Table of Content

20 May 2017 Volume 37 Issue 3

  

Research on gamma ray buildup factor for energy absorption based on MCNP

Li Hua, Zhao Yuan, Liu Liye, Xiao Yunshi, Li Junli

RADIATION PROTECTION. 2017, 37(3):  161-168. 

Abstract ( 63 )   PDF (1270KB) ( 265 )  

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Energy absorption buildup factors of common materials were calculated using the Monte Carlo simulation code MCNP. In the calculations, the newer cross section library (MCPLIB04) and mass energy coefficients of common materials have been used with consideration of the bremsstrahlung and correlative scatter. The results were compared with the reference data and the differences were analyzed. It showed that, for the low-Z materials, the values of buildup factors calculated by MCNP were averagely smaller than the reference data for the intermediate γ energies, whilst the calculated values were averagely bigger than the reference data for the high γ energies. For high-Z materials, the calculated results of buildup factors were generally bigger than the reference data. This work could provide updated data for the old buildup factors.

GEANT4 simulation of silicon-on-insulator microdosimeter for monitoring lineal spectra of neutron and gamma mixed field

Lei Ming, Liu Shuhuan, Zong Pengfei, Liu Bing

RADIATION PROTECTION. 2017, 37(3):  169-173. 

Abstract ( 59 )   PDF (1255KB) ( 113 )  

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Lineal energy spectra of novel SOI (silicon-on-insulator) microdosimeter and detector response in Cf-252 neutron and gamma mixed field and Co-60 gamma radiation field were simulated with GEANT4. The simulated results were compared with the TEPC monitoring experiments with good consistency. Some differences are identified and discussed. The effects of different conversion layer thickness on lineal energy spectra were analyzed. Through the simulation, it can be seen that the SOI detector could be used to distinguish the contribution of neutron from gamma. We also found that the thicker conversion layer could increase the peak values of gamma lineal spectra, which may be used for gamma dose measurement at various depth of tissue. These results provide valuable information for the design of the SOI microdosimeter.

Study on dosimetric method of low energy neutron with CR39 solid state nuclear track detector

Cao Lei, Deng Jun, Lan Changlin, Song Yanchao, Ding Xiaowen, Ma Chi, Guo Zeqin, Zheng Yun, Qiu Yutong

RADIATION PROTECTION. 2017, 37(3):  174-179. 

Abstract ( 57 )   PDF (1495KB) ( 104 )  

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A dual-track counting method and a detector structure for measuring low energy neutrons (energy below 0.5 eV) with a solid state nuclear track detector are described. The detector track density per unit area induced by low energy neutron was analyzed by both Monte Carlo simulation and field experiments. The results showed that the dual-track counting method achieved the response of CR39 to low energy neutrons, suggesting that individual dose induced by low energy neutron could be estimated with this method. The energy response range of CR39 was extended so that low energy neutrons with fluence of less than 104 could be measured. The dual-track counting method can effectively discriminate the background track for monitoring of personal neutron dose, thus the measurement uncertainty is reduced.

Report on CIRP participitation in international inter-comparison projects organized by US EML

Ren Xiaona, Song Hailong, Han Yuhu, Wang Ruijun, Huang Zhijian

RADIATION PROTECTION. 2017, 37(3):  180-188. 

Abstract ( 37 )   PDF (1029KB) ( 67 )  

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China Institute for Radiation Protection (CIRP) has participated in a quality assessment program organized by US EML for testing the quality of environmental radioactivity measurements from 1997 to 2004. A total number of 43 samples in three different matrices were analyzed, and 212 analytical results were presented. For the evaluation performance, 97% of the results were designated as A (Acceptable) and 3% as N (Not Acceptable). The N (Not Acceptable) results were found for four nuclides in all three sample matrices including ²⁴¹Am, ⁶⁰Co, ⁵⁷Co and ⁵⁴Mn. The evaluation results of this inter-comparison project showed that the efficiency calibration for γ spectrometry analysis at CIRP has been acceptable but the interferences on the low-energy radionuclides has not yet been treated very well.

