Table of Content

20 November 2019 Volume 39 Issue 6

  

Determination of ^239+240Pu in environmental aerosols from some provinces in China

LI Pengxiang, LI Zhou, ZHANG Jing, WANG Ruijun, HAN Yuhu, REN Xiaona

RADIATION PROTECTION. 2019, 39(6):  451-455. 

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The contents of ^239+240Pu in the environmental aerosols from seven provinces in China were analyzed using anion exchange resin separation and α spectrometer. Their total recovery rates were 60.8%-94.6%. The minimum detectable limit of ^239+240Pu in aerosols was 0.008 μBq/m³. The sampling volume of aerosol in common environment needs more than 30 000 m³. In emergency and other special situations the aerosol sampling volume of 10 000 m³ will be enough. The ²¹⁰Po content in aerosol is 4-6 orders of magnitude higher than ^239+240Pu. In this analysis, we should pay attention to the influence of ²¹⁰Po on ^239+240Pu measurement. Our experimental results show that the contents of ^239+240Pu in the common environmental aerosols in China are 0.009-0.099 μBq/m³, the Pu content in air aerosols in China is the same level as that in the United States, South Korea and Spain.

Study on direct seawater measurement by ultra-low background gamma spectrometry

MI Yuhao, MA Hao, ZENG Zhi, HE Jianhua, CHENG Jianping

RADIATION PROTECTION. 2019, 39(6):  456-462. 

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In order to realize the convenient and sensitive measurement of radioactivity in seawater, the direct measurement method is established based on the low background HPGe gamma spectrometer GeTHU in China Jinping underground Laboratory (CJPL). 4 nearly 8.8 L seawater samples from the western Pacific Ocean and the coastal waters of Shanghai City, Qingdao City, Xiamen City respectively are directly measured by GeTHU, and the 18-hour measurement can detect ⁴⁰K as well as some key radionuclides from the ²³⁸U and ²³²Th decay chains. The method with GeTHU also shows an excellent sensitivity to artificial radionuclides. The MDACs for ⁵⁷Co, ¹³¹I, ¹³⁴Cs and ¹³⁷Cs can drop below 25 mBq/L after 12 hours and the MDAC for ¹³⁷Cs is ~8.6 mBq/L after 48 hours. GeTHU will be continuously dedicated in direct measurements of radioactivity in seawater, especially for the urgent monitoring task with massive samples.

Survey on radon activity concentration of underground metro station in Nanning city

WANG Jingbo, JU Zhiping, YU Huijun, XU Mingfa, FENG Liangliang, GUO Qiuju

RADIATION PROTECTION. 2019, 39(6):  463-468. 

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Subway has become one of the most important traffic tools for the public in nearly all the provincial capital cities in China. To confirm the radiation safety in this special underground spaces, a one-year survey of radon activity concentration measurement was carried out in all metro stations at Line-one. Totally 25 stations were involved. Passive integrated radon cup monitor with CR-39 as a detector was adopted for radon integrated measurement. For measurement quality control, the background track density of CR-39 was strictly defined and controlled during operation of the survey. The annual average radon activity concentration of all the 25 stations is (13.9±3.7) Bq/m³ range from 6.4 to 32.9 Bq/m³. For seasonal variation, radon activity concentration in winter was obviously higher than the other three seasons. It was (18.1±2.2) Bq/m³. For Spring, Summer and Autumn, they were (12.7±1.9), (12.9±3.5) and (12.4±4.4) Bq/m³ respectively. Comparisons of different stations and different floors were also performed and no statistically significant difference was observed.

Study on pulsed X ray response characteristics of active ionization radiation dosimeters

GAO Fei, CHEN Dongfeng, XIAO Xuefu, XU Yang

RADIATION PROTECTION. 2019, 39(6):  469-474. 

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Research on radiation protection dosimetry mainly focuses on continuous radiation, but in the fields of industrial detection, X ray diagnosis, flash X ray photography, security inspection and scientific research, pulsed ionizing radiation has been widely practised. The active electronic dosimeters are used in the fields of environment monitoring, area monitoring, personal dose monitoring and emergency monitoring. The active electronic dosimeters are calibrated in continuous radiation field and difficult to measure short pulse and high dose rate pulsed ionizing radiation accurately. In order to learn the pulsed response characteristics of the active ionizing radiation dosimeter, a pulsed X ray reference radiation field has been built based on a millisecond pulsed X ray machine, and pulsed response characteristics of four active ionizing radiation dosimeters were studied in the pulsed X ray reference radiation field. The results show that the commonly used active dosimeters are not suitable for dose measurement and early warning of short pulse and high dose rate radiation fields.

Research on interpolation reconstruction and visualization of radiation dose field based on Kriging theory

LI Hua, ZHAO Yuan, LIU Liye, XIAO Yunshi, CAO Qinjian

RADIATION PROTECTION. 2019, 39(6):  475-482. 

