Table of Content

20 November 2024 Volume 44 Issue S1

  

A review of radioactive leakage source parameter inversion methods

XU Yuhan, FANG Sheng, DONG Xinwen, ZHUANG Shuhan

RADIATION PROTECTION. 2024, 44(S1):  1-7. 

Abstract ( 67 )   PDF (2052KB) ( 56 )  

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In recent years, radioactive leakage incidents from unknown sources have garnered widespread attention. In response to such events, nuclear emergency responses often lack source term inputs, making it difficult to make radiation consequence assessment based on atmospheric dispersion models. As a result, methods for reconstructing radioactive leakage source parameters based on limited environmental monitoring data have become a research focus. This paper systematically introduces a comprehensive framework for radioactive leakage source parameter inversion, including four key elements: monitoring data, prior information, atmospheric dispersion models, and inversion methods. The inversion methods are classified into two major categories: iterative optimization methods and Bayesian inference methods. This study conducts an in-depth analysis and comparison of these two approaches, summarizes the latest research developments, and proposes future research direction based on a comprehensive evaluation of the performance of various methods.

Measurement of radiation field of ⁶⁰Co source irradiation facility

WANG Dongxi, SUN Tao, LIU Haixia, ZHOU Hongzhao, LI Chongwei, GUAN Xian

RADIATION PROTECTION. 2024, 44(S1):  8-12. 

Abstract ( 50 )   PDF (2793KB) ( 60 )  

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Radionuclides and radiation generating devices are general way to produce reference radiation fields. According to national standards, a reference γ radiation standard device has been constructed. Firstly, the structural composition, physical principle and technical route of the γ-ray Irradiation Facility were introduced. Secondly, the reference radiation filed of ⁶⁰Co source was measured by calibrated standard equipment. The measurement results show that the air kerma rate of the radiation field conforms well to the inverse square of the distance (R²≈1). The air kerma rate at 1 100 mm from the center of the source vary less 5% within 200 mm of field diameter, and the shutter transition time is about 0.74 s.

Analysis on radiation field characteristics outside lead-cooled reactor vessel

ZHAI Zi′an, WU Yirui, MIAO Jianxin, WANG Shuang, LI Wenhan, DENG Lilin, CHEN Xin, WEN Xingjian, YU Hong

RADIATION PROTECTION. 2024, 44(S1):  13-17. 

Abstract ( 45 )   PDF (2587KB) ( 45 )  

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Lead-cooled reactor, one of the fourth generation nuclear power reactor technology, attracts great attention from the world. Due to the significant differences in neutron and γ shielding capabilities between lead coolant and water, radiation field outside the vessel of a lead-cooled reactor differs greatly from that of a pressurized water reactor (PWR). Therefore, the shield design experience from PWRs can't be directly applied to the shield design of lead-cooled reactors. In order to meet the economic shield design requirements of the fourth generation reactors, shield design also needs to be more precise and efficient. Therefore, conducting an analysis of the radiation field characteristics outside the reactor vessel is of great significance. In this study, a typical radial structure of a lead-cooled reactor is chosen, and a 1D computational model is established to analyze the radiation field outside the reactor vessel under normal operation and shutdown conditions by using the RMC program. Firstly, by comparing and analyzing the neutron and γ flux outside the vessel during normal operation of the lead-cooled reactor and PWR, the main contradictions that the shield design needs to be solved during normal operation are identified. At the same time, by analyzing the main sources of γ outside the vessel, the locations and causes of γ generation are determined. Then, the main contributors to the radiation field outside the vessel during shutdown of the lead-cooled reactor are determined by comparing and analyzing the core source terms and reactor vessel activation source terms as well as radiation fields results outside the vessel. Finally, based on the radiation field characteristics of the lead-cooled reactor during normal operation and shutdown, methods for shield design of lead-cooled reactors are proposed. The conclusions in this study are applicable to the shield design of lead-cooled reactors, laying a theoretical foundation for efficient and economical shield design in lead-cooled reactors.

Study on traceability of radioactive aerosols in closed spaces based on quasi reversible method

ZHANG Minghao, WU Rongjun, CHEN Yan, NI Muyi, JIANG Yingwu, WANG Yuqing

RADIATION PROTECTION. 2024, 44(S1):  18-23. 

