are in good agreement with the theoretically calculated values, which can meet the requirements of radiation protection testing for industrial pulse X-ray generator. The test result evaluation method adopted in this paper can give a quantitative evaluation conclusion on the radiation protection effect of the pulse X-ray generator workplace, and the evaluation method has certain feasibility.

Improvement and Optimization of Access Monitoring System in Radiation Control Area of Nuclear Power Plant

Fu Can

RADIATION PROTECTION BULLETIN. 2022, 42(1):  21-25. 

Abstract ( 75 )   PDF (2764KB) ( 67 )  

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This paper introduces the basic situation of the access monitoring system of radiation control area in nuclear power plant. Based on the application feedback and management experience in the nuclear power plant, it analyzes the existing problems in the design. Combined with the development of new technology and the improvement of management requirements, it puts forward improvement and optimization suggestions from the aspects of network architecture, automatic distribution, performance improvement, clean control area, large dose data, etc., which is of certain significance to prevent contamination diffusion and improve the level of dose control.