RADIATION PROTECTION

Modified Mathematic Model of Low Solubility Nuclide Migration in Porous Media

Wang Tieliang, Zhang Jianxin, Cao Yuan

RADIATION PROTECTION. 2014, 34(3): 129-133.

Abstract ( 11 )

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When the general sorption relations between nuclide concentration dissolving in groundwater and that in solid phase are used to simulating farinose low solubility radioactive waste migration, an unreasonable result that the nuclide concentration in groundwater is larger than its solubility may occur. The model including the reversible linear sorption relation is considered in this paper. The general model is modified by taking the solubility limit into account. A hypothetical calculating example is numerically simulated by the modified model and the general model respectively. The result testifies the rationality of the modified model, that is, the phenomena of nuclide concentration larger than the solubility will not happen even if the initial nuclide concentration in solid phase is very large. When the initial concentration of nuclide is small enough, the simulating result of the modified model is consistent with the result of the general model.

Development of Portable ¹³⁷Cs Irradiation Facility and On-site Calibration

Gao Fei, Xiao Xuefu, Ni Ning, Song Mingzhe, Hou Jinbing, Wang Hongyu

RADIATION PROTECTION. 2014, 34(3): 134-137.

Abstract ( 12 )

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Fixed environmental gamma radiation dose rate monitoring instrument is the main equipment to undertake environmental continuous monitoring tasks, but its inconveniencies in terms of installation and removal, as well as it prolonged submission period (about a week) affects the continuity of its continuous monitoring data. For the on-time calibration of the instrument, a portable ¹³⁷Cs irradiation device was developed using the Monte Carlo method with PTW dosimeter being adopted to measure dose rate of the radiation field. Finally, the portable irradiation device was used to calibrate on-site the fixed environmental gamma radiation dose rate monitoring instrument.

Research on a New Process for Cement Solidification of NPP Radioactive Borated Spent Resin

Zhao Ying, He Xiaoping

RADIATION PROTECTION. 2014, 34(3): 138-146.

Abstract ( 8 )

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In order to improve the resin cement solidified waste for boron tolerance rate, by changing the curing formulations, field solidification studies were carried out at the radioactive waste disposal systems of Daya Bay Nuclear Power Plant (GNPS) and Ling Ao Nuclear Power Plant (LNPS). Results show that the spent resin inclusive rate increased from 32.4% to 46.3%, improved 42.9%, solidified volume decreased by 30%. Performance of the solidified waste satisfies the requirements of GB 14569.1—2011. Six years of engineering practices have proved that the improved cement solidification process can be used in nuclear power plants curing system without changing the original facility situation.

Development of Calculation Program for Allowable Residual Concentration in Soil and Environmental Dose

Liao Haitao, Li Xia, Xia Yihua

RADIATION PROTECTION. 2014, 34(3): 147-151.

Abstract ( 4 )

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Allowable residual concentration in soil is one of the important bases guiding the engineering design, implementation and management. It involves many aspects, such as safety, economy, technique feasibility and social influences, etc. The paper introduces the physical model and developing concept for the calculation program of allowable residual concentration in soil and environmental dose, and a demonstrative calculation is also presented with analysis at last.

An Algorithm for Reconstructing Radiological Contamination Distribution

Liu Ruirui, Xiao Xuefu, Yu Xiumei

RADIATION PROTECTION. 2014, 34(3): 152-156.

Abstract ( 6 )

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A reconstructing algorithm based upon the data taken by the low altitude measuring system is introduced in this paper. The algorithm reconstructs the radiological contamination distribution through solving the detection response factor equation set (DRFES). The study shows that the reconstructing algorithm performs well when the detection height is lower than 50 meters.

The Standard Comparison for Gamma-rays Air Kerma 2012

Song Xiaojing, Xiong Xuya, Su Chunlei, Quan Lin, Miao Liangliang,Yu Xiaoren, Pan Xiaobing, Ma Yan

RADIATION PROTECTION. 2014, 34(3): 157-161.

Abstract ( 5 )

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The standard comparison for Air Kerma of γ-rays with attendance of seven participants organized by the Metrology and Test station of Northwest Institute of Nuclear Technology in 2012 was introduced. According to existing conditions, each participating laboratory chose the ionization chamber of appropriate range to accomplish the comparison. The experiment data of comparison indicate that the deviations between measurement values and reference values are within the reasonable expectation, the results are considered satisfactory.

Performance Assessment of Gamma-ray Monitors for Radiation Protection Monitoring in China

Wei Yingjing, Meng Yanjun, Ke Haipeng, Zhao Pengfei, Gu Weigang, Zhang Qingli

RADIATION PROTECTION. 2014, 34(3): 162-167.