Abstract ( 46 )   PDF (2820KB) ( 92 )  

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After a radioactive leakage occurs in nuclear facilities, it is generally difficult to directly observe the release point of the source term. The location information of the source term could be obtained indirectly by using radiation monitoring data in the field and the inversion calculation of the diffusion model. Based on the quasi-reversible method, considering the aerosol particle gravity and Brownian diffusion, a direct inversion model for radioactive source terms in a closed space was carried out in this work. The k-epsilon turbulence equation and the convection-diffusion equation of particle pollutant diffusion were established by considering the typical aerosol dynamics parameters and combining the particle Eddy diffusion rate in the turbulent flow field. Then, by forcibly inverting the time step and replacing the second-order diffusion term with the fourth-order stable term, the numerical format of the equation is stabilized. Furthermore, a multi-sensor mode is adopted to reduce the impact of measurement errors, resulting in the inversion of quasi-reversible equations for multiple nominal sources. Finally, taking the “c-T” information of the sensor position as input, an appropriate stability coefficient for inversion was selected. The results show that this inversion model can accurately trace the location of the source term of particle pollutants in the convective diffusion environment within a closed space.

Simulation and analysis of ²⁴¹Am alpha spectrum with varying source to detector distance

PAN Lantian, LI Rui, FAN Lei, HUANG Xinjie, CHEN Xianglei, WANG Yi, LIU Xingyu

RADIATION PROTECTION. 2024, 44(S1):  24-27. 

Abstract ( 39 )   PDF (1733KB) ( 55 )  

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This paper investigates the alpha energy spectrum of ²⁴¹Am and analyzes its generation process. Based on the analysis, detector response function is derived, and a detector response function model based on the convolution of exponential and Gaussian functions is established for the alpha energy spectrum of ²⁴¹Am. The model parameters are obtained using the weighted nonlinear least squares method, and the goodness of fit is evaluated using the Reχ². The model is then used to reconstruct the alpha energy spectrum of ²⁴¹Am obtained from Geant4 simulation. The impact of source-to-detector distance on fitting performance is investigated. This study could provide theoretical guidance for the development of an alpha spectrometer and algorithm design based on the PIPS detector.

Directional detector worked with four-leg robot for searching gamma-ray source

HUANG Yifei, ZHAO Qianru, WU Qichao, WANG Zhonghai

RADIATION PROTECTION. 2024, 44(S1):  28-34. 

Abstract ( 67 )   PDF (8158KB) ( 51 )  

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This article focuses on the task of gamma-ray source searching. A 2×2 CsI(Na) array-based gamma-ray source directional detector was designed, and the spatial orientation algorithm was studied and verified. Based on the ROS (Robot Operating System), the directional detector is integrated with a four-leg robot developed by the company Unitree Robotics. Through the design of PC software, the integration of functionssuch as communication connection, robot motion control, functional settings for the directional detector, and robot motion status monitoring was achieved. Furthermore, a triangulation algorithm based on matrix operations is developed for gamma-ray source localization, which requires parameters from only two measurement points to achieve spatial localization of the radiation source. Experimental validation shows that, for a milli-curie level ¹³⁷Cs radioactive source, the total measurement time is within 90 seconds, and the spatial localization error is less than 0.4 meters.

Study on shielding performance measurement of X-ray protective clothing based on IEC 61331 standard

TANG Xianqiang, GUO Bin, ZHAO Rui, LI Mengfei, ZHANG Xuan, LIU Bo, WU Jinjie

RADIATION PROTECTION. 2024, 44(S1):  35-40. 

Abstract ( 44 )   PDF (2753KB) ( 44 )  

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While nuclear technology is widely used in medicine, radiation protection is becoming more and more important. X-ray protective clothing could provide patients and healthcare workers with direct protection, in which the radiation shielding performance directly determines the protection efficiency. Integrity testing of X-ray protective clothing made of conventional lead-containing materials using digital radiography (DR) can visualise whether the clothing is defective. According to the IEC 61331 standard, conditions for the measurement of lead equivalent of narrow beam X-rays were established, and some X-ray protective clothing was selected for the measurement of the lead equivalent at defect-free and defect areas. The results show that the actual lead equivalent of the selected X-ray protective clothing is greater than or equal to the nominal lead equivalent in the majority of the cases, while the lead equivalent at the defect areas of the clothing is reduced to different degrees.

Analytical method study for the determination of radium-226 in water by liquid scintillation counting

GUO Chen, YANG Hailan, YANG Youkun, BAO Li, GOU Rongxia, WANG Ruijun, LIAN Bing

RADIATION PROTECTION. 2024, 44(S1):  41-45. 

