Table of Content

20 August 2016 Volume 36 Issue 4

  

Discussions on Implementation of Non-radioactive Liquid Waste Discharge Standards in NPPs

Yu Fan, Zhang Lingyan, Li Yong, Li Wenhui

RADIATION PROTECTION BULLETIN. 2016, 36(4):  1-8. 

Abstract ( 31 )   PDF (2096KB) ( 13 )  

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The applicability of existing sewage discharge standards for non-radioactive liquid waste water in nuclear power plants is discussed, in view of the characteristics of such a waste. Discharge standard of pollutants for municipal wastewater treatment plant (GB 18918-2002)is suggested to be based mainly, at present stage, to perform such an emission. A further proposal is that it is necessary to carry out research and preparation of non-radioactive liquid waste discharge standards for nuclear power plants.

Current Status of Radioactive Waste Management in Russia

Kong Qingjun, Li Feng, Zhu Jie, Zhao Mi

RADIATION PROTECTION BULLETIN. 2016, 36(4):  9-16. 

Abstract ( 21 )   PDF (2400KB) ( 15 )  

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On basis of an introduction to radioactive waste management system, regulation, classification and the status quo in Russia, the experience and current existing problems are summed up and analyzed.It is expected to provide reference for China's radioactive waste management.

Karlsruhe Reprocessing Plant Decommissioning and Its Implications

Xin Pingping

RADIATION PROTECTION BULLETIN. 2016, 36(4):  17-22. 

Abstract ( 33 )   PDF (1649KB) ( 19 )  

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An introduction to decommission experiences of WAK is presented, with respect to the strategy, cost, process, technology, radiation protection for dismantling, and waste management.

Design Verification of a 200 L Microwave In-drum Drying Devicefor Spent Resin

Gao Chao, Jia Meilan, Gao Shuai

RADIATION PROTECTION BULLETIN. 2016, 36(4):  23-26. 

Abstract ( 21 )   PDF (4046KB) ( 8 )  

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Based on preliminary tests and data analysis, combined with the measured temperature and electric field distribution,a 200 L microwave in-drum drying device for spent resin was designed using Ansoft HFSS. Pilot studies indicate that HFSS simulation results can guide practicaldesign work.

Current Situation of Radiation Environmental Monitoring and Suggestions for Its Development in Xinjiang Uygur Autonomous Region

Wang Zhihuang

RADIATION PROTECTION BULLETIN. 2016, 36(4):  27-29. 

Abstract ( 15 )   PDF (726KB) ( 12 )  

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Existing problems of radiation environmental monitoring in Xinjiang are analyzed, based on the status quo and actual situation of the work. Some improvement measures and countermeasures are then putforward.

Radiation and Thermal Effects on the Evolution ofBuffer Material in Geological Repository of High Level Radioactive Waste

Zhao Shuaiwei, Li Honghui, Liu Wei, Jia Meilan, Mao Liang, Yang Zhongtian

RADIATION PROTECTION BULLETIN. 2016, 36(4):  30-34. 

Abstract ( 16 )   PDF (1351KB) ( 11 )  

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Radiation and heat release is the intrinsic feature of high level radioactive waste. Their effect on bentonite performance is of vital importance for the safety assessment of high level waste repository. As a preliminary literature survey of findings on radiation and thermal effect on the performance of engineering barrier material, performance changes ofengineering barrier material at higher temperature (above 100 ℃) is focused inthis paper.

Measurement of ¹⁴C in Liquid Effluents from Ningde NPP

Chen Ligang, Liu Heng, Li Fuping, Li Jing

RADIATION PROTECTION BULLETIN. 2016, 36(4):  35-38. 

Abstract ( 31 )   PDF (954KB) ( 12 )  

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By combining a 1030W total carbon analyzer and a 3180 liquid scintillation counter, a method for measuring ¹⁴C in NPP liquid effluents was established. It was achieved by using the totalcarbon analyzer to have the carbon in sample acidized and oxidized to carbon dioxide, which was then absorbed with a sodium hydroxide solution, and succeeded byliquid scintillation measurement. The method can effectively eliminate interference from other radionuclides, and can accurately determine ¹⁴C activity in the sample. The results show that its overall average recovery was 96.91%,detection limit was 2.07 Bq/L, and, the precision (relative standard deviation)and accuracy (relative error) of measurement results was less than ±5% respectively.

Radiation Monitoring for Recycling of Scrap Metal

He Zeyong

RADIATION PROTECTION BULLETIN. 2016, 36(4):  39-41. 

Abstract ( 15 )   PDF (802KB) ( 12 )  

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The origin of radioactive material inscrap metal is presented, along with the type of radiation given by scrap metaland its products. The principles for monitoring instrument selection, formulation of monitoring scheme, monitoring methods and quality assurance measures are analyzed.