Abstract ( 10 )

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According to the national standard GB/T 4835—2008 and the verification regulation JJG 393—2003 for radiation protection instrumentation, 40 radiation protection γ monitors of different types were tested using X and γ reference radiation devices of the radiation metrology station of China Institute for Radiation Protection (CIRP). Judging by the test results of these monitors in terms of repeatability, relative intrinsic error, energy dependence of response, angle dependence of response, and alarm sound, it is known that about 50% of these monitors fails to meet the standards.

Apoptosis in HaCaT and Bad Pathways

Xue Zhenan, Huang Xin, Cao Di, Chen Jin, Huang Kun, Chen Aijun

RADIATION PROTECTION. 2014, 34(3): 168-171.

Abstract ( 8 )

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To study the mechanism of low-doses of ultraviolet B (UVB, 280—315 nm) on human immortalized cells (HaCaT cells) apoptosis, proliferation and Bad pathway, chose the most suitable 5 mJ/cm² intensity of UVB from 3,5 and 7 mJ/cm²to irradiate the HaCaT cells for 18, 36 and 72 hours, then, collected the cells for the detection of apoptosis and proliferation; The total protein in HaCaT cells was extracted from the irradiated cell for western blot to detect the expression of AKT, Bad and the Bad-p136. The results showed that the apoptotic effects of 5 mJ/cm² intensity irradiation on HaCaT cells have no distinguish difference among different time point. But the proliferation rate after 72 hours irradiation on HaCaT cells was significant higher than control group. Immunoblotting experiments confirmed the expression levels of AKT and Bad-p136 were significant increasing compared to normal expression of Bad protein after UVB irradiation. Therefore, a long time UVB radiation of 5 mJ/cm² may promote cell proliferation signaling pathway by Bad, which may be a potential risk factor for the development of skin tumors.

Analysis of Access Management for Control Area in PWR Plant

Yin Wei

RADIATION PROTECTION. 2014, 34(3): 172-176.

Abstract ( 7 )

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The paper reviews the access requirements of radioactive control area in NPP, and introduces the access process of CPR1000 as well as the international advanced access control mode “EVEREST”. The access management of radioactive control area for CPR1000 NPPs based on radiation zoning requires outer-layer clothes off first and then radiation protective clothing on before entering into the control area, which is complicated comparing with the “EVEREST” mode, which bases on contamination zoning and evolves towards an entrance without universal dress. “EVEREST” needs exact contamination partition, and adopts different radiation wear and access process for each zone. Its purpose is to simplify the NPP radioactive control area access. By comparison, EVEREST is found a good applicability for the recast of in-service PWR NPPs.

Application of R&D 128 and ERICA Model in Calculating Radiological Dose of Terrestrial Biota

Bai Xiaoping, Wang Xiaoliang, Du Hongyan, Mao Yawei, Zheng Wei

RADIATION PROTECTION. 2014, 34(3): 177-182.

Abstract ( 6 )

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The R&D 128 and ERICA are models recommended by the Environment Agency of England and Wales and European Commission respectively in assessing non-human species radiation dose. Comparisons and analyses were made on aspects such as the calculation principal of terrestrial biota radiological dose, nuclide types, reference biota types and computation parameters. By adopting the two models, radiation doses of terrestrial biota near a Chinese AP1000 nuclear power plant were calculated with their computation results and merits being compared and analyzed at last.

Study on the Impregnation and Drying Process ofNuclear-grade Activated Carbon in Vacuum Condition

Hou Jianrong, Shi Yingxia, Li Yongguo, Xu Lutong, Qiu Dangui, Kong Haixia, Qiao Taifei, Han Lihong

RADIATION PROTECTION. 2014, 34(3): 183-186.

Abstract ( 5 )

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The technics of nuclear-grade activated carbon impregnated and dried in vacuum condition were studied in this paper. The process was compared with that in ambient condition. Experimental results show that KI and TEDA were easily absorbed by activated carbon in vacuum condition along with small loss of impregnant and high efficiency of drying process. The large-scale process of nuclear-grade activated carbon impregnating and drying were established based on the experimental results, and the results can also be used as a basis for designing such process.

Discussions on Radioactivity Limits for Waste Water in National Emission Standards of Pollutants from Rare Earths

Jin Wenlong, Deng Fei, Cheng Xiaobo, Zhang Yanjin, Chen Wentao, Mo Guanghua

RADIATION PROTECTION. 2014, 34(3): 187-192.

Abstract ( 7 )

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Due to the existence of radium along with uranium and thorium in waste water, the truth of radioactivity limits for waste water set in GB 26451—2011“Emission Standards of Pollutants from Rare Earths” was questioned. Referencing to the GB 23727—2009 “Regulations for Radiation and Environment Protection in Uranium Mining and Milling”, the paper suggests an inclusion of Ra series in GB 26451—2011, with specific limits as U 0.03 mg/L, ²³²Th, ²²⁸Ra, and ²²⁶Ra is 1.0, 0.1 and 1.0 Bq/L respectively in waste water from product line or plant.

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