Abstract ( 61 )   PDF (1555KB) ( 49 )  

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This paper studies a liquid scintillation counter measurement method for radium-226 in water. The method extracts radon-222, a daughter of radium-226, from water sample and enters into scintillation solution by means of insoluble scintillation liquid, thus realizes the separation of radon-222 from other interfering nuclides in water. After a period of time, when radium-226 and its daughter reached equilibrium, alpha/beta discrimination measurement was carried out by liquid scintillation counter to separate radon-222 and its alpha emmision daughters polonium-218 and polonium-214 from the beta emmision daughters bismuth-214 and lead-210, and indirectly obtains the activity concentration of radium-226 in the aqueous phase through the measurement of total alpha counts of radon-222, polonium-218 and polonium-214. The results indicated that the quench of liquid scintillation on the measurement of radium-226 in water is very low, and the Quantulus 1220 liquid scintillation counter has a measurement background of 0.02 cpm for this method, with a measurement efficiency of 2.52-2.60 and a minimum detection level of less than 2 mBq/L, which can meet the requirement for the measurement of radium in environmental samples.

Research on the mechanism of enrichment and excretion of strontium ions in Danio rerio

BO Hongyu, FENG Jundong, ZHANG Xiaohong, WANG Weitai, LI Qian, LIU Liang, HE Chengyu, TIAN Liuxin

RADIATION PROTECTION. 2024, 44(S1):  46-52. 

Abstract ( 43 )   PDF (2743KB) ( 47 )  

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Radioactive strontium has a strong affinity with bone, therefore strontium transfer parameters in the body are key parameters for evaluating the environmental impact of nuclear facilities. By using Danio rerio as research object, the enrichment and excretion patterns of strontium ions in Danio rerio are explored, and the moderation effect of verapamil and metallothionein were assessed. The results show that when Danio rerio was exposed to strontium solutions of 0, 10, 50, and 250 mg/L, the enrichment rate constants and bioconcentration factors were negatively correlated with the exposure concentration of strontium ions. A two-way kinetic model was used to simulate the theoretical equilibrium state of strontium accumulation in the whole Danio rerio, bones, and liver, which was positively correlated with the exposure concentration of strontium ions and the accumulation time, and the accumulation rate decreased as accumulation time increased. Under the same strontium concentration exposure level, the accumulation amount and rate of strontium in Danio rerio and its tissues from high to low were: bones ＞ liver ＞ whole body, and the excretion rate shows that: whole body ＞ liver ＞ bones. In a strontium environment of 50 mg/L, the accumulation of strontium in the whole body, bones, and liver was significantly reduced in theapamil group, and the strontium content in the liver was significantly reduced in the metallothionein group. This indicates that verapamil has a inhibitory effect on the accumulation of strontium in Danio rerio, and metallothionein has a certain promoting effect on the excretion of strotium from the liver of Danio rerio.

Development and application of a design platform for radiation protection for pressurized water reactor nuclear power plant

LYU Weifeng, WEI Xinnan, LI Yunfei, XIONG Jun, LIU Jie

RADIATION PROTECTION. 2024, 44(S1):  53-59. 

Abstract ( 67 )   PDF (3846KB) ( 52 )  

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Based on the need analysis of radiation protection design of nuclear power plant, the functional requirement of radiation protection design platform (CEPP) is defined. In consideration with the analysis and conclusion of radiation protection design of nuclear power plant, three key technical issues, namely on-line radiation protection design and full process record, design collaboration inside CEPP platform and between platforms, and precise knowledge delievery are identified and solved. Thus, the radiation protection design platform has been established and tested base on the typical nuclear power plant design project. And the tests were completed in PWR design.

Research on composition optimization of new Gd-containing Ni-based materials

GAO Jing, PENG Chao, MEI Qiliang, LI Hui, ZHENG Zheng, WANG Mengqi

RADIATION PROTECTION. 2024, 44(S1):  60-66. 

Abstract ( 31 )   PDF (3248KB) ( 46 )  

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Based on Monte Carlo particle transport program, a research method and calculation process for the composition optimization of a new shielding material were established. By analyzing the material properties of different matrices and doping elements, the basic components of the composites were preliminarily screened. The one-tenth layer thickness of different Gd-containing composite material at typical neutron and photon energies was simulated and calculated, and the shielding effect was compared with that of high boron stainless steel. The results show that the Gd-containing nickel-based material exhibits excellent shielding performance at various neutron and photon energies. For nickel-based alloy materials, the influence of Gd content on the neutron shielding performance was calculated and analyzed. It was found that with the increase of Gd content, the neutron shielding performance of the material first improved and then decreased, and the neutron shielding effect was always better than that of nickel-based materials without Gd, while there was a optimum doping amount.

