RADIATION PROTECTION BULLETIN

Analysis and Suggestions on Radiation Safety Risk Control for Nuclear Power Plants

Peng Hui, Zhou Qifu, Wang Xiaotao, Zhou Xiaojian

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 3-6.

Abstract ( 46 )

PDF (1528KB) ( 27 )

References | Related Articles | Metrics

During the construction, operation and refueling overhaul of nuclear power plants, it is necessary to use a large number of radiation sources such as radioactive sources and radiation-emitting devices for flaw detection and other detection activities. In view of the numerous organizations responsible for managing and using radioactive sources and radiation-emitting devices in nuclear power plants, the complex working environment and limited conditions for radiation protection, radiation safety risks cannot be ignored. The whole process control of high risk sources and a new model of radiation safety license are conducive to reducing the radiation safety risks of nuclear power plants.

Management of Radiation Safety for Nuclear Technology Application in Nuclear Power Plant

Wu Huiyuan, Ma Xi

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 7-12.

Abstract ( 41 )

PDF (711KB) ( 35 )

References | Related Articles | Metrics

Industrial applications of nuclear technology have been widely used in nuclear power plants. This paper systematically introduces these applications and discusses their characteristics in nuclear power plants. By combining nuclear facility operation with nuclear safety management system, the concepts, methods and measures could be further improved and optimized, so as to improve the management of nuclear and radiation safety in nuclear power plants.

Summary of Experience in the Tangible Construction ofRadiation Safety Culture in a Nuclear Power Plant

Zhang Wenxian, Guan Xiaoqiang, Zhou Zhili

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 13-16.

Abstract ( 38 )

PDF (677KB) ( 16 )

References | Related Articles | Metrics

Based on the investigation results of radiation safety culture in a domestic nuclear power plant, and according to the characteristics of radiation safety culture and the actual weaknesses identified during the investigation, some new ideas and suggestions on the tangible construction of radiation safety culture in nuclear power plant were put forward from three levels of cognition, identification and practice.

Research and Application of Technology for Reducing Radiation Field in Pressurized Water Reactor Nuclear Power Plant

Huang Xinming, Yang Junwu, Chen Zhiyuan, Li Bo, Duan Xiaoxun, Su Liangliang

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 17-25.

Abstract ( 54 )

PDF (6644KB) ( 28 )

References | Related Articles | Metrics

This paper introduces the general idea of reducing the radiation field in pressurized water reactor nuclear power plant. Based on a number of field practice experience at home and abroad, some specific optimization and improvement measures are put forward, from radiation source term control for reactor unit, the development and application of various radioactive decontamination technology, radiation shielding design and installation, as well as radiation hot spot removal and management. Reducing radiation field is a kind of system engineering, because each kind of radiation field reduction technology has its unique advantages but also has certain limitations. Therefore it is necessary to combine all kinds of technology strategically according to the characteristics of reactor unit, in order to achieve continuous control and comprehensive treatment of radiation field.

Research on Ag-110m Removal Method for Primary Circuit Coolant in Nuclear Power Plant

Wang Wei, Guan Xiaoqiang, Kong Xiangchao

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 26-29.

Abstract ( 30 )

PDF (1409KB) ( 21 )

References | Related Articles | Metrics

Ag-110m is an activated corrosion product. Ag-110m occures in the primary circuit system of many nuclear power plants at home and abroad, which contributes greatly to the radiation level. In this paper, the characteristics, form, influence and source of Ag-110m are analyzed. The treatment measures of Ag-110m in domestic power plants are investigated and summarized, which provides some ideas and methods for the removal of Ag-110m in nuclear power plants.

Experience and Improvement in Safety Supervision of Radiographic Inspection in Nuclear Power Plants

Sang Yanjie, Zhang Xueguang, Wang Wei, Guan Xiaoqiang, Chen Liang

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 30-36.

Abstract ( 34 )

PDF (1424KB) ( 95 )

References | Related Articles | Metrics

As a common industrial nondestructive testing technology, radiographic testing has ionizing radiation risk during the process of use. If the operation is improper, it will cause over dose exposure accident. Radiographic testing technology is widely used in pre-service and in-service inspections of equipment pipelines and pressure vessels in nuclear power plants. This kind of operation mainly uses movable type of radiographic testing equipment, which poses radiation risks during the storage, transportation, and operation of the equipment. On the basis of summarizing historical events and experiences, a nuclear power plant has drawn some conclusion about the radiation risk factors of radiographic testing, and improved the risk management and safety supervision of radiographic testing. The application of the improved risk management and safety supervision has achieved good results so far, ensuring the radiation safety of radiographic testing workers and the public.