Determination of ⁴⁰K in environmental water samples by ICP-OES

Cheng Feng, Lin Guan, Liu Zongxiao, Jin Xiaoxiang

RADIATION PROTECTION. 2017, 37(3):  189-192. 

Abstract ( 52 )   PDF (966KB) ( 56 )  

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A method for the determination of ⁴⁰K in environmental water samples by inductively coupled plasma-optical emission spectrometry (ICP-OES) was established. The detection limit for this method is 0.001 Bq/L with relative standard deviation of less than 1.5% and relative error of less than 4.0%. The recoveries of standard addition is 94.1%—105.5%. The method is a promising candidate for the analysis of ⁴⁰K in water samples due to good linear correlation, low detection limits, high precision, and little interferences.

A preliminary study on wet oxidation of IRN78 anion exchange resin with hydrogen peroxide

Jia Shaoqing, Feng Wendong, Li Xiaolong, Yang Qiaozhen, Guo Xiliang

RADIATION PROTECTION. 2017, 37(3):  193-199. 

Abstract ( 59 )   PDF (1984KB) ( 109 )  

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The conditions of wet oxidation using hydrogen peroxide for nuclear grade IRN78 anion exchange resin were investigated. The pH of anion exchange resin was adjusted with sulfuric acid, and the catalytic effects of Fe²⁺, Cu²⁺, and Fe²⁺/Cu²⁺ on the H₂O₂-anion exchange resin system were compared. The results showed that the mole ratio of 1∶2 for mixed catalysts of Fe²⁺/Cu²⁺ had an excellent catalytic effect, with the degradation rate of IRN78 anion exchange resin up to 99.7%, and the efficiency of hydrogen peroxide up to 92.7%. It indicated that IRN78 anion exchange resin could be degraded effectively by wet oxidation using hydrogen peroxide.

Analysis of ²³⁷Np, ^239+240Pu, ²⁴¹Am, ²⁴⁴Cm in low level liquid waste by alpha spectrometry after TRPO extraction with single amide back extraction

Sun Bin, Meng Jiqun

RADIATION PROTECTION. 2017, 37(3):  200-205. 

Abstract ( 42 )   PDF (1600KB) ( 96 )  

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A TRPO (trialkyl phosphine oxides) extraction-NA (single amide) reverse extraction-electrodeposition method was utilized for the preparation of alpha counting sources to determine the activities of some common radionuclides (e.g.,²³⁷Np, ^239+240Pu, ²⁴¹Am and ²⁴⁴Cm) by alpha spectrometry. The results showed that this method could be effectively applied for the qualitative identification and quantitative measurement of the key alpha emitting radionuclides in emergency monitoring and liquid effluent monitoring.

Experimental study on decontamination of self-crushing decontamination fluid for radioactive dust removal on indoor wall surface

Zhang Kun, He Zeyin, Cao Xingwei, Wang Jianhui, Cui Can

RADIATION PROTECTION. 2017, 37(3):  206-213. 

Abstract ( 92 )   PDF (2007KB) ( 88 )  

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To control and remove radioactive pollution on indoor wall surface, a special injector, a collector and self-crushing decontamination fluid were developed. As a result of performance tests, these specific equipments met the requirements of application considerably well. The decontamination effects of the self-crushing decontamination fluid for radioactive dusts on the surface of concrete, glass, and marble were measured. The results showed that its decontamination efficiency were higher than 85%. Practical applications of this method could be expected.

Effects of salt-inducible kinase 2 on autophagy and apoptosis induced by ionizing radiation

Li Chao, Li Zhongqiu, Li Xueping, Yang Yang, Zeng Yan, Pan Xiujie, Yang Zhihua, Zhu Maoxiang, Gu Yongqing

RADIATION PROTECTION. 2017, 37(3):  214-222. 