Preparation and application of new type rubber based flexible gamma ray shielding composite material

LI Yulong, ZHANG Qiang, LIU Xiajie, LIU Feng, YAN Jinhuang, LI Li

RADIATION PROTECTION. 2024, 44(S1):  67-73. 

Abstract ( 62 )   PDF (6484KB) ( 52 )  

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In order to meet the shielding requirements of gamma rays at radiation hot spots during outage and maintenance of nuclear power plants, a new flexible shielding composite material was developed by mixing vulcanization process, with polymethyl-vinyl siloxane rubber as matrix and heavy metal lead as functional filler. The shielding effect and mechanical properties of rubber-based composite with different lead powder content and particle size were studied. The experimental results show that the shielding performance of materials with the same thickness increases with the increase of lead powder content, and the particle size of 300 mesh lead powder is more conducive to the dispersion of lead powder in the matrix. The shielding performance of gamma rays is tested with ¹³⁷Cs and ⁶⁰Co collimated radiation. The density, tensile strength and hardness of composites increase with the increase of lead content, while the elongation at break decreases with the increase of lead content. By carrying out the demonstration application in nuclear power plants, it is proved that the installation of customized shielding materials can be quickly completed and the collective dose can be effectively reduced.

Research on optimization design of multi-objective neutron shielding materials based on NSGA-Ⅲ

JI Junjie, LI Guodong, HAN Yi, CHI Xiaomiao, SHEN Huaya, SUN Yansong, CHEN Zhiwei

RADIATION PROTECTION. 2024, 44(S1):  74-80. 

Abstract ( 39 )   PDF (5204KB) ( 59 )  

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In order to optimize the design of neutron shielding materials, a study is carried out with a homogeneous mixture of composite materials consisting of boron carbide, iron, tungsten, lead, bismuth oxide, polyethylene and NBS concrete. The evolutionary multi-objective optimization design of material composition and thickness is performed. Based on the simulation results of MCNP5, an adaptive RBF neural network dose prediction model is trained. The reference point-based non-dominated sorting genetic algorithm NSGA-Ⅲ is used to optimize three objective functions: weight, volume, and shielding property of the shielding material. The Pareto-optimal solution set is analyzed to verify the feasibility of the optimization method and provide methods and theoretical guidance for the multi-objective optimization design of neutron shielding materials.

Design of a robot motor driver for strong radiation field

CHEN Zhiwei, HAN Yi, LI Guodong, CHI Xiaomiao, SUN Yansong, YANG Mingming

RADIATION PROTECTION. 2024, 44(S1):  81-85. 

Abstract ( 28 )   PDF (6115KB) ( 48 )  

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Motor is an indispensable part for robots to complete movement and various operations in strong radiation environments. To make the motor more reliable, motor driver, the key part of the motor system, is taken as the research object. The redevelopment design based on radiation hardening has been carried out. Through radiation resistance test and screening of COTS electronics, the partition design of driver circuit based on the electronics’ intrinsic radiation resistance, and the shielding design based on the electronics’ radiation resistance and the partitioned circuit, a three-phase brushless DC motor driver with an output power of 2 kW and a tolerance to total dose of more than 2 000 Gy (⁶⁰Co) was designed. Its prototype manufacturing and related verification test will be carried out in the future.

Impact analysis on source term control method for CPR1000 reactor unit temporary outage

SONG Yunlong, ZHAO Yanpeng, WANG Liang

RADIATION PROTECTION. 2024, 44(S1):  86-89. 

Abstract ( 56 )   PDF (2140KB) ( 94 )  

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The duration of outage, the mode of operation, and the source term control measures will all have an impact on source term. This paper introduces and analyzes the differences in source terms for two CPR1000 units at a nuclear power plant after passive selection of different source term control measures during an outage. This paper also provides recommendations for source term control measures during an outage of a nuclear power unit.

Treatment of silver-coated silica gel containing iodine waste by subcritical hydrothermal condition

ZHANG Yuchuan, FENG Yaxin, LIU Yi, ZHANG Sai, WANG Zhipeng, YANG Kaidi, GUO Peng, LI Yining, ZHANG Shengdong, ZHANG Zhentao

RADIATION PROTECTION. 2024, 44(S1):  90-96. 

