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20 June 2015 Volume 35 Issue 3
Orientation and Connotation of the Discipline of Ionizing Radiation Protection
Zheng Junzheng
RADIATION PROTECTION BULLETIN. 2015, 35(3): 1-5.
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This paper, based on the essential attribute and characteristics of the discipline, is a review of orientation and connotation of ionizing radiation protection subject in the last hundred years. Asa discipline of closely multidisciplinary integration, ionizing radiation protection has been formed by many different names. There is no doubt it is necessaryto define its orientation and connotation, which will be conducive to the construction and development of the discipline.
Investigation of
3
H Activity Concentrations in Environmental Waster Surrounding Taishan and Yangjiang NPPs
Deng Fei, Lin Qing, Zhou Reidong, Qin Lianjing, Wang Jiayue, Li Qiaoqin
RADIATION PROTECTION BULLETIN. 2015, 35(3): 6-11.
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26
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101
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A wide range of investigation was launched in surface water, drink water, sea water, rain water, water vapor for the present of
3
H in the environment surrounding Taishan and Yangjiang NPPs during 2010-2011. Water samples were electrolyzed with homemade electrolytic enrichment device before measurement. It has been shown the activity concentrations of
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H are, respectively, 0.23±0.04 Bq/L in surface water, 0.22±0.04 Bq/Lin drinking water, 0.22±0.06 in sea water, and 0.25±0.08 Bq/L in rain water, nearly at the same level.
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H activity concentrations in water vapor is 0.37±0.17 Bq/L,negatively related to air humidity.
Beta Surface Activity Response Calibration of Hand Detectors in a Hand-Foot Surface Contamination Monitor
Wang Yong, Liu Bei, Niu Qiang, Li Qiang, Feng Mei, Shang Jie
RADIATION PROTECTION BULLETIN. 2015, 35(3): 12-15.
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24
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61
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Hand-foot surface contamination monitors are usually used in nuclear facilitiesfor radiation protection purpose, which measure surface contamination levels onworkers' hands and feet. A hand model and two plastic film sources were made to facilitate the calibration of surface activity response of hand detectors in amonitor of this kind, and give rise to calibration results more in line with actual measurements. The effects of beta backscatter from hand tissue on measurement were investigated. The calibration results with aluminum substrate sources used were employed to perform a comparison in the meantime. Their difference was then analyzed.
Management and Recycling of Uranium Containing CaF
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Sludges
Li Yang, Yang Jie, Lian Bin, Zhao Yangjun, Chen Hailong
RADIATION PROTECTION BULLETIN. 2015, 35(3): 16-18.
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27
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50
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Uranium containing CaF
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Sludges comefrom treatment of wastewater with uranium and floride in nuclear fuel cycle facilities. Status quo of management of the sludges in China is presented, along with their potential recycling patterns. A probe on how to strengthen their management and recycling is provided.
Advances in Research of Radiation Induced Bystander Effect and Its Mechanism
Zhang Chaoning, Li Jintian, Liu Yongqi
RADIATION PROTECTION BULLETIN. 2015, 35(3): 19-24.
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48
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Radiation induced bystander effect isa phenomenon that non-radiated cells have the same or similar biological reaction with those radiated cells. A large number of studies show the objective existence of this effect. The paper briefly reviews its research status, in vitro andin vivo, and discusses studies on time-effect and research progress of generation mechanism in the respect.
Experience of In-site Emergency Preparedness for Multi-unit NPPs
Jin Li
RADIATION PROTECTION BULLETIN. 2015, 35(3): 25-28.
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24
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19
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After Fukushima nuclear accident, NPPs' operators in China are requested to implement emergency preparedness aimed atcombine unit accidents. On the basis of IAEA's suggestions and NNSA's requirements on multi-unit sites, such issues as emergency management, determination of accident and emergency states, emergency organizations and their coordination mechanisms, procedures for emergency state level determination, are analyzed in therespect. Capability building to be strengthened is also discussed in this paper. These can inform emergency preparedness management at other domestic nuclear facilities.
Post-closure Scenario Analyses of Low and Intermediate Level Solid Radioactive Waste Disposal Facilities
Zhao Yangjun, Lian Bing, Yang Jie, Chen Hailong, Li Yang
RADIATION PROTECTION BULLETIN. 2015, 35(3): 29-32.
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37
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25
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After a low and intermediate level waste disposal facility is shut down, surveillance will be still in place over fora sustained period. When this period ends, the disposal site could be restrictedor unrestricted released. The public may somehow close contact with the waste disposed of, and be impacted by the radiation contained therein. To estimate thepost-closure effect to environment, it is necessary to analyze and select the Features, Events and Processes that can affect the release and migration of radionuclide, directly or indirectly, from a disposal facility. Based on IAEA findings, post-closure scenario analysis and selection was carried out for a low and intermediate level solid waste disposal facility in China. Preliminary results indicate that the scenarios should be properly chosen on the basis of full investigation.
Discussion on Some Issues in Environmental Radiation Monitoring
Song Haiqing, Huang Naiming, Chen Zhidong, Chen Wentao
RADIATION PROTECTION BULLETIN. 2015, 35(3): 33-36.
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26
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19
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Guangdong Environmental Radiation Monitoring Center (GREC) has been engaged in environmental radiation monitoring since it was established in 1989. Combined with problems encountered in our daily work, such issues as significant digits of measurement results, background subtraction in γ-spectrometry measurement, reporting of data below detection limit, and the evaluation criteria of the results of duplication measurement, re-measurement and inter laboratory comparison are discussed.
Radiation Protection Assessment of a Radiotherapy Facility at a Hospital
Wang Lujie, Yu Zhiwen, Tao Jie, Peng Zheng
RADIATION PROTECTION BULLETIN. 2015, 35(3): 37-40.
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The radiation dose survey of a radiotherapy facility at a hospital, aimed at radiation protection assessment, indicates the machine-room shielding in accordance with the approved scheme upon pre-assessment does not conform to the standard requirements. The assessment agency requested the hospital have it rectified. The shielding thickness is increased asa result. Re-survey of radiation dose confirms that the health and safety of therapists and the public is able to be guaranteed under normal operation condition of the accelerator.
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