Table of Content

20 April 2024 Volume 44 Issue 2

  

Overview

Status of routine monitoring methods for internal radiation contamination of transuranic nuclides in urine

SUN Yi, LUO Maoyi, WU Yang

RADIATION PROTECTION BULLETIN. 2024, 44(2):  1-7. 

Abstract ( 31 )   PDF (772KB) ( 19 )  

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For the purpose of radiation protection, individual monitoring of internal exposure provides the necessary means to protect occupational safety and health of nuclear workers. The most commonly used methods for routine monitoring of transuranic nuclides are in vitro measurements of those concentration in urine samples. Due to the interference from complex matrix and extremely low emission of transuranic nuclides in urine, accurate measurement of ultra-low level of transuranic nuclides in urine remains a major bottleneck. In this paper, the routine monitoring methods of transuranic nuclides for internal radiation contamination was investigated, and the difficulties and bottlenecks were pointed out in view of the research progress of radiochemical analysis methods and measurement techniques.

Ariticles

Study on radiation protection during the overhaul of HTR-PM spent fuel storage system

LEI Weijun, SHI Jin, DING Ming, HUANG Shulong

RADIATION PROTECTION BULLETIN. 2024, 44(2):  8-14. 

Abstract ( 34 )   PDF (4980KB) ( 29 )  

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In order to address the radiation protection during equipment maintenance and overhaul of HTR-PM high-temperature gas-cooled reactor (HTGR) spent fuel storage system, a three-dimensional model of the spent fuel storage tank and its related compartments was established. The gamma dose rate at staff maintenance location was calculated using the Monte Carlo method. The results show that: the dose rate decreases rapidly with the increase of the distance between the assessed point position and the opening of the concrete platform; due to the existence of holes on the shielding cover and the concrete floor slab, a high dose rate directly above the holes on the concrete platform of the spent fuel loading room was found. Considering the 2-fold safety coefficient, the dose rate is in the range of the red zone around 50 cm from the center of the holes, and the entry of personnel into the area should be strictly limited; the point of radiation protection in the service equipment room is in the range of 30-70 cm from the center of the holes. The dose rate within 30-70 cm from the center of the maintenance equipment room is in the restricted working area (orange zone), and the working time of the personnel in this area should be as short as possible. In order to ensure safety, it is recommended to carry out physical simulation training and shorten the working time, to set up a temporary shield of lead sand not less than 16 cm and protective equipment, and to decontaminate the local hot spots to reduce the intensity of the source term.

Study on material selection of endoscopic window glass in shielding enclosure

ZHANG Changjie, MA Zhanying, LI Kun

RADIATION PROTECTION BULLETIN. 2024, 44(2):  15-20. 

Abstract ( 21 )   PDF (8314KB) ( 5 )  

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Traditional endoscopic windows of shielding enclosures are often made of radiation resistant optical glass. However, this type of glass is brittle and the breakage risk of large glass is high. Therefore, it is necessary to select glass that is more suitable for large endoscopic windows from commonly used glass. This article focuses on PC galss, PMMA and K509. γ irradiation and neutron irradiation tests were conducted to compare the changes in color and transmittance of various materials. The tensile, bending, and impact resistance of glass before and after γ irradiation were analyzed. It was found that PC glass possessed high transparency, good toughness, and excellent impact resistance, which was a more suitable material for large endoscopic windows. This study could provide reference for similar shielding enclosure designs in the future.

Management

Status and suggestions on radiation safety regulation of nuclear technology utilization in a northern city

LIANG Yunping, JU Zhihao, ZHANG Jingchen, YU Guanghui

RADIATION PROTECTION BULLETIN. 2024, 44(2):  21-24. 

Abstract ( 26 )   PDF (1452KB) ( 17 )  

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This study analyzes the current status and characteristics as well as the development trend of nuclear technology utilization in a northern city. This study also analyzes the problems in radiation safety regulation in the city and proposes corresponding countermeasures and suggestions to improve the efficiency of radiation safety regulation.

Experiences

Assessment of radiation protection and safety management at Hongyanhe Nuclear Power Plant (2012-2021)

ZHANG Weihua, ZHANG Mingrui, ZHAO Yanpeng, QIU Wenhong, YANG Yue, GUO Haifeng, Ding Zhibo

RADIATION PROTECTION BULLETIN. 2024, 44(2):  25-30. 

Abstract ( 30 )   PDF (2449KB) ( 12 )  

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This paper introduces the radiation protection safety management system of Hongyanhe Nuclear Power Plant, and presents the statistical results of the individual dose report of the nuclear power plant from 2012 to 2021. Analysis and evaluation on the proportion of collective dose for overhauls and the main population as well as job types receiving collective dose were conducted. Important anomalies related to radiation protection management and the causes were analyzed. The results showed that the control of occupational exposure dose of Hongyanhe nuclear power plant met the national standards while operating safely and stably. Contractors contribute the most part of collective dose radiation exposure. The largest contribution to the collective dose comes from overhaul, mechanical maintenance, main insulation maintenance, ect. Radiation protection management should focus on relevant activities during the overhaul and contractors management.

Application practice of domestic electronic personal dosimetry monitoring system in a nuclear power plant

LI Hui, YANG Haoran, XIE Jiangshan

RADIATION PROTECTION BULLETIN. 2024, 44(2):  31-34. 

Abstract ( 26 )   PDF (4183KB) ( 9 )  

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This paper studied the development status and existing problems of electronic personal dosimetry monitoring systems in domestic nuclear power plants. This paper also introduced the optimization practices of the large-scale domestic electronic personal dosimetry monitoring system which was first applied in a nuclear power plant in terms of data interface, electronic personal dosimer distribution and application, access control management for radiation protection control areas, the function of personal dose management software, natural background radiation deduction, and the overall application effect of the system. Suggestions on design improvement of domestic electronic personal dosimetry monitoring systems were put forward.