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Table of Content

    20 December 2025 Volume 45 Issue 6
      
    Expert Forum
    My opinions on the five whys——Conceptual identification of terminology related to the Basic Standard for Radiological Protection
    ZHENG Junzheng
    RADIATION PROTECTION BULLETIN. 2025, 45(6):  1-13. 
    Abstract ( 5 )   PDF (961KB) ( 0 )  
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    Radiological protection standards are the guidelines for the development of radiological protection science and its implementation. The crucial role of basic standards for radiological protection is self-evident. When the four generations of evolution and updates of China′s basic standards for radiological protection have attracted high attention from all sectors of society, it is necessary to simultaneously address the standardization of relevant professional terminology concepts. Therefore, this article carefully analyzes and identifies the main five Whys perspectives. ①Why should the abbreviation for "protection against ionizing radiation" be "radiological protection" instead of "radiation protection"? ②Why it is necessary to scientifically and rigorously analyze the "source term" that radiological protection focuses on in order to select the right keywords and avoid ambiguity? ③Why is the translation of relevant terms in the ICRP radiological protection system, which serves as the main basis for formulating radiological protection standards, primarily focused on the pursuit of accurate expression? ④Why it is necessary to "bring order out of chaos" for professional terminology concepts within the fields of nuclear science and technology as well as radiological protection? ⑤Why must the whole society uphold and adhere to the spirit of science and rigorous work style, and should never tolerate the unhealthy trend of abusing professional terminology and concepts? It is hoped that this article will serve as a catalyst to build common understanding and promote better and more dynamic development of nuclear science and technology, their wide-ranging applications and the closely related science of radiological protection.
    Overview
    GPU-accelerated methods for gamma-ray shielding and a point-kernel integration framework
    YU Chenyue, ZHANG Hongjian, ZHANG Liguo
    RADIATION PROTECTION BULLETIN. 2025, 45(6):  14-20. 
    Abstract ( 5 )   PDF (3579KB) ( 1 )  
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    This review synthesizes recent advances in GPU (Graphics Processing Unit)——based acceleration for gamma-ray shielding and dose computation. Focusing on the computational kernels of deterministic and stochastic approaches, acceleration strategies for Monte Carlo transport, discrete ordinates (SN), and point-kernel integration are summarized. Building on these insights, we formalize a GPU-oriented framework for point-kernel methods that covers task granularity and thread mapping, cooperative use of shared/constant/texture memories, kernel refactoring, and host & device pipelining with data residency. We further survey CPU-GPU co-processing, real-time 3D radiation-field simulation with visualization feedback, and learning-based surrogates/denoisers with physics-informed constraints, identifying practical bottlenecks including load imbalance, unified memory page migration, unstructured-geometry memory access, and verification/validation of numerical consistency. Evidence indicates that GPUs can markedly shorten time-to-solution for thick-shield penetration, multiple scattering, and large voxelization, enabling field reconstruction and interactive assessment in near real-time.
    Management
    Progress and suggestions on international standardization work in the radiation protection field of ISO/TC85/SC2 in China
    DONG Fangfang, PAN Jianjun, LIU Lipo, GUO Jianxin, YU Haoyang, NI Xueting
    RADIATION PROTECTION BULLETIN. 2025, 45(6):  21-26. 
    Abstract ( 2 )   PDF (832KB) ( 0 )  
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    International standards could facilitate technological progress and enhance economic efficiency, driving and coordinating international trade and technological exchange. In recent years, the International Organization for Standardization (ISO) and several developed countries generally formulated standardization strategies to address the new wave of scientific revolution and industrial transformation. Drawing on China′s practical experience in the radiation protection field of ISO/TC85/SC2, this paper explores and analyzes the main challenges and issues within this domain. This paper also summarizes and evaluates the progress in international standardization work for radiation protection (ISO/TC85/SC2) China has made in recent years, proposing targeted recommendations to further advance standardization efforts in this field.
    Ariticles
    Research on tritium removal from water filter cartridge of Qinshan heavy water reactor
    LU Liyan, ZHANG Bin, XU Hongming, LONG Ke, GE Jian′an, SUN Lei, SHEN Zhaogen
    RADIATION PROTECTION BULLETIN. 2025, 45(6):  28-34. 
    Abstract ( 2 )   PDF (6481KB) ( 0 )  
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    In order to reduce the tritium level in tritium-contaminated waste filter cartridges of Qinsan CANDU NPP, a relevant device needs to be developed to remove and adsorb the tritium contained in the waste filter cartridges, providing a basis for subsequent treatment and disposal of waste filter cartridges. This study established a circulating air/hot air dehumidification experimental device for filter cartridge to simulate tritium removal by dehumidification, and conducted dehumidification and molecular sieve adsorption experiments on filter cartridges with different flow rates (5 m3/h, 10 m3/h, and 15 m3/h) at both normal temperature and heated conditions. Experiment shows that the breakthrough water absorption capacity of the molecular sieve is approximately 0.056 kg/kg, and the saturated water absorption capacity is approximately 0.23 kg/kg. When the measured humidity at the outlet reaches 3%RH, the water absorption rate of the molecular sieve decreases significantly. The experiment provided basic data for the design and operation of the tritium removal device.
