RADIATION PROTECTION

Research on technology for the decommissioning of radioactive concrete chimney

HUA Zhengtao, BAO Fang, ZHENG Li, JIANG Xingdou

RADIATION PROTECTION. 2025, 45(S1): 1-6.

Abstract ( 16 )

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With the progress of decommissioning of old nuclear facilities, the supporting concrete chimney is also facing decommissioning. At present, China has no engineering experience in the decommissioning of large radioactive chimneys. In consideration with the structural characteristics of the chimney to be decommissioned in China, this paper analyzed technical routes for the decommissioning of radioactive chimneys. Removal technology for process pipes inside the chimney and decontamination process technology of the inner wall were studied; key equipment was developed; and solutions to difficult problems in decommissioning technology were proposed.

Research on the development and application of virtual simulation platform for nuclear facility decommissioning

ZHONG Xiangbin, ZHANG Zhennan, LIU Fan, LIANG Weilun, HUO Ming

RADIATION PROTECTION. 2025, 45(S1): 7-11.

Abstract ( 17 )

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Decommissioning of nuclear facilities is a complex system engineering task that involves radiation and industrial risks. This paper presents a construction plan for a decommissioning simulation platform based on international virtual simulation research of nuclear facility decommissioning. This study further explores key technical issues in decommissioning collaborative design and construction management, thus proposing corresponding solutions. Utilizing these methods, the China General Nuclear Power Group's decommissioning simulation platform has been successfully developed and applied. The practical results demonstrate that virtual simulation technology, with advantages of low cost, repeatability, and visualization, has significant potential in the field of nuclear facility decommissioning. It can effectively reduce construction changes, lower project risks, and enhance the quality of engineering.

A parameter optimization method for vibration dehydration screen for radioactive slurry

SUN Haobin, KANG Jinyang, QIAN Yuheng, HOU Shaohan, MA Qizhao, LI Houlin, TAN Fengming

RADIATION PROTECTION. 2025, 45(S1): 12-17.

Abstract ( 12 )

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Vibration dehydration screen, as an important equipment for solid-liquid separation in the work of retrieving slurry from intermediate and high-level liquid waste storage tanks in China's nuclear industry, is designed to separate solids and liquids in radioactive slurry. A method is proposed to improve the dehydration efficiency of the vibration dehydration screen for radioactive slurry without changing its structure. This is achieved by finding the optimal values for the amplitude, vibration frequency, and vibration direction angle. The method combines orthogonal experimental design and discrete element analysis software to numerically simulate the dehydration process of radioactive slurry on the vibration dehydration screen. After fitting the simulation results with a multivariate nonlinear regression, a genetic annealing algorithm is used to find the vibration parameters corresponding to the highest dehydration efficiency. The research results indicate that, with a screen mesh of 25, an amplitude of 8 mm, a vibration frequency of 30 Hz, and a direction angle of 60°, the optimal dehydration efficiency for the vibration dehydration screen can be achieved. The research conclusions could provide some guidance for the optimal design of the vibration dehydration screen for radioactive slurry.

Study on Ce (Ⅳ) plus ultrasonic decontamination technology for primary circuit decontamination of PWR

YANG Rui, QU Xiaohu, ZHENG Kaiyuan, TIAN Chunping, GUO Jinhan, WANG Zhao, LIU Tingting, ZHOU Yu, GAO Yang

RADIATION PROTECTION. 2025, 45(S1): 18-25.

Abstract ( 12 )

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Aiming at the corrosion products generated during the operation of the primary circuit of the pressurized water reactor, the synergistic decontamination technology of Ce(Ⅳ) and ultrasound was studied. The 304 stainless steel was selected as the sample, and the high-pressure reaction vessel was used to simulate the corrosion environment of the primary circuit of the pressurized water reactor to produce a corrosion sample for decontamination. The effects of different Ce(Ⅳ) concentration, nitric acid concentration and ultrasonic factors on the decontamination efficiency were investigated, and the corrosion of metal matrix materials under different conditions was studied. The results show that the surface morphology of the corrosion layer produced by the high-pressure reaction vessel is dense and uniform, and there are no obvious voids and cracks. In the decontamination experiment, the concentration of Ce(Ⅳ) has a significant impact on the decontamination effect. When the concentration of cerium ammonium nitrate is 25 mmol/L, the decontamination solution has the highest decontamination efficiency on the oxide film; The effect of nitric acid concentration on the decontamination effect is not significant, and the decontamination efficiency is not much different under different nitric acid concentrations. However, with the increase of nitric acid concentration, the decontamination efficiency increases first and then decreases. When the concentration of nitric acid is 1.5 mol/L, the decontamination efficiency reaches the highest; The addition of ultrasonic factors will significantly improve the decontamination effect; The decontamination solution has good compatibility with the metal matrix material; The maximum corrosion amount of the metal matrix material is 6.25 g/m², which is far lower than the upper limit of the corrosion amount of the matrix material and the upper limit of the corrosion amount of the precision parts specified in the industry standard.