Performance Analysis and Design Optimization of Primary Neutron Source Container for a Third-Generation Reactor

Li Xiaoning, Ma Boyang, He Weihua

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 37-41.

Abstract ( 28 )

PDF (1304KB) ( 22 )

References | Related Articles | Metrics

Primary Neutron source provides sufficient initial neutron flux for reactor before criticality, which is a necessary condition for the first start-up of PWR. The measured surface dose rate of neutron source shielding container of a third-generation PWR is relatively high, which could affect the safety of personnel and equipment to a certain extent. In order to reduce the radiation level, Monte Carlo method is used to establish a model for calculation, to evaluate the performance of the neutron source shielding container, and to propose an improvement plan for the shielding container in combination with neutron energy spectrum analysis. It is expected to reduce radiation levels by 99.5% while ensuring only a small increase in volume and satisfying transportation performance.

Investigation of a Source Term Abnormal Event in a Nuclear Power Plant

Li Jianlong, Jiang Weiwei, Li Yanpeng, Long Lin, Guo Fei, Chen Ziliang

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 42-50.

Abstract ( 44 )

PDF (7906KB) ( 8 )

References | Related Articles | Metrics

The radiation level of a reactor unit of a domestic power plant during overhaul is high. The cumulative collective dose during overhaul is also high. When descending to the hot stop platform the radiation index of the RCP system is very high. mainly for radionuclide Co-60. The overall radiation index after oxidation and purification is relatively high. Compared with the other three reactor units, the overall radiation level of the reactor unit under overhaul is at the highest level. This paper mainly introduces the causes for the high radiation source of the reactor unit and the investigation process.

Radiation Risk Control for Salvaging Foreign Object in the Reactor Pool of Nuclear Power Plants

Wang Wen, Zhang Xueguang, Wang Wei, Guan Xiaoqiang, Sang Yanjie, Huang Qianqian

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 51-56.

Abstract ( 38 )

PDF (4230KB) ( 11 )

References | Related Articles | Metrics

There are risks of radioactive pollution diffusion and external radiation exposure during the salvage process of foreign objects in the primary circuit of nuclear power plants, especially for metal foreign objects activated by neutrons. There may be risks of over-dose exposure of personnel during the salvage process. This paper mainly discusses the radiation risk control of foreign objects emerging from primary circuit. This paper also analyzes the source, classification, and emerging risk of foreign objects in primary circuit, and calculates the impact of primary circuit foreign objects emerging with different radiation levels on the workplace through related software modeling. Corresponding radiation risk protection and control measures according to the degree of impact are formulated, which could provide a protection plan for conducting related work.

Application Practice of Source Term Investigation Technology in a Source Term Anomaly Analysis in a Nuclear Power Plant

Chen Bin

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 57-61.

Abstract ( 42 )

PDF (3370KB) ( 42 )

References | Related Articles | Metrics

Source term investigation technology has been widely applied in nuclear power plants both domestically and internationally. The information obtained from source term investigation, such as radionuclide types, surface contamination activity, and contribution ratio of radionuclide dose rate, is important source term basic data. These data provide important support for the development of source term control strategies, the analysis of source term anomalies, radiation shielding design, and archiving reactor unit source term information. This article introduces the source investigation of a CPR1000 unit using the CZT gamma spectrum measurement system and the practical experience of assisting in determining the causes of reactor unit source term anomalies, through the results of source term investigations.

Practice of Radiation Source Term Control During the Operation Preparation for a PWR Nuclear Power Plant

Zhang Jingzhi, Zhao Yanpeng, Song Yunlong, Qu Bing, Xiao Yiming

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 62-66.

Abstract ( 35 )

PDF (2359KB) ( 29 )

References | Related Articles | Metrics

Collective dose is an important indicator of radiation safety for nuclear power plants. There are many factors affecting the collective dose, but the most fundamental one is the radiation source term of nuclear power reactor units. However, the control of source term is not so simple, and the source term is related to many factors such as reactor unit type, loop number, operation cycle, reactor unit operation time, primary circuit equipment material, chemical control process, purification unit capacity, fuel state and so on. Due to the lack of experience and appropriate attention, many factors that could improve source term control in the design, construction, installation and commissioning stage were ignored for most reactor units. In order to make good use of the key stage of operation preparation, related work has been carried out in six aspects: including purification capacity improvement, special washing, cleaning and decontamination, special test tracking, shielding improvement and comprehensive improvement, in order to minimize the source term level. A lot of valuable data and experience for the source term control has been accumulated through this work.