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The data reconstruction and visualization of different radiation field distribution types were carried out by interpolation calculation method based on Kriging theory, such as uniform mesh, random arrangement, and so on. The reconstruction results were compared with the commonly used inverse distance weighted interpolation method. The different interpolation methods were used to analyze the effect of reconstruction accuracy and visual display for the radiation field. The results show that for most cases, the Kriging interpolation method is superior to the inverse distance weighted interpolation method in the accuracy of the radiation field reconstruction and the visual display. The deviation between original data and the results of the Kriging interpolation method in the example is within 10%, and the deviation between original data and the results of the IDW is basically above 15%. However, in the region where the gradient of the radiation dose field is large and the known data is very few, the result of the Kriging interpolation method will be biased greatly. In the case where the source position coincides with the interpolation point, the calculation result of the Kriging interpolation method near the source will be biased. In this case, IDW interpolation can be used as a supplement and used comprehensively. The research work in this paper verifies the application potential of Kriging interpolation in radiation field reconstruction and visualization, which provides a technical support for promoting the development of radiation field and dose visualization simulation technology.

Study on shielding effectiveness of nickel-base composite coating for environmental electromagnetic radiation

ZHANG Tao, GAO Peng, YU Zhengping

RADIATION PROTECTION. 2019, 39(6):  483-486. 

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The environmental electromagnetic radiation intensities near a TV transmitter tower and a mobile phone base station were measured. A composite coating for shielding radiofrequency electromagnetic radiation was prepared using nickel carbonyl powder and water-borne varnish as main raw materials. Experimental results show that the environmental electromagnetic radiation intensities near typical radiation sources do not exceed the national control limits. The nickel-based composite coating has high shielding performance for radio-frequency electromagnetic radiation in environment. Using the formula and technological conditions adopted in this experiment, the shielding effectiveness of the material is found to be optimal when the nickel content per unit area is 0.015 g/cm².

The design of national dispatching platform for emergency radiological monitoring

LI Ke, LIANG Manchun, YUE Feng, LIN Quanyi, ZHANG Miao, ZHANG Yan, YUE Huiguo, YANG Jie, CHEN Jiehe, YUAN Hongyong, CHENG Jianping, YANG Dandan, SHEN Hongmin, LIU Fang

RADIATION PROTECTION. 2019, 39(6):  487-496. 

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Emergency Radiological Monitoring is an important work carried out when a nuclear or radiological accident occurs. In an accident or exercise, National Dispatching Platform for Emergency Radiological Monitoring (NDPERM) is used to draw up the emergency monitoring plan, dispatch provincial emergency monitoring forces, implement online conference with relevant emergency departments, collect national radiation emergency monitoring data, conduct monitoring data analysis, and make emergency monitoring decision and command. The paper mainly introduces the design of NDPERM and proposes for the future development of NDPERM.

Domestic development of environmental monitoring spectrometer for emergency response in NPP

ZHANG Wei, LIU Weirong, WANG Xin

RADIATION PROTECTION. 2019, 39(6):  497-501. 

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Environmental monitoring spectrometer,as a new-type of equipment used for emergency response,was used in domestic NPPs after Fukushima nuclear accident. The improvement of emergency monitoring ability is restricted by the high cost of imported equipment. The domestic environmental monitoring spectrometer for emergency response which is developed in this work, is about half cost in batch manufacturing compared with imported equipment and it has excellent performance and specifications, as well as open software system. The developed environmental monitoring spectrometer can meet the need of normal operation and emergency monitoring in NPPs. It also has a good application prospect in other nuclear facility.

Study on reuse of liquid effluents in inland pressurized water reactor plants

YE Xinnan, FAN Wenwen, WANG Yilin, GAO Ruifa, ZHANG Zhiyin

RADIATION PROTECTION. 2019, 39(6):  502-509. 

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Reuse of liquid effluents in inland nuclear power plants (NPPs) and discharge reduction of liquid effluents to environment is an effective way to protect water resources, and it is a necessary choice for inland NPPs to meet energy development plan and major safety requirements of site selection. The reusing feasibility of liquid effluent is studied based on design and operation experiences of NPPs. The results show that the recycling of treated laundry liquid in hot laundry and reusing of floor drains in reactor cavity and spent fuel pit cooling system are practicable, and can reduce the discharge of liquid effluents to environment by 8 400 m³ (Two units per year) accounting for the reduction of 51.8% of its total amount, and the reduced discharge of radioactivity in liquid effluents to environment by 4.8×10⁵ Bq accounting for the reduction of 36.9% of its total radioisotope amount.

Effect of loads on wear performance of graphite pebbles used in HTR-PM high temperature gas cooled reactor

DENG Shaogang, GUO Lixiao, LIANG Yu, ZHANG Yuhang, LIANG Dong, WANG Yongxian

RADIATION PROTECTION. 2019, 39(6):  510-516. 

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Wear performance of graphite pebbles used in the HTR-PM high temperature gas cooled reactor at different loads in helium were investigated with a friction and wear tester. Surface and appearance of graphite pebbles were analyzed using a optical microscope. Particle size and pattern of graphite dust were studied using a scanning electron microscope and laser particle analyzer. Results show that in helium atmosphere, the friction coefficient decreases as the load increases. The graphite dust is mainly flaky or flocculent, and has strong adhesiveness. Particle size of the graphite dust increases as the load increases. At different loads, the wear rate of graphite pebbles decreases continuously and eventually goes to a steady value.