Application of ICRP radiological protection system in geological disposal of radioactive waste

LIU Xudong

RADIATION PROTECTION. 2025, 45(S1): 26-31.

Abstract ( 9 )

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Starting from a brief review of ICRP Publications 46, 64, 77, 81 and 122, this paper introduces the development process of key concepts and the application of ICRP 2007 Recommendations, in the context of radiation protection for geological disposal of radioactive waste. Based on the relevant content in the International Basic Safety Standards and regulatory guidelines in China, the internal connection and mutually supporting relationship between radiation protection system and the standards and guidelines of geological disposal are discussed.

Progress of safety case study of southwest low and intermediate level radioactive waste disposal repository

CHEN Yunli, XIANG Xiujuan, LUO Guozhou

RADIATION PROTECTION. 2025, 45(S1): 32-37.

Abstract ( 11 )

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In accordance with the requirements of IAEA Safety Guide SSG-23, a safety case study for the Southwest radioactive waste disposal facility was conducted from 2019 to 2023. This research has developed a site-specific FEPs (Features, Events, and Processes) list and assessment scenarios for the facility, projected future climate change prediction in the facility site region, established a concrete evolution model for the disposal units and a long-term dynamic model of groundwater level. Migration parameters are also provided for representative radionuclides in both concrete and undisturbed soil. This research achievement could serve as a demenstration for China to develop guidelines for safety process system analysis, and provide reference for other near surface disposal facilities to conduct safety process system analysis research.

Process design and engineering verification of near-surface disposal of disused radioactive sources

GONG Jie, LV Gang, DONG Zhiqiang, ZHOU Zhaoyu, WU Hong, LI Shiyang, YAN Xu, ZHANG Peipei, XIANG Xiujuan, YAO Zhenyu

RADIATION PROTECTION. 2025, 45(S1): 38-43.

Abstract ( 14 )

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This work is based on the national disused radioactive sources (DRS) centralized storage repository and the Northwest Low and Intermediate Radioactive Solid Waste Disposal Site. The engineering verification of DRS disposal was carried out for the first time. Through retrieval, verification, encapsulation and barrel fixation of 1 102 Class Ⅳ and Class Ⅴ DRS, packages that meet acceptance requirements of the disposal site were formed and disposed. The conditioning and disposal process of DRS for the purpose of disposal was established. The feasibility and rationality of the process flow of DRS retrieval, verification, conditioning and disposal were verified, which laid a technical foundation for the next large-batch and higher activity DRS disposal in China.

Design optimization of the process scheme for phase I, stage II construction project of a low and intermediate level radioactivite solid waste disposal repository

ZHOU Wenbo, GUO Yitian

RADIATION PROTECTION. 2025, 45(S1): 44-51.

Abstract ( 10 )

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A low and intermediate level solid radioactive waste disposal repository phase I, stage I project is about to complete all the disposal units of low-level solid waste disposal tasks. In order to ensure that low and intermediate level solid radioactive waste produced by nuclear facilities in the southwest region is timely and properly disposed of, it is very necessary and urgent to carry out the phase I, stage II construction projects. In the design stage of the phase I, stage II construction project, the process plan research is carried out in view of the problems existing in the operation of phase I, stage I, such as the low automation level of the waste receiving inspection equipment, incomplete function, lowl efficiency, low volume utilization rate of the disposal unit, and high radiation risk of personnel. By optimizing the process flow, waste inspection, key equipment parameters, waste placement and control room design, the problems existing in the phase I, stage I are effectively solved. The low and intermediate level solid waste disposal repository is designed into a highly digital and intelligent near-surface radioactive waste disposal repository, which effectively improves the construction of china's radioactive waste disposal capacity.

Development of volume reduction device for radioactive waste filter cartridge

XU Wei, LI Huan, RUAN Jiasheng, ZHANG Yu, ZHENG Bowen

RADIATION PROTECTION. 2025, 45(S1): 52-56.

Abstract ( 11 )

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In response to the treatment requirements of radioactive waste filter cartridge, two sets of volume reduction devices for waste filter cartridge have been developed. The first device adopts the "overall crushing and compression" process, which crushes and compresses the waste filter cartridge as a whole. This device significantly reduces the volume of the waste and provides technical support for waste minimization. During the use of the filter, most of the radioactive dust and aerosols are retained on the cartridge material, while the metal shell is lightly contaminated mainly on the surface and can be decontaminated and reused through cleaning. The second device was developed to adopt different treatment measures for the metal frame and cartridge material. The second device uses a step-by-step processing method of "separation and compression". That is, separating the cartridge material and the metal frame, and the cartridge material is reduced in volume through compression, while the metal frame is cleaned of the outer surface by processes such as adhesive removal and wiping, with the aim for clearance or preparation. The waste filter cartridge volume reduction device of separating and compressing the filter cartridge can effectively reduce the volume of the waste filter cartridge, and has the advantages of high automation, good vovlume reduction effect, and high radiation protection effctiveness.