    Radionuclides contents in edible parts of corn and rice and their annual effective doses to residents in Lingwu of Ningxia
    DOU Zhijuan, ZHAO Decai, YANG Xiulong, RUI Ting, WANG Dan, LI Zuoyou
    RADIATION PROTECTION BULLETIN. 2025, 45(6):  35-40. 
    Abstract ( 2 )   PDF (2236KB) ( 0 )  
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    In order to investigate the content of radionuclides in edible parts of corn and rice in the study area and their resulting annual effective dose to residents, and to provide a scientific basis for ensuring food safety and people’s health, this study analyzed the activity concentrations of 238U, 226Ra, and 232Th in edible parts of corn and rice from the study area. The results showed that the mean activity concentrations of 238U, 226Ra, and 232Th in corn were 0.003 7, 0.214, and 0.005 Bq/kg respectively; while the mean activity concentrations of 238U, 226Ra, and 232Th in rice were 0.051 6, 1.516, and 0.068 Bq/kg respectively. It was also found that rice exhibited a slightly stronger capacity for accumulating radionuclides compared to corn, although the overall enrichment capacity for both crops remained weak. Importantly, the activity concentrations of radiouclides in corn and rice from the study area were below the limits specified in national standards and fell within normal background range of Limit Concentrations of Radioactive Substances in Food Standards. The calculated internal dose value based on local residents′ recipes is significantly lower than the individual dose criterion of 1 mSv/a for existing exposure situations. Therefore, consumption of these crops poses no health risks to residents and is safe for consumption.
    Experiences
    Requirements and practice for radiation protection for spent fuel transfer at wharfs of nuclear power plants
    ZHANG Hui, LIU Yiqing, CHEN Jiangtao, ZHONG Maihao, YANG Ming, SUN Qian
    RADIATION PROTECTION BULLETIN. 2025, 45(6):  42-46. 
    Abstract ( 2 )   PDF (832KB) ( 0 )  
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    Based on the characteristics of spent fuel cargo packages and the operation process of transporting spent fuel at nuclear power plant wharfs, in consideration with the parameters and radiation protection requirements of the first dedicated ship for transporting spent fuel in China, radiation protection requirements for transporting spent fuel at nuclear power plant wharfs are proposed. On this basis, radiation detection and evaluation of spent fuel transportation at the wharf were carried out from three aspects: the radiation operation area of the wharf, the cargo holding area of the dedicated ship, and the personnel involved in the transportation at wharf. The radiation exposure dose of different operation positions during the loading and unloading of six packages in a single transportation was calculated and compared with the measured values during the spent fuel transportation process. The results were far below the radiation limit for professional personnel in GB 18871. Therefore, the radiation protection requirements and measures proposed in this article for the transportation of spent fuel at nuclear power plant wharfs are reasonable and effective.
    Reports
    Analysis of detection results for gross alpha and gross beta radionuclides in water from 2019 to 2024
    LI Chunhua, GUO Dandan, ZHANG Yifei, ZHOU Xian, HAN Jin, CHEN Yuzhong
    RADIATION PROTECTION BULLETIN. 2025, 45(6):  48-52. 
    Abstract ( 3 )   PDF (842KB) ( 0 )  
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    This study analyzed the assessment results of the detection capability of gross α and gross β radioactivity in water in Yancheng from 2019 to 2024, with the aim to sort out the experiences and deficiencies, and to further improve the detection capability of the laboratory and ensure the accuracy of the detection results. From 2019 to 2023, the standard curve method (GB/T 5750.13—2006) was used. In 2024, the study transitioned to the thick-source method (GB/T 5750.13—2023) for simultaneously determining gross α and β radioactivity concentrations. Referring to the national standard "Conformity Assessment-General Requirements for Proficiency Testing" GB/T 27043—2012, results were valuated using Z-scores and the influencing factors were analyzed. All Z-scores for gross α (ranging 0.11-0.73) and gross β (ranging 0.17-1.67) measurements showed satisfactory performance (Z≤2.0), with outstanding results in 2020 and 2022. After accounting for influencing factors such as crosstalk ratios and branching ratios of gross β, the Z-scores aligned more closely with the reference values. Through systematic reviews of analytical procedures and to continuously improve detection capability, the detection accuracy and reliability of radionuclides in water samples has notably been enhanced.