Synthesis and Characteristics of Crown Ether Resin for Depleted Zinc Separation

Li Chengxin, Su Xingdong, Zhan Jie, He Ye, Li Xuefei, Li Jiawen, Liu Feng, Xue Yi, Zu Jianhua

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 67-74.

Abstract ( 37 )

PDF (7650KB) ( 21 )

References | Related Articles | Metrics

PS@DB18C6 crown ether resin based on polystyrene and dibenzo-18-crown ether-6 was synthesized by poly-condensation method, and its stability, adsorption and desorption mechanism and characteristics were explored. Then Zinc isotopes separation experiment by column chromatography was carried out. The results showed that PS@DB18C6 crown ether resin has large adsorption capacity in acetone solution at pH=7. The adsorption model of Zinc ion is a quasi-first-order kinetic equation, and the desorption of α-hydroxyisobutyric acid (AHIB) solution at pH=3 satisfies the first-order kinetic equation. PS@DB18C6 crown ether resin can maintain good structural stability during adsorption and desorption. Zinc isotopes can be effectively separated by column chromatography with PS@DB18C6 crown ether resin. After the leaching operation of 5 m chromatographic column, the maximum front-end enrichment values (β) of ⁶⁶Zn and ⁶⁸Zn are 1.019 6 and 1.020 8 respectively.

Research and Development of Access Authorization Between Reactor Units in Radiation Control Area of Nuclear Power Plant

Yu Ru, Zhang Xueguang, Wang Wei, Hu Lue, Yang Yiqiang

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 75-79.

Abstract ( 18 )

PDF (7094KB) ( 6 )

References | Related Articles | Metrics

Through the in-depth study of the control logic of access monitoring system in the radiation control area, the method of combining unified authorization of radiation workers and the authorization of the working sub-unit in nuclear power plants to clearly limit the radiation activities to the corresponding reactor units is explored. The focus is on the methods and applications of solving the radiation control division unit authorization. Experiments were made to systematize the monitoring of access to the radiation control areas.

Networking Improvements to the Monitoring System for Control Area Access in Nuclear Power Plant

An Shifeng, Li Xiuchuan, Yang Jingping, Sun Bo, Zhang Jingzhi

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 80-85.

Abstract ( 28 )

PDF (8024KB) ( 10 )

References | Related Articles | Metrics

Taking the renovation project of the nuclear power plant as an example, on the basis of the monitoring system for the control area access in the existing operating nuclear power plant, the on-site operating equipment is networked, in order to carry out renovation and increase the corresponding centralized control management software. By adding a video acquisition module to collect the facial information of the personnel whoes contamination is measured, realizing real-time monitoring of the equipment state on site and the response of the personnel after equipment alarm, so as to improve the radiation safety control capability on site. This work will provide a good reference for upgrading and optimizing the network of access monitoring systems and similar systems in the control area in nuclear power plants.

Research Progress of Management Technology for Waste Source Control in Nuclear Power Plant

Han Xu, Gao Chao, Liu Jianqin, Guo Xiliang, Yan Xiaojun, Wan Yong, Xi Yahui, Qin Xiang

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 86-91.

Abstract ( 34 )

PDF (1234KB) ( 155 )

References | Related Articles | Metrics

The waste source control management technology for nuclear power plant operation is a key measure to achieve radioactive waste minimization. This paper introduces waste source control measures and methods from the perspective of waste generation control, clearance management, recycle and reuse. Through the analysis of waste source control management technology for nuclear power plant operation, this paper discusses good practice of waste source control management technology in recent years in China. Consideration and suggestions of waste source control management and radioactive waste management for domestic nuclear power plant operation are put forward.

The Key Technology for Quality Control of Radiotherapy Construction Project Evaluation

Zhang Zaoqin, Yang Huiping, Xu Zhiqiang, Geng Jiwu, Li Lichun, Su Shibiao

RADIATION PROTECTION BULLETIN. 2023, 43(3-4): 92-95.

Abstract ( 46 )

PDF (961KB) ( 30 )

References | Related Articles | Metrics

This paper expounds the necessity of quality control in the evaluation of occupational disease hazards from the construction project of radiation diagnosis and treatment. According to the relevant regulations and standards, the knowledge of radiation hygiene and the experience of evaluation, the key techniques for quality control in the main evaluation stages are put forward, including contract signing, Evaluation Program Preparation, data collection and audit, on-site investigation, on-site testing and evaluation report preparation. Radiation health technical service organizations can draw on the experience of other organizations and their own reality, develop effective quality control procedures and operational guidelines, to ensure the traceability of evaluation data and credible conclusions, in order to standardize the service behavior of radiation health technology and improve the quality control ability of provincial institutions.

Table of Content