Research on hospital-level CT radiation dose and diagnostic dose level

WANG Liang, PENG Yong, LIU Yi, PENG Hongfen

RADIATION PROTECTION. 2019, 39(6):  517-521. 

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This work aims to study the CT scan radiation dose of the human anatomical region of hospital scale and diagnostic dose level of adult CT examination. A total of 15,440 CT scan data were collected from the anatomical regions of all adults who underwent diagnostic CT examinations on GE Light Speed 16 CT equipment from February 2018 to January 2019. The volumetric dose index (CTDI_vol) and the dose length product (DLP) of the patient’s anatomical region were counted according to the anatomical region classification. The quantities of CTDI_vol and DLP in the scan data were statistically analyzed using spss19 software and the effective dose (ED) was calculated. As a result, the DRL values of CTDI_vol in each anatomical region were as follows: 87.75 mGy for the brain, 8.09 mGy for the lungs, 15.82 mGy for the upper and lower abdomen, and 15.79 mGy for the upper and lower abdominal pelvis. The DRL values of DLP in each anatomical region were as follows: for the brain was 1 053.03 mGy cm, for the lung was 245.19 mGy cm, for the upper and lower abdomen was 269.96 mGy cm, for the upper and lower abdominal pelvic was 835.20 mGy cm. The DRL values of CTDI_vol and DLP in lung anatomical region (8.09 mGy, 245.19 mGy cm) were lower than those in other regions of China and other countries. The DRL values of CTDI_vol and DLP in patients under 60 year old were lower than 8.09 mGy and 245.19 mGy cm, and the DRL values of CTDI_vol and DLP in CT scan of patients over 60 year old were higher than 8.09 mGy and 245.19 mGy cm. Taking all together, according to the analysis of the research results, the CT radiation dose and the adult CT examination dose level of each anatomical area of the hospital can be determined, which provides a basis for optimizing the CT scanning technique and monitoring the radiation dose.

The influence of MgSO₄ on the NF-κB/ICAM-1 of human umbilical vein endothelial cells after irradiation

FENG Shicheng, XU Hualin, SUN Yang, XU Ruijun, CUI Fengmei, TU Yu

RADIATION PROTECTION. 2019, 39(6):  522-527. 

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To study the effect of magnesium sulfate on the expression of NF - κ B and ICAM-1, and to explore the protective mechanism of magnesium sulfate on radiation injury of HUVECs. The cells under exponential growth phase were divided into control group, irradiation group and irradiation+MgSO₄ group, and treated with a single 4 Gy X-ray except the control group, while 1.25 mg/mL was added to the irradiation+MgSO₄ group 0.5 h before the irradiation. Flow cytometry analysis and RT-PCR were used to study the expression of NF-κB/ICAM-1 mRNA, and NF-κB/ICAM-1 protein expression was detected by Western blot and the laser confocal microscope. The results showed that within 72 hours after irradiation, the expression levels of NF-κB、ICAM-1 mRNA were higher than that of control group, especially for 3 h;48 h and 72 h post-irradiation. The protein level of NF-κB/ ICAM-1 Proteins expression in the group of treated by 1.25 mg/mL MgSO₄ was significantly lower than that of the controls. These results indicate that ionizing radiation can induce the over expression of NF-κB/ICAM-1, and MgSO₄ down-regulation the expression of ICAM-1 by inhibited the trans-location of NF-κB, which may be the mechanisms of radiation protection.

Diagnosis, treatment and medical follow-up of one case of acute radiation induced finger skin injury

WANG Youyou, LIU Yulong, YU Daojiang, BIAN Huahui, CHEN Weibo, DAI Hong, FENG Junchao, HOU Yuhan, YU Jun

RADIATION PROTECTION. 2019, 39(6):  528-531. 

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Based on one case of the III° acute finger skin injury induced by accidental over-exposure to ¹⁹²Ir source, the diagnosis and treatment solution was reviewed, systematic medical follow-up was conducted. Further observation and reflection are intended to summarize clinical data and to accumulate experience for medical treatment for nuclear and radiation injury. Acute radiation induced skin injury may develop into chronic damage, affecting the quality of life of patients. Hence, it is necessary to take appropriate measures for treatment, with various factors considered synthetically.

40-year medical follow-up of early over-exposed workers in a nuclear facility

ZHANG Huisheng, LI Li, SHANG Wei, ZHONG Xiaohu, WANG Junfeng, WANG Shouzheng

RADIATION PROTECTION. 2019, 39(6):  532-535. 

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The results of 40-year medical follow-up of 106 early over-exposure cases in a nuclear facility is reported. It turned out that no radiation cataract was found, and there was no difference in the lens opacity and chromosome aberration rate, while the rate of lymphocyte micronucleus was significantly higher than that of the control group.