Abstract ( 32 )   PDF (8150KB) ( 91 )  

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This study utilizes the fact that hydroxyl radicals generated under subcritical hydrothermal conditions can accelerate the reaction process. The iodosodalite was formed by treating homemade iodine-containing silver-containing silica gel with NaAlO₂ as raw material and adding 5 wt.% FD61 glass powder as an additive. The differences under static subcritical hydrothermal conditions and dynamic subcritical hydrothermal conditions were compared in the physical phase, microstructure and morphology of the iodosilicate synthesized. The XRD results showed that the dynamic subcritical hydrothermal conditions were favourable for the formation of iodosodalite due to the full contact between the solid phase and the liquid phase by the constant stirring. The SEM-EDS results show that the iodosodalite synthesized under the dynamic subcritical hydrothermal perform a homogeneous morphology with regular round flakes and the particle size about 2 μm. In the dynamic subcritical hydrothermal conditions, the iodine element is uniformly distributed in the solidification. The TG-DSC result shows that the synthesized solidified body has a good thermal stability, and can only decompose above 850 ℃. The XPS result shows that the elemental iodine in iodosodalite exists in the form of I^-. The present work could provide some theoretical references for low-temperature and rapid treatment of iodine-containing silver-coated silica gel under subcritical hydrothermal conditions.

Research on wet oxidation technology of radioactivespent resins

ZHANG Li, WANG Jianlong, XI Yahui, HAN Xu, QIN Xiang, YAN Xiaojun, LIU Zhaofeng, GAO Chao, GUO Xiliang

RADIATION PROTECTION. 2024, 44(S1):  97-101. 

Abstract ( 50 )   PDF (3029KB) ( 50 )  

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By using wet oxidation technology to treat gram-level radioactive waste resin, the effects of pH value of the reaction system, oxidant concentration and drop acceleration rate on the degradation effect of the waste resin were investigated. The results showed that when the system pH value is 2 and the concentration of hydrogen peroxide is 50%, efficient degradation of the waste resin can be achieved. Degradation efficiency can reach more than 99%. Under the same process parameters, different types of waste resin wet oxidation experiments were carried out, and the degradation efficiency reached more than 99％, indicating that the wet oxidation process is compatible with the treatment of different types of resins. Based on this study, the process amplification experiment with kilogram level waste resin was carried out, and the wet oxidation process showed good stability.

Reuse process design and application of HF gas recovery

MA Yan, YAN Hanyang, XIAO Jianhua, CHANG Yuzhen, WANG Jieyu, GONG Lu

RADIATION PROTECTION. 2024, 44(S1):  102-107. 

Abstract ( 30 )   PDF (2028KB) ( 43 )  

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In uranium enrichment plant, HF gas is absorbed by adsorbent material instead of condensation collection. The recovery unit uses NaF absorption attached tower. The reuse system of HF gas recovery unit is mainly to desorb the absorption-saturated NaF adsorption tower and adsorb it inside the tower HF gas is released by heating, and HF gas is sprayed and reused by adsorption tower. A set of HF gas process system is designed based on the test results. From the process flow, process parameters, process equipment, process method, process control and other aspects of the demonstration, a set of desorption process is designed to meet the requirements of the system. The process system has reached mature process standards in terms of production scale, safety and automation. In this paper, the operation of HF gas recovery device recycling system was studied and summarized, and the system equipment, process pipeline, centralized transmission and DCS control, computer workstation and other process design were carried out. The system fault interlocking protection part is designed, and the system innovation and difficulties are analyzed and summarized.

The treatment and discharge of NORM wastewater

LI Yang, LIAN Bing, WANG Yan, YANG Jie, LUO Kai

RADIATION PROTECTION. 2024, 44(S1):  108-110. 

Abstract ( 35 )   PDF (983KB) ( 50 )  

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Wastewater discharge is one of the main pathways for the environmental release of radioactive nuclides in the development and utilization of NORM mines. In order to protect public health, radiation safety supervision for the development and utilization of NORM mines is being strengthened in recent years. However, there are no corresponding standards and regulations on how to treat and discharge NORM wastewater. Based on analysis of the production and discharge status of NORM wastewater in China, suggestions on how to standardize the treatment and discharge of NORM wastewater are put forward.

Preliminary study on the safety assessment system for decommissioning of nuclear facilities

DING Hongchun, MAO Cui, HE Fang

RADIATION PROTECTION. 2024, 44(S1):  111-115. 