Abstract ( 62 )   PDF (2171KB) ( 127 )  

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The purpose of this study is to explore the effects of salt-inducible kinase 2 (SIK2) on autophagy and apoptosis induced by ionizing radiation in the hope of providing a new idea for tumor radiotherapy. Lentivirus LV-GFP and LV-SIK2 were transfected into HeLa cells in vitro. The success of transfection was examined by fluorescence microscopy after 48 h. Real-time PCR and Western blot were used to measure the efficiency of the SIK2 knockdown. After exposure to 8 Gy ⁶⁰Co γ irradiation, the effects of the SIK2 knockdown on autophagy related protein LC3-II and on the P62 expression were examined by Western blot to observe the changes of autophagy. Flow cytometry was performed to examine the effect of the SIK2 knockdown on the apoptosis after 8 Gy ⁶⁰Co γ irradiation. The results showed that the SIK2 knockdown of stably transfected cell line was established successfully. In the down-regulating SIK2 cell line after 8 Gy γ irradiation, the expression of LC3-II was down-regulated while the P62 expression was up-regulated, indicating that autophagy was reduced. Flow cytometric analysis showed that FITC⁺/PI^- cells ratio was already increased significantly at 12 h post irradiation in the down-regulating SIK2 cell line, indicating that the SIK2 knockdown increased the cell apoptosis. In conclusion, the SIK2 knockdown could lead to a significant increase of cell apoptosis induced by ionizing radiation.

Application of ERICA code in radiological impact assessment of terrestrial organisms with IAEA SRS-19 model and XOQDOQ model

Wei Qiming, Du Hongyan, Bai Xiaoping, Zhu Hao, Mao Yawei, Zheng Wei

RADIATION PROTECTION. 2017, 37(3):  223-229. 

Abstract ( 71 )   PDF (1739KB) ( 80 )  

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The IAEA SRS-19 model or site specific medium concentration could be used to calculate the nuclide concentration in environment media in terrestrial organisms radiological impact assessment by the ERICA code, so could the XOQDOQ model. The differences of the IAEA SRS-19 model and the XOQDOQ model are compared in this paper. The two models are used to calculate concentration of nuclides in environment media near a Chinese nuclear power plant and to assess terrestrial organisms radiological impact by the ERICA code. It was concluded that the radiation effects on terrestrial organisms near the site were acceptable by using both models in the ERICA code but the result calculated by the XOQDOQ model was larger.

Recommended concentration limits for consequence assessment of uranium hexafluoride accidental release

Pan Wei, Li Jie, Lian Bing, Kang Jing

RADIATION PROTECTION. 2017, 37(3):  230-234. 

Abstract ( 46 )   PDF (1466KB) ( 56 )  

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Chemical Toxicity of uranium hexafluoride (UF₆) should be evaluated in addition to the effects of radiation in consequence assessment of UF₆ accidental release. The hazard of UF₆ accidental release would be underestimated when the half lethal concentration was used as the criteria for chemical toxicity assessment. In the environmental impact assessment for UF₆ accidental release, the health impact on public surrounding the site of accident should be considered besides the lethality of the released chemicals. Several series of chemical limits have been proposed by EPA, AIHA etc. The protective action criteria values (PACs) proposed by DOE are recommended for consequence assessment of the UF₆ accidental release.

Discussions on redefinition methodologies for emergency planning zone of small reactor

Su Yongjie, Wang Jianhua, Li Wenhui, Zhong Xia, Sun Zhigang

RADIATION PROTECTION. 2017, 37(3):  235-239. 

Abstract ( 51 )   PDF (1539KB) ( 185 )  

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Several methods, including the NUREG-0396 recommended method, probability criterion method and risk-informed method, used in redefinition emergency planning zone (EPZ) of small reactors, and their possible applicability are discussed. The risk-informed method is recommended to define the EPZ of small reactors. Issues including interaction between EPZ and nuclear power plant design, reasonable accident hypothesis, and public psychological factors applied in defining EPZ are discussed and recommendations are given.

Review on the environmental remediation of off-site area after the Fukushima nuclear accident

Zhang Qiong, Wang Bo, Wang Liang, Zhang Chunming, Xu Haifeng

RADIATION PROTECTION. 2017, 37(3):  240-247. 

Abstract ( 99 )   PDF (2812KB) ( 343 )  

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The release and deposition of radioactive materials from the Fukushima nuclear accident was summarized. The policy, regulations, programs and progress on the environmental remediation of off-site area after the Fukushima nuclear accident were introduced. The problems and enlightenments about off-site environmental remediation after nuclear accident were discussed.