Control algouithm and related data management modules for the feeding cycle chain of ceramic electric melter

ZHU Lingjia, MENG Xiangda, ZHAO Limei, BAO Yin, ZHANG Bo, ZHANG Junlong

RADIATION PROTECTION. 2025, 45(S1): 57-66.

Abstract ( 12 )

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The vitrification process of high level radioactive liquid waste requires a high degree of automation. In this paper, control algorithm and related data management modules for the feeding process of ceramic electric melter is designed. With this design, the automatic,continuous,and stable feeding process of ceramic electric melter is achieved,and the automation level in the vitrification process is improved. Besides, data management modules will record important data of material flow control and feeding cycle parameters. The above design method provides necessary assurance for the stability and reliability of facility operations.

Detrmination of segregation guideline values for ¹³⁷Cs/⁹⁰Sr containing soil waste

SHI Haijiang, ZHU Xinyan, DU Xiaohui, HAN Hongchen, LV Hailei, CHU Lili, MIAO Caixia, WANG Chenyu, SUN Qi

RADIATION PROTECTION. 2025, 45(S1): 67-70.

Abstract ( 16 )

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For radioactive waste containing multiple nuclides with differentt guideline values of specific activities, radioactive soil standard samples prepared with ¹³⁷Cs and ⁹⁰Sr as representative nuclides are utilized to determine measurement and segregation guideline values. This paper introduces the followings: methodological principles, implementation procedures, validation criteria, and practical applications.

Discussion on the current situation and solutions of ventilation systems in nuclear facilities

WANG Yikang, DOU Yichang, WU Qingdong, DUAN Yujian, XUE Xiangming, ZHAN Jingming

RADIATION PROTECTION. 2025, 45(S1): 71-75.

Abstract ( 9 )

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At present, problems in the ventilation system of nuclear facilities occur from time to time. In order to understand the current situation of China's nuclear facility ventilation system and reduce the impact of radioactive dust and aerosols, chemical harmful factors, high temperature and other hazards on human health, this paper takes a nuclear fuel element plant as an example to summarize some possible problems in the whole process (design review stage, construction and installation stage, commissioning stage and operation and maintenance stage) of ventilation system in nuclear facilities in China, and puts forward some improvement solutions. It can be seen that the environmental quality of China’s nuclear facilities need to be further improved. Facility operaters need to pay more attention to plant ventilation management, rectify possible hidden dangers as soon as possible, ensure efficient operation of ventilation facilities, so as to improve air environment in the plant and reduce the incidence of occupational diseases.

Emergency exposure situations and protection requirements in for basic standards

ZHANG Jiangang, LI Guoqiang, YANG Yapeng, FENG Zongyang, JIA Linsheng, WANG Ning, LIANG Boning

RADIATION PROTECTION. 2025, 45(S1): 76-81.

Abstract ( 13 )

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This article introduces the overall requirements for emergency exposure, emergency management system, public exposure, emergency worker exposure, and the transition from emergency exposure to existing exposure in Radiation Protection and Safety of Radiation Sources—International Basic Safety Standards. This article also introduces the changes in the standard of Preparedness and Response for a Nuclear or Radiological Emergency published by the IAEA in November 2015, and puts forward suggestions for revising China's national standard of Basic Standards for Protection against ionizing radiation and for the Safety of Radiation Sources.

Conceptual framework for constructing an AI-based learning platform for radiation protection standards

MAO Yanzhe, MA Yuefeng, LIU Kai, ZHAO Kaijie, WANG Xiaofeng, GAO Jiaxin, Wu Yao, HAN Fangjie, KONG Xiaona, LIU Xiaoming, ZHENG Jianguo, ZHAO Huaipu

RADIATION PROTECTION. 2025, 45(S1): 82-84.

Abstract ( 14 )

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This article proposes a concept for the construction of an intelligent learning platform based on artificial intelligence algorithms, aiming to improve learning efficiency, understanding depth, and application effectiveness of radiation protection standard. AI driven learning platforms utilize natural language processing technology to transform standard text into more understandable language, providing various forms of resources such as charts, videos, and interactive cases. Generative artificial intelligence can support conversational learning and help learners better understand the content. The learning platform can automatically generate personalized learning paths based on learners’ background, job requirements, and learning progress, track their learning situation in real time, provide personalized feedback and evaluation, and dynamically optimize learning content and strategies. With the continuous advancement of artificial intelligence technology, learning platforms could be sustainably optimized.

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