Abstract ( 44 )   PDF (1057KB) ( 64 )  

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Safe decommissioning of nuclear facilities is one of the necessary conditions for the healthy and sustainable development of nuclear power. To ensure the safety of personnel and the environment during decommissioning process of nuclear facilities, it is urgent to conduct research on the safety assessment system for decommissioning of nuclear facilities. China has not yet established a comprehensive safety assessment system for decommissioning of nuclear facilities. Based on current situation, this paper first focuses on the characteristics of safety assessment for decommissioning of nuclear facilities, which make the safety assessment for decommissioning of nuclear facilities significantly different from the safety assessment of nuclear facilities in operation or general industrial facilities. Secondly, this paper summarizes and extracts the general process and evaluation content of safety assessment for nuclear facilities decommissioning. Finally, this paper summarizes the shortcomings and challenges faced by China in the safety assessment of nuclear facility decommissioning, providing reference for the subsequent development of decommissioning safety assessment for nuclear facilities.

Application practice of ultrasonic on-line decontamination in nuclear power plant

XU Xianda, DENG Kechun, WANG Yonghui, HONG Binlong, SONG Yuanze, ZHANG Zequn, GUO Fei

RADIATION PROTECTION. 2024, 44(S1):  116-120. 

Abstract ( 38 )   PDF (2580KB) ( 88 )  

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This paper mainly introduces the research practice of removing radiation hot spots deposited in the primary coolent system lines by ultrasonic on-line decontamination process in NPP. In this study, ultrasonic power of 60 W and 100 W were applied to the decontamination practice of 26.7 mm and 88.9 mm lines, respectively. The practice shows that the efficiency of on-line hot spot removal by ultrasonic can reach 60%-70%, which is more obvious than that by conventional flushing process. At the same time, this research shows that the application of ultrasonic on-line decontamination needs to consider the factors such as on-site working environment, ultrasonic power, medium flow rate and radionuclide deposition mode comprehensively, so as to make it achieve a better application effect.

Discussion on several problems of radiation accident emergency for uranium mine and associated radioactive mine

GAO Siyi, YANG Chun, XIE Shujun, LIAO Yunxuan, ZHANG Ailing, LI Guanghui

RADIATION PROTECTION. 2024, 44(S1):  121-125. 

Abstract ( 53 )   PDF (972KB) ( 70 )  

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This paper analyzes laws, regulations, and standards related to radiation accidents. This paper clarified the concepts related to nuclear accidents, radiation accidents, radiation contamination incidents, and abrupt environmental incidents, as well as their relationships. Radiation contamination incidents and radiation accidents are considered to have the same implication. Suggestions have been put forward to strengthen the management of emergency plans for radiation accidents in uranium mines and associated radioactive mines, conduct risk assessments for radiation accidents in uranium mines and associated radioactive mines, and promote emergency drills for radiation accidents in uranium mines and associated radioactive mines, for reference by relevant departments and practitioners.

Characteristics of emergency radiation dosimetry based on TL/OSL measurement with resistances

MA Lei, JI Yunlong, WANG Yilong, CHEN Shunian, NING Jing, GUO Junwang

RADIATION PROTECTION. 2024, 44(S1):  126-131. 

Abstract ( 36 )   PDF (2995KB) ( 14 )  

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For the purpose of rapid external radiation dose assessment in nuclear emergency medical rescue, thermoluminescence (TL) and optically stimulated luminescence (OSL) methods were used to detect the irradiated SMD resistance and their characteristics for emergency radiation dose assessment were studied. Experimental results indicated that: (1) Detection efficiency: radiation induced effective signal could be obtained with a detection time of 100 s; (2) Signal stability: the relative standard error of TL measurement for 10 Gy irradiated resistance was 4.3%, and the relative Standard error of OSL measurement was 3.4%; (3) Dose response linearity: in the range of 0-100 Gy, the linear correlation coefficient of TL measurement was 0.987 0, and the linear correlation coefficient of OSL measurement was 0.997 5. (4) The detection limit was 0.12 Gy for OSL measurement and 0.02 Gy for TL measurement, indicating that this method could meet the needs of acute radiation disease classification; (5) Time decay characteristics: the TL and OSL detection signals decayed fast in the first days and then slowly, which could be regarded as exponential type decay. This result showed that the time decay calibration should be considered in dose reconstruction. However, it still reserved sufficient sensitivity for dose reconstruction after 7-10 days.